Irdf-2002 Dosimetry file - Group data                             2002 0  0    0
 3.00600E+3 5.96340E+0          0          0         34         10 325 1451    1
 0.0        0.0                 0          0          0          6 325 1451    2
 1.00000E+0 2.00000E+7          0          0         10       2002 325 1451    3
 3.00000E+2 0.0                 1          0        237          4 325 1451    4
  3-Li-  6 LANL       EVAL-APR89 G.M.HALE, P.G.YOUNG               325 1451    5
                      DIST-Feb2004                                 325 1451    6
----IRDF-2002         MATERIAL  325                                325 1451    7
-----INCIDENT NEUTRON DATA                                         325 1451    8
------ENDF-6 FORMAT                                                325 1451    9
****************************************************************** 325 1451   10
  3-LI - 6 LANL       EVAL-APR89 G.M.HALE, P.G.YOUNG               325 1451   11
                      DIST-SEP91 REV1-JUL91            19910806    325 1451   12
----ENDF/B-VI         MATERIAL  325         REVISION 1             325 1451   13
****************************************************************** 325 1451   14
  3-LI - 6 LANL       EVAL-APR89 G.M.HALE, P.G.YOUNG               325 1451   15
                      DIST-FEB91                       910201      325 1451   16
----ENDF/B-VI         MATERIAL  325                                325 1451   17
*****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 325 1451   18
DOSIMETRY                                                          325 1451   19
****************************************************************** 325 1451   20
                                                       891221      325 1451   21
----ENDF/B-VI         MATERIAL  325                                325 1451   22
                                                                   325 1451   23
****************************************************************** 325 1451   24
                                                                   325 1451   25
 ***************************************************************** 325 1451   26
 ***************************************************************** 325 1451   27
                                                                   325 1451   28
                  MOD1 OF ENDF/B-VI                                325 1451   29
                                                                   325 1451   30
     The following revisions were made for MOD1 of ENDF/B-VI:      325 1451   31
                                                                   325 1451   32
 1. MF=1,MT=451 - Comments were added regarding estimated          325 1451   33
    (expanded) covariance for the Standards Cross Sections.        325 1451   34
 2. MF=3,MT=53 - LF flag and Q-value corrected.                    325 1451   35
                                                                   325 1451   36
 ***************************************************************** 325 1451   37
****************************************************************** 325 1451   38
                                                                   325 1451   39
                        ENDF/VI EVALUATION                         325 1451   40
                     G. M. Hale and P. G. Young                    325 1451   41
                                                                   325 1451   42
 MAJOR CHANGES FROM VERSION V OF ENDF/B ARE:                       325 1451   43
                                                                   325 1451   44
   1. Inclusion of the ENDF/B-VI standard (n,t) cross section      325 1451   45
      from the simultaneous standards analysis (ca85) over the     325 1451   46
      energy range thermal to 1 MeV.                               325 1451   47
   2. Replacement of all major cross sections and elastic angular  325 1451   48
      distributions at energies between 10^-5 eV and 3 MeV with    325 1451   49
      results from the R-matrix analysis performed in conjunction  325 1451   50
      with the simultaneous standards analysis.                    325 1451   51
   3. Revision of the elastic cross sections and angular distri-   325 1451   52
      butions at energies between 3 and 20 MeV to match recent     325 1451   53
      experimental data, resulting in a general decrease of the    325 1451   54
      elastic cross section in this energy range.                  325 1451   55
   4. Revision of the (n,n')d cross sections to account for        325 1451   56
      recent measurements, resulting in a general increase in      325 1451   57
      the total (n,n')d cross section that tends to offset the     325 1451   58
      decrease in the elastic cross section and maintain about     325 1451   59
      the same total cross section as before.                      325 1451   60
                                                                   325 1451   61
                                                                   325 1451   62
****************************************************************** 325 1451   63
                                                                   325 1451   64
                        STANDARDS COVARIANCES                      325 1451   65
                                                                   325 1451   66
 Phase 1 reviewers of the ENDF/B-VI standards cross sections have  325 1451   67
 expressed the concern that the uncertainties resulting from the   325 1451   68
 combination of R-matrix and simultaneous evaluations might have   325 1451   69
 led to uncertainties that are too small.  As a result, the        325 1451   70
 Standards Subcommittee produced (at the May, 1990 CSEWG meeting)  325 1451   71
 a set of expanded covariance estimates for the standard cross     325 1451   72
 section reactions.  These uncertainties are estimates such that   325 1451   73
 if a modern day experiment were performed on a given standard     325 1451   74
 cross section using the best techniques, approximately 2/3 of     325 1451   75
 the results should fall within these expanded uncertainties. The  325 1451   76
 expanded uncertainties for the Li-6(n,t) cross section are given  325 1451   77
 in the following table and are compared to values from the        325 1451   78
 combined output of the standards covariance analysis:             325 1451   79
                                                                   325 1451   80
    Energy Range    Estimated Uncertainty    Combined Analysis     325 1451   81
      (keV)              (percent)               (percent)         325 1451   82
                                                                   325 1451   83
 1.0E-08 - 0.1               0.3                     0.14          325 1451   84
     0.1 - 1.0               0.5                                   325 1451   85
     1.0 - 10.               0.7                     0.14          325 1451   86
     10. - 50.               0.9                                   325 1451   87
     50. - 90.               1.1                     0.25          325 1451   88
     90. - 150               1.5                                   325 1451   89
     150 - 450               2.0                     0.29          325 1451   90
     450 - 650               5.0                                   325 1451   91
     650 - 800               2.0                     0.36          325 1451   92
     800 - 1000              5.0                                   325 1451   93
                                                                   325 1451   94
 ****************************************************************  325 1451   95
                                                                   325 1451   96
                                                                   325 1451   97
 mf=2 --------- resonance parameters ----------------------------  325 1451   98
                                                                   325 1451   99
   mt=151  effective scattering radius = 2.31175e-13 cm.           325 1451  100
                                                                   325 1451  101
 mf=3 --------- smooth cross sections ---------------------------  325 1451  102
                                                                   325 1451  103
      the 2200 m/s cross sections are as follows:                  325 1451  104
          mt=1     sigma = 941.6928  barns                         325 1451  105
          mt=2     sigma = 0.67157   barns                         325 1451  106
          mt=102   sigma = 0.03850   barns                         325 1451  107
          mt=105   sigma = 940.9827  barns                         325 1451  108
                                                                   325 1451  109
   mt=105        (n,t) cross section                               325 1451  110
       below 3 mev, values are taken from the r-matrix analysis,   325 1451  111
          which includes (n,t) measurements from re78, la78, br77, 325 1451  112
          ov74, and ba75.  between 3 and 5 mev, the values are     325 1451  113
          based on ba75, and at higher energies are taken from the 325 1451  114
          evaluation of pe64, extended to 20 mev considering the   325 1451  115
          data of ke58.                                            325 1451  116
                                                                   325 1451  117
                                                                   325 1451  118
                                                                   325 1451  119
 mf=33----------cross section covariances------------------------- 325 1451  120
                   (to be added later)                             325 1451  121
                                                                   325 1451  122
  the relative covariances for mt=1,2, and 105 below 4 mev are     325 1451  123
  given in file 33. they are based on calculations using the co-   325 1451  124
  variances of the r-matrix parameters in first-order error        325 1451  125
  propogation.                                                     325 1451  126
   mt=1         total                                              325 1451  127
       relative covariances entered as nc-type sub-subsection,     325 1451  128
          implying that they are to be constructed from those for  325 1451  129
          mt=2 and 105.  they are not intended for use at energies 325 1451  130
          above 4 mev.                                             325 1451  131
   mt=2,105     elastic and (n,t)                                  325 1451  132
       relative covariances among these two cross sections are     325 1451  133
          entered explicitly as ni-type sub-subsections in the     325 1451  134
          lb=5 (direct) representation at energies below 4 mev.    325 1451  135
          although values for the 3.95-4.05 mev bin are repeated   325 1451  136
          in a 4-20 mev bin, the covariances are not intended for  325 1451  137
          use at energies above 4 mev.                             325 1451  138
                                                                   325 1451  139
                                                                   325 1451  140
--------------------- references --------------------------------  325 1451  141
                                                                   325 1451  142
ab70  U.Abbondanno, Nuo.Cim. A166,139(1970).                       325 1451  143
aj74  f.ajzenberg-selove and t.lauritsen, nucl. phys. a227,55      325 1451  144
      (1974).                                                      325 1451  145
ar64  a.h.armstrong, j.gammel, l.rosen, and g.m.frye, nucl. phys.  325 1451  146
      52,505 (1964).                                               325 1451  147
as63  v.j.ashby et al, phys. rev. 129,1771 (1963).                 325 1451  148
ba53  m.e.battat and f.l.ribe, phys.rev. 89,80 (1953).             325 1451  149
ba63  r.batchelor and j.h.towle, nucl. phys. 47,385 (1963).        325 1451  150
ba65  r.bass, c.bindhardt, and k.kruger, eandc(e)-57u (1965).      325 1451  151
ba75  c.m.bartle, proc. conf. on nuclear cross sections and        325 1451  152
      technology, vol.2,688 (1975),  and private communication     325 1451  153
      (1976).  see also nucl. phys. a330, 1 (1979).                325 1451  154
be75  besotosnyj et al., yk-19, 77 (1975).                         325 1451  155
br77  r.e.brown,g.g.ohlsen,r.f.haglund, and n.jarmie, phys. rev.   325 1451  156
      16c, 513 (1977).                                             325 1451  157
ca85  a.d.carlson,w.p.poenitz,g.m.hale, and r.w.peele, nuclear     325 1451  158
      data for basic and applied science (santa fe, n.m.), 1429    325 1451  159
      (1985).                                                      325 1451  160
co67  j.a.cookson and d.dandy, nucl. phys. a91,273 (1967).         325 1451  161
co82  h.conde,t.andersson,l.nilsson, and c.nordborg, nuclear data  325 1451  162
      for science and technology (antwerp, belgium), 447 (1982).   325 1451  163
de73  F.Demanins et al., infn/be-73 (1973).                        325 1451  164
dr82  m.drosg,d.m.drake,r.a.hardekopf, and g.m.hale, la-9129-ms    325 1451  165
      (1982).                                                      325 1451  166
dr85  m.drosg et al., santa fe conf.1, 145(1985).                  325 1451  167
fo71  d.g.foster and d.w.glasgow, phys. rev. c3,576 (1971).        325 1451  168
fr54  g.m.frye, phys. rev. 93,1086 (1954).                         325 1451  169
go72  c.a.goulding and p.stoler, eandc(us)-176u,161 (1972).        325 1451  170
ha75  j.a.harvey and n.w.hill, nuclear cross sections and          325 1451  171
      technology (washington, d.c.), 244 (1975).                   325 1451  172
ha84  g.m.hale, nuclear standard reference data (geel,belgium)     325 1451  173
      iaea tecdoc-335, 103 (1984). describes preliminary analysis. 325 1451  174
ho68  j.c.hopkins,d.m.drake, and h.conde, nucl. phys. a107,139     325 1451  175
      (1968), and j.c.hopkins, d.m.drake, and h.conde, la-3765     325 1451  176
      (1967).                                                      325 1451  177
ho79  h.h.hogue et al., n.s.&e. 69, 22 (1979).                     325 1451  178
ju73  e.t.jurney, lasl, private communication (1973).              325 1451  179
ke58  r.d.kern and w.e.kreger, phys. rev. 112, 926 (1958).         325 1451  180
ke79  j.d.kellie,g.p.lamaze, and r.b.schwartz, nuclear cross       325 1451  181
      sections for technology (knoxville, tn.), 48 (1979).         325 1451  182
kn77  h.h.knitter,c.budtz-jorgensen,m.mailly, and r.vogt, eur-     325 1451  183
      5726e (1977).                                                325 1451  184
kn79  h.d.knox,r.m.white, and r.o.lane, n.s.&e. 69, 223 (1979).    325 1451  185
kn83  h.h.knitter,c.budtz-jorgensen,d.l.smith, and d.marletta,     325 1451  186
      n.s.&e. 83, 229(1983).                                       325 1451  187
la61  r.o.lane,a.s.langsdorf,j.e.monahan, and a.j.elwyn, ann.      325 1451  188
      phys.12, 135 (1961).                                         325 1451  189
la78  g.p.lamaze,o.a.wasson,r.a.schrack, and a.d.carlson, n.s.&e.  325 1451  190
      68, (1978).                                                  325 1451  191
li80  p.w.lisowski et al., la-8342 (1980).                         325 1451  192
ma69  d.s.mather and l.f.paine, awre-o-47/69 (1969).               325 1451  193
me65  f.merchez,n.v.sen,v.regis, and r.bouchez, compt. rend. 260,  325 1451  194
      3922 (1965).                                                 325 1451  195
ov74  j.c.overley,r.m.sealock, and d.h.ehlers, nucl. phys. a221,   325 1451  196
      573 (1974).                                                  325 1451  197
pe64  e.d.pendlebury, awre-o-60/64 (1964).                         325 1451  198
pr69  g.presser et al., nuc.phys. a131, 679(1969).                 325 1451  199
re78  c.renner,j.a.harvey,n.w.hill,g.l.morgan, and k.pusk, bull.   325 1451  200
      am. phys. soc. 23, 526 (1978).                               325 1451  201
sa82  e.t.sadowski,h.knox,d.a.resler, and r.o.lane, bap 27,624(c5) 325 1451  202
      (1982).                                                      325 1451  203
sm77  a.b.smith,p.guenther,d.havel, and j.f.whalen, anl/ndm-29     325 1451  204
      (1977).                                                      325 1451  205
sm82  a.b.smith,p.t.guenther, and j.f.whalen, nucl. phys. a373,    325 1451  206
      305 (1982).                                                  325 1451  207
wo62  c.wong,j.d.anderson, and j.w.mcclure, nucl. phys. 33,680     325 1451  208
      (1962).                                                      325 1451  209
****************************************************************** 325 1451  210
                                                                   325 1451  211
                                                                   325 1451  212
                                                                   325 1451  213
                                                                   325 1451  214
****************************************************************** 325 1451  215
                                                                   325 1451  216
 ***************** Program LINEAR (VERSION 2002-1) *************** 325 1451  217
 For All Data Greater than 1.0000E-10 barns in Absolute Value      325 1451  218
 Data Linearized to Within an Accuracy of .100000000 per-cent      325 1451  219
 ***************** Program SIGMA1 (VERSION 2002-1) *************** 325 1451  220
 Data Doppler Broadened to 300.000000 Kelvin                       325 1451  221
 for All Data Greater than 1.0000E-10 barns in Absolute Value      325 1451  222
 Data Linearized to Within an Accuracy pf .100000000 per-cent      325 1451  223
 ***************** Program FIXUP (Version 2002-1) **************** 325 1451  224
 Corrected ZA/AWR in All Sections-----------------------------Yes  325 1451  225
 Corrected Thresholds-----------------------------------------Yes  325 1451  226
 Extended Cross Sections to 20 MeV----------------------------No   325 1451  227
 Allow Cross Section Deletion---------------------------------No   325 1451  228
 Allow Cross Section Reconstruction---------------------------No   325 1451  229
 Make All Cross Sections Non-Negative-------------------------Yes  325 1451  230
 Delete Energies Not in Ascending Order-----------------------Yes  325 1451  231
 Deleted Duplicate Points-------------------------------------Yes  325 1451  232
 Check for Ascending MAT/MF/MT Order--------------------------Yes  325 1451  233
 Check for Legal MF/MT Numbers--------------------------------Yes  325 1451  234
 Allow Creation of Missing Sections---------------------------No   325 1451  235
 Allow Insertion of Energy Points-----------------------------No   325 1451  236
 Create Uniform Energy Grid-----------------------------------No   325 1451  237
 Delete Section if Cross Section =0 at All Energies-----------Yes  325 1451  238
 ***************** Program GROUPIE (VERSION 2002-1) ************** 325 1451  239
 Unshielded Group Averages Using  640 Groups                       325 1451  240
 Weighting Spectrum: Flat (Constant) Spectrum                      325 1451  241
                                1        451        245          2 325 1451  242
                                2        151          4          2 325 1451  243
                                3        105        217          1 325 1451  244
                               33        105         33          1 325 1451  245
                                                                   325 1  099999
                                                                   325 0  0    0
 3.00600E+3 5.96340E+0          0          0          1          0 325 2151    1
 3.006000+3 1.000000+0          0          0          1          0 325 2151    2
 1.000000-5 1.000000+5          0          0          0          0 325 2151    3
 1.000000+0 2.311750-1          0          0          0          0 325 2151    4
                                                                   325 2  099999
                                                                   325 0  0    0
 3.00600E+3 5.96340E+0          0          0          0          0 325 3105    1
 4.78380E+6 4.78380E+6          0          0          1        641 325 3105    2
        641          1                                             325 3105    3
 .000100000 14794.9461 .000105000 14449.9534 .000110000 14122.2061 325 3105    4
 .000115000 13820.1942 .000120000 13467.1458 .000127500 13075.4530 325 3105    5
 .000135000 12717.5721 .000142500 12388.6847 .000150000 12032.7367 325 3105    6
 .000160000 11661.9312 .000170000 11324.5439 .000180000 11014.8459 325 3105    7
 .000190000 10726.6978 .000200000 10463.6234 .000210000 10216.1135 325 3105    8
 .000220000 9986.21324 .000230000 9772.62292 .000240000 9521.91859 325 3105    9
 .000255000 9246.40272 .000270000 9033.79728 .000280000 8797.12696 325 3105   10
 .000300000 8508.50325 .000320000 8247.16668 .000340000 8007.82467 325 3105   11
 .000360000 7787.37574 .000380000 7586.13528 .000400000 7376.33068 325 3105   12
 .000425000 7161.64277 .000450000 6965.50583 .000475000 6785.66231 325 3105   13
 .000500000 6616.52235 .000525000 6461.94757 .000550000 6315.93048 325 3105   14
 .000575000 6180.13284 .000600000 6040.94642 .000630000 5897.75751 325 3105   15
 .000660000 5766.73697 .000690000 5641.05202 .000720000 5507.32050 325 3105   16
 .000760000 5363.93249 .000800000 5230.80234 .000840000 5108.78635 325 3105   17
 .000880000 4992.81623 .000920000 4886.50890 .000960000 4784.70637 325 3105   18
 .001000000 4679.19964 .001050000 4569.04414 .001100000 4465.76191 325 3105   19
 .001150000 4370.59678 .001200000 4258.33842 .001275000 4134.96155 325 3105   20
 .001350000 4022.16216 .001425000 3916.88925 .001500000 3805.04153 325 3105   21
 .001600000 3688.10030 .001700000 3581.34573 .001800000 3482.60854 325 3105   22
 .001900000 3392.40441 .002000000 3308.77765 .002100000 3230.31157 325 3105   23
 .002200000 3158.44480 .002300000 3089.72099 .002400000 3011.30697 325 3105   24
 .002550000 2924.17510 .002700000 2856.02126 .002800000 2781.96182 325 3105   25
 .003000000 2690.80549 .003200000 2607.85391 .003400000 2531.98785 325 3105   26
 .003600000 2462.79638 .003800000 2398.91608 .004000000 2332.33692 325 3105   27
 .004250000 2264.72689 .004500000 2203.02081 .004750000 2145.35559 325 3105   28
 .005000000 2092.44576 .005250000 2043.40654 .005500000 1997.05482 325 3105   29
 .005750000 1954.57647 .006000000 1909.96714 .006300000 1865.38391 325 3105   30
 .006600000 1823.18871 .006900000 1784.04467 .007200000 1741.48065 325 3105   31
 .007600000 1695.96373 .008000000 1654.34447 .008400000 1615.27928 325 3105   32
 .008800000 1578.91854 .009200000 1545.13798 .009600000 1513.00017 325 3105   33
 .010000000 1479.73644 .010500000 1444.57603 .011000000 1412.42313 325 3105   34
 .011500000 1381.75051 .012000000 1346.59615 .012750000 1307.68584 325 3105   35
 .013500000 1271.64181 .014250000 1238.56317 .015000000 1203.27730 325 3105   36
 .016000001 1166.23862 .017000001 1132.28052 .017999999 1101.28202 325 3105   37
 .018999999 1072.79317 .020000000 1046.06875 .021000000 1021.61496 325 3105   38
 .022000000 998.572690 .023000000 977.099923 .024000000 951.867476 325 3105   39
 .025500000 924.650334 .027000001 903.085714 .028000001 879.664218 325 3105   40
 .029999999 850.841313 .032000002 824.584971 .034000002 800.612528 325 3105   41
 .035999998 778.732778 .037999999 758.549586 .039999999 737.487875 325 3105   42
 .042500000 716.110259 .045000002 696.571444 .047499999 678.366928 325 3105   43
 .050000001 661.623345 .052499998 646.130877 .055000000 631.464013 325 3105   44
 .057500001 618.035173 .059999999 603.916290 .063000001 589.802419 325 3105   45
 .066000000 576.497152 .068999998 564.095301 .071999997 550.648650 325 3105   46
 .075999998 536.246480 .079999998 523.089245 .083999999 510.719324 325 3105   47
 .088000000 499.211911 .092000000 488.553833 .096000001 478.374129 325 3105   48
 .100000001 467.864268 .104999997 456.740352 .109999999 446.578283 325 3105   49
 .115000002 436.871661 .119999997 425.753899 .127499998 413.473559 325 3105   50
 .135000005 402.085828 .142499998 391.626836 .150000006 380.471804 325 3105   51
 .159999996 368.744950 .170000002 358.015375 .180000007 348.198886 325 3105   52
 .189999998 339.184378 .200000003 330.720268 .209999993 322.982244 325 3105   53
 .219999999 315.682189 .230000004 308.885854 .239999995 301.048031 325 3105   54
 .254999995 292.298232 .270000011 285.625887 .280000001 278.184188 325 3105   55
 .300000012 269.039086 .319999993 260.740769 .340000004 253.189079 325 3105   56
 .360000014 246.269336 .379999995 239.820982 .400000006 233.210767 325 3105   57
 .425000012 226.472440 .449999988 220.243253 .474999994 214.511408 325 3105   58
 .500000000 209.256293 .524999976 204.282890 .550000012 199.729453 325 3105   59
 .574999988 195.403926 .600000024 190.991063 .629999995 186.517846 325 3105   60
 .660000026 182.279486 .689999998 178.400407 .720000029 174.092531 325 3105   61
 .759999990 169.580921 .800000012 165.402550 .839999974 161.482057 325 3105   62
 .879999995 157.896838 .920000017 154.457639 .959999979 151.313264 325 3105   63
 1.00000000 147.924471 1.04999995 144.457738 1.10000002 141.215388 325 3105   64
 1.14999998 138.163257 1.20000005 134.661002 1.27499998 130.732247 325 3105   65
 1.35000002 127.134297 1.42499995 123.849352 1.50000000 120.293925 325 3105   66
 1.60000002 116.585459 1.70000005 113.209752 1.79999995 110.125223 325 3105   67
 1.89999998 107.244386 2.00000000 104.595170 2.09999990 102.145940 325 3105   68
 2.20000005 99.8337043 2.29999995 97.7171215 2.40000010 95.2040034 325 3105   69
 2.54999995 92.4334553 2.70000005 90.3148276 2.79999995 87.9381155 325 3105   70
 3.00000000 85.0523601 3.20000005 82.4380221 3.40000010 80.0560785 325 3105   71
 3.59999990 77.8616733 3.79999995 75.8730582 4.00000000 73.7205775 325 3105   72
 4.25000000 71.6078328 4.50000000 69.6686317 4.75000000 67.8455059 325 3105   73
 5.00000000 66.1838277 5.25000000 64.5853545 5.50000000 63.1383990 325 3105   74
 5.75000000 61.7747034 6.00000000 60.3789510 6.30000019 58.9664576 325 3105   75
 6.59999990 57.6264409 6.90000010 56.4004006 7.19999981 55.0410801 325 3105   76
 7.59999990 53.6130860 8.00000000 52.2937668 8.39999962 51.0497077 325 3105   77
 8.80000019 49.9143943 9.19999981 48.8331393 9.60000038 47.8550339 325 3105   78
 10.0000000 46.7674076 10.5000000 45.6690583 11.0000000 44.6357610 325 3105   79
 11.5000000 43.7022554 12.0000000 42.5635629 12.7500000 41.3292052 325 3105   80
 13.5000000 40.1934306 14.2500000 39.1440984 15.0000000 38.0253790 325 3105   81
 16.0000000 36.8529448 17.0000000 35.7847221 18.0000000 34.8158482 325 3105   82
 19.0000000 33.8933511 20.0000000 33.0523746 21.0000000 32.2802396 325 3105   83
 22.0000000 31.5498964 23.0000000 30.8900598 24.0000000 30.0863941 325 3105   84
 25.5000000 29.2029000 27.0000000 28.5498764 28.0000000 27.7953130 325 3105   85
 30.0000000 26.8770847 32.0000000 26.0473656 34.0000000 25.2913699 325 3105   86
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 760.000000 5.34606717 800.000000 5.21088095 840.000000 5.08749818 325 3105  107
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 1000.00000 4.66214100 1050.00000 4.55068283 1100.00000 4.44663325 325 3105  109
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 1350.00000 4.00425444 1425.00000 3.89861606 1500.00000 3.78734478 325 3105  111
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 1900.00000 3.37800941 2000.00000 3.29486079 2100.00000 3.21551739 325 3105  113
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 3600.00000 2.45174631 3800.00000 2.38777474 4000.00000 2.32270437 325 3105  117
 4250.00000 2.25510324 4500.00000 2.19365477 4750.00000 2.13670837 325 3105  118
 5000.00000 2.08457190 5250.00000 2.03627206 5500.00000 1.99039043 325 3105  119
 5750.00000 1.94936120 6000.00000 1.90477373 6300.00000 1.85961556 325 3105  120
 6600.00000 1.81901788 6900.00000 1.77993500 7200.00000 1.73673731 325 3105  121
 7600.00000 1.69311398 8000.00000 1.65259511 8400.00000 1.61376704 325 3105  122
 8800.00000 1.57933324 9200.00000 1.54536879 9600.00000 1.51458549 325 3105  123
 10000.0000 1.48148743 10500.0000 1.44753210 11000.0000 1.41542407 325 3105  124
 11500.0000 1.38664009 12000.0000 1.35144015 12750.0000 1.31350635 325 3105  125
 13500.0000 1.27925643 14250.0000 1.24632102 15000.0000 1.21228417 325 3105  126
 16000.0000 1.17680908 17000.0000 1.14467554 18000.0000 1.11531321 325 3105  127
 19000.0000 1.08719999 20000.0000 1.06229582 21000.0000 1.03950157 325 3105  128
 22000.0000 1.01741295 23000.0000 .997227860 24000.0000 .974081174 325 3105  129
 25500.0000 .948872168 27000.0000 .929148193 28000.0000 .907398612 325 3105  130
 30000.0000 .881470428 32000.0000 .858737818 34000.0000 .836735594 325 3105  131
 36000.0000 .818752128 38000.0000 .801639590 40000.0000 .783680690 325 3105  132
 42500.0000 .765304010 45000.0000 .749668270 47500.0000 .735815842 325 3105  133
 50000.0000 .723236597 52500.0000 .711539506 55000.0000 .701119014 325 3105  134
 57500.0000 .692908091 60000.0000 .683919102 63000.0000 .674380573 325 3105  135
 66000.0000 .667827826 69000.0000 .662106422 72000.0000 .655498425 325 3105  136
 76000.0000 .650743008 80000.0000 .647467476 84000.0000 .645314418 325 3105  137
 88000.0000 .645905186 92000.0000 .646794521 96000.0000 .649732309 325 3105  138
 100000.000 .655973768 105000.000 .664808760 110000.000 .676082349 325 3105  139
 115000.000 .690829300 120000.000 .713964961 127500.000 .749125868 325 3105  140
 135000.000 .794888454 142500.000 .853444591 150000.000 .940557974 325 3105  141
 160000.000 1.07268258 170000.000 1.24910602 180000.000 1.48475164 325 3105  142
 190000.000 1.79021138 200000.000 2.16724840 210000.000 2.58737388 325 3105  143
 220000.000 2.97055397 230000.000 3.21624274 240000.000 3.14487391 325 3105  144
 255000.000 2.68272158 270000.000 2.21496823 280000.000 1.73853659 325 3105  145
 300000.000 1.28420207 320000.000 .995985834 340000.000 .809601128 325 3105  146
 360000.000 .683879984 380000.000 .595363931 400000.000 .524296863 325 3105  147
 425000.000 .466780760 450000.000 .424250250 475000.000 .392127833 325 3105  148
 500000.000 .366737894 525000.000 .346395836 550000.000 .329775983 325 3105  149
 575000.000 .315914474 600000.000 .303191401 630000.000 .291316531 325 3105  150
 660000.000 .281550546 690000.000 .273122818 720000.000 .264899246 325 3105  151
 760000.000 .256798774 800000.000 .249995237 840000.000 .244279456 325 3105  152
 880000.000 .239346901 920000.000 .235225321 960000.000 .231452864 325 3105  153
 1000000.00 .226350724 1100000.00 .220650709 1200000.00 .216735563 325 3105  154
 1300000.00 .214180518 1400000.00 .212825498 1500000.00 .212585477 325 3105  155
 1600000.00 .213375516 1700000.00 .215245010 1800000.00 .217149014 325 3105  156
 1900000.00 .217113782 2000000.00 .214724255 2100000.00 .210929540 325 3105  157
 2200000.00 .206289640 2300000.00 .201289713 2400000.00 .196072216 325 3105  158
 2500000.00 .190637149 2600000.00 .184940109 2700000.00 .178981094 325 3105  159
 2800000.00 .173060051 2900000.00 .167354974 3000000.00 .161391900 325 3105  160
 3100000.00 .154771724 3200000.00 .147786528 3300000.00 .140801332 325 3105  161
 3400000.00 .134060373 3500000.00 .127860050 3600000.00 .122303414 325 3105  162
 3700000.00 .117470853 3800000.00 .113407378 3900000.00 .110136087 325 3105  163
 4000000.00 .107525230 4100000.00 .105174916 4200000.00 .102666422 325 3105  164
 4300000.00 .099999748 4400000.00 .097333074 4500000.00 .094500068 325 3105  165
 4600000.00 .091750038 4700000.00 .089050002 4800000.00 .086350327 325 3105  166
 4900000.00 .084050483 5000000.00 .082333769 5100000.00 .081000034 325 3105  167
 5200000.00 .079666298 5300000.00 .077999635 5400000.00 .076000045 325 3105  168
 5500000.00 .074000454 5600000.00 .072375633 5700000.00 .071125580 325 3105  169
 5800000.00 .069875527 5900000.00 .068625474 6000000.00 .067375421 325 3105  170
 6100000.00 .066125368 6200000.00 .064875315 6300000.00 .063625262 325 3105  171
 6400000.00 .062500236 6500000.00 .061500238 6600000.00 .060500239 325 3105  172
 6700000.00 .059500241 6800000.00 .058500243 6900000.00 .057500245 325 3105  173
 7000000.00 .056500246 7100000.00 .055500248 7200000.00 .054625243 325 3105  174
 7300000.00 .053875231 7400000.00 .053125220 7500000.00 .052375208 325 3105  175
 7600000.00 .051625196 7700000.00 .050875184 7800000.00 .050125173 325 3105  176
 7900000.00 .049375161 8000000.00 .048700156 8100000.00 .048100159 325 3105  177
 8200000.00 .047500162 8300000.00 .046900165 8400000.00 .046300168 325 3105  178
 8500000.00 .045700170 8600000.00 .045100173 8700000.00 .044500176 325 3105  179
 8800000.00 .043900179 8900000.00 .043300182 9000000.00 .042700184 325 3105  180
 9100000.00 .042100187 9200000.00 .041500190 9300000.00 .040900193 325 3105  181
 9400000.00 .040300196 9500000.00 .039800199 9600000.00 .039400202 325 3105  182
 9700000.00 .039000205 9800000.00 .038600208 9900000.00 .038200212 325 3105  183
 10000000.0 .037800215 10100000.0 .037400218 10200000.0 .037000222 325 3105  184
 10300000.0 .036600225 10400000.0 .036200228 10500000.0 .035800231 325 3105  185
 10600000.0 .035400235 10700000.0 .035000238 10800000.0 .034600241 325 3105  186
 10900000.0 .034200244 11000000.0 .033900196 11100000.0 .033700097 325 3105  187
 11200000.0 .033499997 11300000.0 .033299897 11400000.0 .033099798 325 3105  188
 11500000.0 .032799774 11600000.0 .032399825 11700000.0 .031999877 325 3105  189
 11800000.0 .031599928 11900000.0 .031199980 12000000.0 .030800031 325 3105  190
 12100000.0 .030400083 12200000.0 .030000134 12300000.0 .029600186 325 3105  191
 12400000.0 .029200237 12500000.0 .028900259 12600000.0 .028700252 325 3105  192
 12700000.0 .028500245 12800000.0 .028300238 12900000.0 .028100231 325 3105  193
 13000000.0 .027900224 13100000.0 .027700217 13200000.0 .027500210 325 3105  194
 13300000.0 .027300203 13400000.0 .027100196 13500000.0 .026900189 325 3105  195
 13600000.0 .026700182 13700000.0 .026500175 13800000.0 .026300167 325 3105  196
 13900000.0 .026100160 14000000.0 .025900153 14100000.0 .025700146 325 3105  197
 14200000.0 .025500139 14300000.0 .025300132 14400000.0 .025100125 325 3105  198
 14500000.0 .024900118 14600000.0 .024700111 14700000.0 .024500104 325 3105  199
 14800000.0 .024300097 14900000.0 .024100090 15000000.0 .023930075 325 3105  200
 15100000.0 .023790052 15200000.0 .023650029 15300000.0 .023510006 325 3105  201
 15400000.0 .023369983 15500000.0 .023219968 15600000.0 .023059962 325 3105  202
 15700000.0 .022899956 15800000.0 .022739950 15900000.0 .022579944 325 3105  203
 16000000.0 .022399943 16100000.0 .022199948 16200000.0 .021999952 325 3105  204
 16300000.0 .021799957 16400000.0 .021599961 16500000.0 .021399966 325 3105  205
 16600000.0 .021199970 16700000.0 .020999975 16800000.0 .020799979 325 3105  206
 16900000.0 .020599984 17000000.0 .020399988 17100000.0 .020199993 325 3105  207
 17200000.0 .019999997 17300000.0 .019800002 17400000.0 .019600006 325 3105  208
 17500000.0 .019400011 17600000.0 .019200015 17700000.0 .019000020 325 3105  209
 17800000.0 .018800024 17900000.0 .018600029 18000000.0 .018410031 325 3105  210
 18100000.0 .018230031 18200000.0 .018050032 18300000.0 .017870032 325 3105  211
 18400000.0 .017690032 18500000.0 .017520026 18600000.0 .017360013 325 3105  212
 18700000.0 .017200000 18800000.0 .017039987 18900000.0 .016879974 325 3105  213
 19000000.0 .016709991 19100000.0 .016530036 19200000.0 .016350082 325 3105  214
 19300000.0 .016170128 19400000.0 .015990173 19500000.0 .015810219 325 3105  215
 19600000.0 .015630264 19700000.0 .015450310 19800000.0 .015270356 325 3105  216
 19900000.0 .015090401 20000000.0 0.0                              325 3105  217
                                                                   325 3  099999
                                                                   325 0  0    0
 3.00600E+3 5.96340E+0          0          0          0          1 32533105    1
 0.000000+0 0.000000+0          0        105          0          2 32533105    2
 0.000000+0 0.000000+0          1          5         36          8 32533105    3
 1.000000-5 2.900000+6 3.000000+6 4.000000+6 7.000000+6 1.000000+7 32533105    4
 1.500000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 32533105    5
 0.000000+0 0.000000+0 0.000000+0 2.500000-3 1.600000-3 4.000000-4 32533105    6
 1.000000-4 0.000000+0 0.000000+0 7.225000-3 2.500000-3 9.000000-4 32533105    7
 1.000000-4 0.000000+0 1.000000-2 4.900000-3 9.000000-4 1.000000-4 32533105    8
 2.250000-2 1.000000-2 2.500000-3 2.250000-2 1.000000-2 4.000000-2 32533105    9
 0.000000+0 0.000000+0          1          5        136         16 32533105   10
 1.000000-5 1.000000+2 9.000001+2 9.000000+3 2.700000+4 5.000000+4 32533105   11
 9.000000+4 1.350000+5 2.050000+5 2.750000+5 4.125000+5 6.250000+5 32533105   12
 9.500000+5 1.325000+6 1.900000+6 2.900000+6 2.055389-6 2.031643-6 32533105   13
 1.998727-6 1.891522-6 1.717140-6 1.434576-6 1.012230-6 4.474765-7 32533105   14
 2.525604-7 3.803064-7 6.685372-7 5.647702-7 3.525890-7 2.443466-7 32533105   15
 2.403642-7 2.010328-6 1.982675-6 1.885041-6 1.721060-6 1.450429-6 32533105   16
 1.037462-6 4.675514-7 2.568603-7 3.814197-7 6.646155-7 5.640642-7 32533105   17
 3.525987-7 2.386595-7 2.324457-7 1.974322-6 1.928096-6 1.837664-6 32533105   18
 1.666698-6 1.331928-6 6.733060-7 3.031556-7 3.630861-7 6.578547-7 32533105   19
 6.675623-7 4.558385-7 2.464726-7 2.435982-7 2.043087-6 2.202572-6 32533105   20
 2.387305-6 2.349317-6 1.407300-6 4.669809-7 2.820108-7 6.083592-7 32533105   21
 1.042364-6 8.515235-7 3.061526-7 3.219862-7 2.765415-6 3.545594-6 32533105   22
 4.040598-6 2.719275-6 7.756631-7 1.968649-7 4.849967-7 1.603382-6 32533105   23
 1.503952-6 4.541172-7 4.824173-7 5.252231-6 6.679399-6 5.083272-6 32533105   24
 1.396229-6 2.897295-7 2.358371-7 2.244136-6 2.418936-6 7.837799-7 32533105   25
 7.614119-7 9.288824-6 8.271248-6 2.397961-6 9.349064-7 9.954863-9 32533105   26
 2.405782-6 3.039443-6 1.254285-6 1.052807-6 1.105814-5 4.339311-6 32533105   27
 2.488444-6 9.852444-7 1.377236-6 1.989021-6 1.457171-6 9.981584-7 32533105   28
 4.886551-6 3.473981-6 1.653619-6 9.322945-7 7.297434-7 6.455541-7 32533105   29
 7.013815-7 8.443410-6 5.612672-6 2.134349-6 3.386685-7 2.943248-8 32533105   30
 7.915241-7 9.299034-6 8.280879-6 5.098584-6 1.338568-6 1.841448-6 32533105   31
 1.270541-5 1.262244-5 7.390554-6 4.714562-6 1.835564-5 1.767288-5 32533105   32
 9.582569-6 3.027060-5 1.780456-5 3.434466-5                       32533105   33
                                                                   32533  099999
                                                                   325 0  0    0
                                                                     0 0  0    0
 5.00000E+3 1.07191E+1         -1          0         34          0 500 1451    1
 0.0        0.0                 0          0          0          6 500 1451    2
 1.00000E+0 2.00000E+7          0          0         10       2002 500 1451    3
 3.00000E+2 0.0                 1          0         75          5 500 1451    4
  5-B -  0  NDS       IAEA-JAN04                                   500 1451    5
                      DIST-Feb2004                                 500 1451    6
----IRDF-2002                                                      500 1451    7
-----INCIDENT NEUTRON DATA                                         500 1451    8
------ENDF-6 FORMAT                                                500 1451    9
 ***************************************************************** 500 1451   10
*****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 500 1451   11
DOSIMETRY     Assembled at NDS from the ENDF/B-VI evaluations for  500 1451   12
              5-B -10 and 5-B -11. The files were processed        500 1451   13
              through the 2002 pre-processing codes LINEAR,RECENT, 500 1451   14
              SIGMA1 and FIXUP to produce pointwise files prior to 500 1451   15
              input to MIXER.                                      500 1451   16
                                                                   500 1451   17
MIXER INPUT FILE                                                   500 1451   18
                                                                   500 1451   19
Boron   DENSITY  2.34 G/CC. CONSTITUENTS:  10-19.8 11-80.2         500 1451   20
FIXUP.out                                                          500 1451   21
MIXER.OUT                                                          500 1451   22
    5000      500 3  1            (ID FOR COMBINED REACTION)       500 1451   23
    5010             1 0.429086                                    500 1451   24
    5011             1 1.910914                                    500 1451   25
                                 (BLANK LINE TERMINATES LIST)      500 1451   26
****************************************************************** 500 1451   27
                                                                   500 1451   28
  5-B - 10 LANL       EVAL-NOV89 G.M.HALE, P.G.YOUNG               500 1451   29
                      DIST-SEP91 REV1-JUL91            19910806    500 1451   30
----ENDF/B-VI         MATERIAL  525         REVISION 1             500 1451   31
 ***************************************************************** 500 1451   32
  5-B - 11 LANL       EVAL-MAY89 P.G.YOUNG                         500 1451   33
                      DIST-SEP 1 REV1-                 20010926    500 1451   34
----ENDF/B-VI         MATERIAL  528                                500 1451   35
 ***************** Program MIXER (VERSION 2002-1) **************** 500 1451   36
Boron   DENSITY  2.34 G/CC. CONSTITUENTS:  10-19.8                 500 1451   37
 11-80.2                                                           500 1451   38
 ----------------------------------------                          500 1451   39
 Composition                                                       500 1451   40
 ----------------------------------------                          500 1451   41
 Isotope MF   MT  Atom-Fract     Grams/cc                          500 1451   42
 ----------------------------------------                          500 1451   43
    5010  3    1  .198003533   .429086000                          500 1451   44
    5011  3    1  .801996467   1.91091400                          500 1451   45
 ----------------------------------------                          500 1451   46
    5000  3    1  1.00000000   2.34000000                          500 1451   47
 ----------------------------------------                          500 1451   48
 Composition                                                       500 1451   49
 ----------------------------------------                          500 1451   50
 Isotope MF   MT  Atom-Fract     Grams/cc                          500 1451   51
 ----------------------------------------                          500 1451   52
    5010  3  101  .198003533   .429086000                          500 1451   53
    5011  3  101  .801996467   1.91091400                          500 1451   54
 ----------------------------------------                          500 1451   55
    5000  3  101  1.00000000   2.34000000                          500 1451   56
 ----------------------------------------                          500 1451   57
 Composition                                                       500 1451   58
 ----------------------------------------                          500 1451   59
 Isotope MF   MT  Atom-Fract     Grams/cc                          500 1451   60
 ----------------------------------------                          500 1451   61
    5010  3  102  .198003533   .429086000                          500 1451   62
    5011  3  102  .801996467   1.91091400                          500 1451   63
 ----------------------------------------                          500 1451   64
    5000  3  102  1.00000000   2.34000000                          500 1451   65
 ----------------------------------------                          500 1451   66
 Composition                                                       500 1451   67
 ----------------------------------------                          500 1451   68
 Isotope MF   MT  Atom-Fract     Grams/cc                          500 1451   69
 ----------------------------------------                          500 1451   70
    5010  3  107  .198003533   .429086000                          500 1451   71
    5011  3  107  .801996467   1.91091400                          500 1451   72
 ----------------------------------------                          500 1451   73
    5000  3  107  1.00000000   2.34000000                          500 1451   74
 ----------------------------------------                          500 1451   75
 ***************************************************************** 500 1451   76
 ***************** Program GROUPIE (VERSION 2002-1) ************** 500 1451   77
 Unshielded Group Averages Using  640 Groups                       500 1451   78
 Weighting Spectrum: Flat (Constant) Spectrum                      500 1451   79
                                1        451         84          0 500 1451   80
                                3          1        217          0 500 1451   81
                                3        101        217          0 500 1451   82
                                3        102        217          0 500 1451   83
                                3        107        217          0 500 1451   84
                                                                   500 1  099999
                                                                   500 0  0    0
 5.00000E+3 1.07191E+1          0          0          0          0 500 3  1    1
 0.0        0.0                 0          0          1        641 500 3  1    2
        641          1                                             500 3  1    3
 .000100000 11978.8538 .000105000 11699.5424 .000110000 11434.1935 500 3  1    4
 .000115000 11189.6813 .000120000 10903.8500 .000127500 10586.7324 500 3  1    5
 .000135000 10296.9896 .000142500 10030.7205 .000150000 9742.54339 500 3  1    6
 .000160000 9442.33816 .000170000 9169.18928 .000180000 8918.45764 500 3  1    7
 .000190000 8685.17315 .000200000 8472.19074 .000210000 8271.80898 500 3  1    8
 .000220000 8085.68284 .000230000 7912.76203 .000240000 7709.79518 500 3  1    9
 .000255000 7486.74370 .000270000 7314.62300 .000280000 7123.01962 500 3  1   10
 .000300000 6889.35742 .000320000 6677.78760 .000340000 6484.02439 500 3  1   11
 .000360000 6305.55685 .000380000 6142.64221 .000400000 5972.79750 500 3  1   12
 .000425000 5798.99611 .000450000 5640.21803 .000475000 5494.62199 500 3  1   13
 .000500000 5357.70086 .000525000 5232.56691 .000550000 5114.36204 500 3  1   14
 .000575000 5004.43483 .000600000 4891.75483 .000630000 4775.84855 500 3  1   15
 .000660000 4669.78023 .000690000 4568.04345 .000720000 4459.78550 500 3  1   16
 .000760000 4343.71471 .000800000 4235.95327 .000840000 4137.17932 500 3  1   17
 .000880000 4043.30971 .000920000 3957.25264 .000960000 3874.85482 500 3  1   18
 .001000000 3789.45224 .001050000 3700.28924 .001100000 3616.69199 500 3  1   19
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 5.00000000 53.4320267 5.25000000 52.1415345 5.50000000 50.9737218 500 3107   74
 5.75000000 49.8726613 6.00000000 48.7454438 6.30000019 47.6195268 500 3107   75
 6.59999990 46.5473821 6.90000010 45.5165196 7.19999981 44.4382822 500 3107   76
 7.59999990 43.3055712 8.00000000 42.2088568 8.39999962 41.2207849 500 3107   77
 8.80000019 40.2891173 9.19999981 39.4238156 9.60000038 38.6104278 500 3107   78
 10.0000000 37.7464337 10.5000000 36.8635547 11.0000000 36.0283706 500 3107   79
 11.5000000 35.2741197 12.0000000 34.3541266 12.7500000 33.3567208 500 3107   80
 13.5000000 32.4385008 14.2500000 31.5885474 15.0000000 30.6860696 500 3107   81
 16.0000000 29.7524272 17.0000000 28.8739910 18.0000000 28.0911480 500 3107   82
 19.0000000 27.3460530 20.0000000 26.6662729 21.0000000 26.0424408 500 3107   83
 22.0000000 25.4511293 23.0000000 24.9069328 24.0000000 24.2627346 500 3107   84
 25.5000000 23.5573860 27.0000000 23.0281386 28.0000000 22.4191081 500 3107   85
 30.0000000 21.6769025 32.0000000 21.0062824 34.0000000 20.3958028 500 3107   86
 36.0000000 19.8459060 38.0000000 19.3191706 40.0000000 18.7822755 500 3107   87
 42.5000000 18.2392818 45.0000000 17.7374524 47.5000000 17.2703202 500 3107   88
 50.0000000 16.8457580 52.5000000 16.4450194 55.0000000 16.0754608 500 3107   89
 57.5000000 15.7300873 60.0000000 15.3748522 63.0000000 15.0196107 500 3107   90
 66.0000000 14.6763448 69.0000000 14.3572234 72.0000000 14.0201753 500 3107   91
 76.0000000 13.6490649 80.0000000 13.3119617 84.0000000 13.0025740 500 3107   92
 88.0000000 12.7096516 92.0000000 12.4279754 96.0000000 12.1720581 500 3107   93
 100.000000 11.9013600 105.000000 11.6261578 110.000000 11.3581277 500 3107   94
 115.000000 11.1195564 120.000000 10.8282729 127.500000 10.5108884 500 3107   95
 135.000000 10.2304082 142.500000 9.95990027 150.000000 9.67766504 500 3107   96
 160.000000 9.37285945 170.000000 9.10207148 180.000000 8.84680101 500 3107   97
 190.000000 8.62046136 200.000000 8.40200561 210.000000 8.20440641 500 3107   98
 220.000000 8.01793130 230.000000 7.84667701 240.000000 7.64390355 500 3107   99
 255.000000 7.42104248 270.000000 7.25329606 280.000000 7.05967331 500 3107  100
 300.000000 6.82456672 320.000000 6.61558696 340.000000 6.42048859 500 3107  101
 360.000000 6.24469469 380.000000 6.08131922 400.000000 5.91072623 500 3107  102
 425.000000 5.73721413 450.000000 5.57950392 475.000000 5.43377210 500 3107  103
 500.000000 5.29807132 525.000000 5.17396192 550.000000 5.05343430 500 3107  104
 575.000000 4.94469558 600.000000 4.83544095 630.000000 4.71817188 500 3107  105
 660.000000 4.61266936 690.000000 4.51257347 720.000000 4.40252747 500 3107  106
 760.000000 4.28886622 800.000000 4.18032106 840.000000 4.08286357 500 3107  107
 880.000000 3.98761357 920.000000 3.90100326 960.000000 3.81782180 500 3107  108
 1000.00000 3.73424155 1050.00000 3.64416365 1100.00000 3.56008324 500 3107  109
 1150.00000 3.48480860 1200.00000 3.39299051 1275.00000 3.29399192 500 3107  110
 1350.00000 3.20308128 1425.00000 3.11854059 1500.00000 3.02951544 500 3107  111
 1600.00000 2.93255777 1700.00000 2.84781987 1800.00000 2.76936982 500 3107  112
 1900.00000 2.69608696 2000.00000 2.62880327 2100.00000 2.56461217 500 3107  113
 2200.00000 2.50657959 2300.00000 2.45200229 2400.00000 2.38829438 500 3107  114
 2550.00000 2.31802370 2700.00000 2.26356392 2800.00000 2.20371335 500 3107  115
 3000.00000 2.13076696 3200.00000 2.06419343 3400.00000 2.00207311 500 3107  116
 3600.00000 1.94683561 3800.00000 1.89639428 4000.00000 1.84263722 500 3107  117
 4250.00000 1.78777778 4500.00000 1.73752009 4750.00000 1.69196959 500 3107  118
 5000.00000 1.64952012 5250.00000 1.60943785 5500.00000 1.57248167 500 3107  119
 5750.00000 1.53833792 6000.00000 1.50282955 6300.00000 1.46794607 500 3107  120
 6600.00000 1.43396741 6900.00000 1.40275447 7200.00000 1.36870201 500 3107  121
 7600.00000 1.33180505 8000.00000 1.29798250 8400.00000 1.26704130 500 3107  122
 8800.00000 1.23771594 9200.00000 1.21159197 9600.00000 1.18599691 500 3107  123
 10000.0000 1.15875085 10500.0000 1.13132325 11000.0000 1.10606930 500 3107  124
 11500.0000 1.08140960 12000.0000 1.05331716 12750.0000 1.02219711 500 3107  125
 13500.0000 .993621235 14250.0000 .967522791 15000.0000 .939970163 500 3107  126
 16000.0000 .910461974 17000.0000 .883955117 18000.0000 .859670891 500 3107  127
 19000.0000 .837026687 20000.0000 .816403814 21000.0000 .796992000 500 3107  128
 22000.0000 .778972323 23000.0000 .762303468 24000.0000 .742959136 500 3107  129
 25500.0000 .721879013 27000.0000 .705630964 28000.0000 .687423555 500 3107  130
 30000.0000 .665434100 32000.0000 .645633106 34000.0000 .627841284 500 3107  131
 36000.0000 .611336387 38000.0000 .595948890 40000.0000 .580403134 500 3107  132
 42500.0000 .563923221 45000.0000 .549508500 47500.0000 .536231320 500 3107  133
 50000.0000 .524163021 52500.0000 .512878694 55000.0000 .502309402 500 3107  134
 57500.0000 .492977710 60000.0000 .482835278 63000.0000 .472562256 500 3107  135
 66000.0000 .463570968 69000.0000 .454898608 72000.0000 .445548458 500 3107  136
 76000.0000 .435809400 80000.0000 .426517455 84000.0000 .418246514 500 3107  137
 88000.0000 .410927914 92000.0000 .403651642 96000.0000 .396639053 500 3107  138
 100000.000 .389433793 105000.000 .382003081 110000.000 .375165493 500 3107  139
 115000.000 .368436319 120000.000 .360702442 127500.000 .351572543 500 3107  140
 135000.000 .343241912 142500.000 .335345435 150000.000 .326329138 500 3107  141
 160000.000 .316537289 170000.000 .306783115 180000.000 .297358661 500 3107  142
 190000.000 .288201774 200000.000 .279002174 210000.000 .270048673 500 3107  143
 220000.000 .261393856 230000.000 .253065477 240000.000 .242985767 500 3107  144
 255000.000 .231576475 270000.000 .222530053 280000.000 .212176815 500 3107  145
 300000.000 .199518728 320000.000 .188801004 340000.000 .179927189 500 3107  146
 360000.000 .173514984 380000.000 .169522719 400000.000 .167732745 500 3107  147
 425000.000 .167367298 450000.000 .166376264 475000.000 .161645611 500 3107  148
 500000.000 .152153769 525000.000 .139774643 550000.000 .126881860 500 3107  149
 575000.000 .114767061 600000.000 .103279598 630000.000 .092720183 500 3107  150
 660000.000 .084094035 690000.000 .076876211 720000.000 .070034625 500 3107  151
 760000.000 .063669802 800000.000 .058497154 840000.000 .054252351 500 3107  152
 880000.000 .050730286 920000.000 .047795793 960000.000 .045316291 500 3107  153
 1000000.00 .042654072 1100000.00 .041979779 1200000.00 .043619696 500 3107  154
 1300000.00 .047472097 1400000.00 .053984775 1500000.00 .065055907 500 3107  155
 1600000.00 .084445845 1700000.00 .100933533 1800000.00 .102736791 500 3107  156
 1900000.00 .095794408 2000000.00 .084696977 2100000.00 .072437129 500 3107  157
 2200000.00 .063492741 2300000.00 .058306439 2400000.00 .056201749 500 3107  158
 2500000.00 .060131741 2600000.00 .066513985 2700000.00 .074986446 500 3107  159
 2800000.00 .075947111 2900000.00 .068738566 3000000.00 .062584334 500 3107  160
 3100000.00 .057801534 3200000.00 .055856603 3300000.00 .057232663 500 3107  161
 3400000.00 .060268960 3500000.00 .063636930 3600000.00 .067074281 500 3107  162
 3700000.00 .070528099 3800000.00 .071525819 3900000.00 .070040466 500 3107  163
 4000000.00 .065564482 4100000.00 .058097630 4200000.00 .052996540 500 3107  164
 4300000.00 .050076819 4400000.00 .046287789 4500000.00 .041843234 500 3107  165
 4600000.00 .038190148 4700000.00 .035338142 4800000.00 .032754060 500 3107  166
 4900000.00 .030428289 5000000.00 .028475508 5100000.00 .026895717 500 3107  167
 5200000.00 .025327931 5300000.00 .023772152 5400000.00 .022631485 500 3107  168
 5500000.00 .022232566 5600000.00 .022325351 5700000.00 .022583208 500 3107  169
 5800000.00 .022802486 5900000.00 .022972725 6000000.00 .023142792 500 3107  170
 6100000.00 .023312859 6200000.00 .023406626 6300000.00 .023424091 500 3107  171
 6400000.00 .023372579 6500000.00 .023252092 6600000.00 .023078708 500 3107  172
 6700000.00 .022852427 6800000.00 .022521864 6900000.00 .022087019 500 3107  173
 7000000.00 .021559718 7100000.00 .020939960 7200000.00 .020292928 500 3107  174
 7300000.00 .019618622 7400000.00 .018951384 7500000.00 .018291300 500 3107  175
 7600000.00 .017662035 7700000.00 .017074572 7800000.00 .016584340 500 3107  176
 7900000.00 .016216828 8000000.00 .015872377 8100000.00 .015536219 500 3107  177
 8200000.00 .015266814 8300000.00 .015068258 8400000.00 .014936052 500 3107  178
 8500000.00 .014871101 8600000.00 .014867289 8700000.00 .014920678 500 3107  179
 8800000.00 .015022340 8900000.00 .015167674 9000000.00 .015351632 500 3107  180
 9100000.00 .015610118 9200000.00 .015963544 9300000.00 .016408857 500 3107  181
 9400000.00 .016932279 9500000.00 .017524296 9600000.00 .018153582 500 3107  182
 9700000.00 .018815146 9800000.00 .019556606 9900000.00 .020397550 500 3107  183
 10000000.0 .021312872 10100000.0 .022308480 10200000.0 .023350896 500 3107  184
 10300000.0 .024439042 10400000.0 .025543706 10500000.0 .026643313 500 3107  185
 10600000.0 .027694449 10700000.0 .028673826 10800000.0 .029506016 500 3107  186
 10900000.0 .030191021 11000000.0 .030763852 11100000.0 .031224509 500 3107  187
 11200000.0 .031631834 11300000.0 .031985825 11400000.0 .032291818 500 3107  188
 11500000.0 .032568346 11600000.0 .032822288 11700000.0 .033035107 500 3107  189
 11800000.0 .033211108 11900000.0 .033350291 12000000.0 .033508437 500 3107  190
 12100000.0 .033685547 12200000.0 .033862657 12300000.0 .034039767 500 3107  191
 12400000.0 .034204313 12500000.0 .034369036 12600000.0 .034518832 500 3107  192
 12700000.0 .034640959 12800000.0 .034721523 12900000.0 .034760524 500 3107  193
 13000000.0 .034775931 13100000.0 .034767745 13200000.0 .034759560 500 3107  194
 13300000.0 .034751374 13400000.0 .034726948 13500000.0 .034684555 500 3107  195
 13600000.0 .034640435 13700000.0 .034596533 13800000.0 .034538519 500 3107  196
 13900000.0 .034465304 14000000.0 .034379336 14100000.0 .034280613 500 3107  197
 14200000.0 .034181891 14300000.0 .034083168 14400000.0 .033984445 500 3107  198
 14500000.0 .033868518 14600000.0 .033725226 14700000.0 .033571775 500 3107  199
 14800000.0 .033418325 14900000.0 .033264874 15000000.0 .033090006 500 3107  200
 15100000.0 .032893719 15200000.0 .032676905 15300000.0 .032439563 500 3107  201
 15400000.0 .032202220 15500000.0 .031962973 15600000.0 .031700025 500 3107  202
 15700000.0 .031415284 15800000.0 .031130543 15900000.0 .030845802 500 3107  203
 16000000.0 .030542294 16100000.0 .030220019 16200000.0 .029897745 500 3107  204
 16300000.0 .029575470 16400000.0 .029241070 16500000.0 .028895700 500 3107  205
 16600000.0 .028551489 16700000.0 .028207277 16800000.0 .027863066 500 3107  206
 16900000.0 .027518854 17000000.0 .027174643 17100000.0 .026830432 500 3107  207
 17200000.0 .026486220 17300000.0 .026142009 17400000.0 .025797797 500 3107  208
 17500000.0 .025453586 17600000.0 .025109374 17700000.0 .024765163 500 3107  209
 17800000.0 .024430447 17900000.0 .024105228 18000000.0 .023780009 500 3107  210
 18100000.0 .023454789 18200000.0 .023129570 18300000.0 .022804351 500 3107  211
 18400000.0 .022488956 18500000.0 .022183385 18600000.0 .021877815 500 3107  212
 18700000.0 .021572244 18800000.0 .021266674 18900000.0 .020961103 500 3107  213
 19000000.0 .020663773 19100000.0 .020374684 19200000.0 .020085594 500 3107  214
 19300000.0 .019796505 19400000.0 .019507415 19500000.0 .019218326 500 3107  215
 19600000.0 .018935365 19700000.0 .018658533 19800000.0 .018381700 500 3107  216
 19900000.0 .018104868 20000000.0 0.0                              500 3107  217
                                                                   500 3  099999
                                                                   500 0  0    0
                                                                     0 0  0    0
 5.01000E+3 9.92692E+0          0          0         34         10 525 1451    1
 0.0        0.0                 0          0          0          6 525 1451    2
 1.00000E+0 2.00000E+7          0          0         10       2002 525 1451    3
 3.00000E+2 0.0                 1          0        256          6 525 1451    4
  5-B - 10 LANL       EVAL-NOV89 G.M.HALE, P.G.YOUNG               525 1451    5
                      DIST-Feb2004                                 525 1451    6
----IRDF-2002         MATERIAL  525                                525 1451    7
-----INCIDENT NEUTRON DATA                                         525 1451    8
------ENDF-6 FORMAT                                                525 1451    9
****************************************************************** 525 1451   10
  5-B - 10 LANL       EVAL-NOV89 G.M.HALE, P.G.YOUNG               525 1451   11
                      DIST-SEP91 REV1-JUL91            19910806    525 1451   12
----ENDF/B-VI         MATERIAL  525         REVISION 1             525 1451   13
****************************************************************** 525 1451   14
  5-B - 10 LANL       EVAL-NOV89 G.M.HALE, P.G.YOUNG               525 1451   15
                      DIST-FEB91                       910201      525 1451   16
----IRDF-90           MATERIAL  525                                525 1451   17
                                                                   525 1451   18
*****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 525 1451   19
DOSIMETRY                                                          525 1451   20
****************************************************************** 525 1451   21
                                                                   525 1451   22
                  MOD1 OF ENDF/B-VI                                525 1451   23
                                                                   525 1451   24
     The following revisions were made for MOD1 of ENDF/B-VI:      525 1451   25
                                                                   525 1451   26
 1. MF=1,MT=451 - Comments were added regarding estimated          525 1451   27
    (expanded) covariance for the Standards Cross Sections.        525 1451   28
 2. MF=3,MT=55,57,62,64,65,68,70,71,73,74,76-81,83,84 - LR flags   525 1451   29
    and Q-values corrected.                                        525 1451   30
                                                                   525 1451   31
 ***************************************************************** 525 1451   32
****************************************************************** 525 1451   33
                                                                   525 1451   34
                      ENDF/VI EVALUATION                           525 1451   35
                 G. M. Hale and P. G. Young                        525 1451   36
                                                                   525 1451   37
 MAJOR CHANGES FROM VERSION V OF ENDF/B ARE:                       525 1451   38
                                                                   525 1451   39
   1. Inclusion of the ENDF/B-VI standard (n,alpha) and (n,alpha1) 525 1451   40
      results from the simultaneous standards analysis (Ca85) over 525 1451   41
      the standard energy range thermal to 100 keV.                525 1451   42
   2. Replacement of all major cross sections and elastic angular  525 1451   43
      distributions from 10-5 eV to 1 MeV with results from the    525 1451   44
      R-matrix analysis performed in conjunction with the          525 1451   45
      simultaneous standards analysis.                             525 1451   46
   3. Replaced the total cross section 1-20 MeV with results       525 1451   47
      from a covariance analysis of available data.                525 1451   48
   4. Revised elastic and inelastic cross sections for low-lying   525 1451   49
      levels incorporating new elastic, inelastic, and (n,xgamma)  525 1451   50
      experimental data. We attempted to better reconcile the      525 1451   51
      inelastic and gamma ray data.                                525 1451   52
   5. Refit all elastic angular distributions from 1-20 MeV with   525 1451   53
      Legendre expansions and incorporated results from new        525 1451   54
      measurements.                                                525 1451   55
   6. Fit inelastic neutron angular distributions for first 5      525 1451   56
      excited states of B10 with Legendre expansions.              525 1451   57
   7. Incorporated new (n,t2alpha) cross section data into MT113   525 1451   58
      and adjusted (n,alpha) cross sections above standard region  525 1451   59
      for better consistency with data as well as other cross      525 1451   60
      sections (esp. total and elastic) determined by data.        525 1451   61
                                                                   525 1451   62
 *****Note that covariance data will be added at a later date.     525 1451   63
                                                                   525 1451   64
****************************************************************** 525 1451   65
                                                                   525 1451   66
                        STANDARDS COVARIANCES                      525 1451   67
                                                                   525 1451   68
 Phase 1 reviewers of the ENDF/B-VI standards cross sections have  525 1451   69
 expressed the concern that the uncertainties resulting from the   525 1451   70
 combination of R-matrix and simultaneous evaluations might have   525 1451   71
 led to uncertainties that are too small.  As a result, the        525 1451   72
 Standards Subcommittee produced (at the May, 1990 CSEWG meeting)  525 1451   73
 a set of expanded covariance estimates for the standard cross     525 1451   74
 section reactions.  These uncertainties are estimates such that   525 1451   75
 if a modern day experiment were performed on a given standard     525 1451   76
 cross section using the best techniques, approximately 2/3 of     525 1451   77
 the results should fall within these expanded uncertainties. The  525 1451   78
 expanded uncertainties for the B-10(n,alpha0) and B-10(n,alpha1)  525 1451   79
 cross sections are given in the following tables and are          525 1451   80
 compared to values from the combined output of the standards      525 1451   81
 covariance analysis:                                              525 1451   82
                                                                   525 1451   83
                                                                   525 1451   84
                     B-10(n,alpha0) Cross Section                  525 1451   85
                                                                   525 1451   86
    Energy Range    Estimated Uncertainty    Combined Analysis     525 1451   87
      (keV)              (percent)               (percent)         525 1451   88
                                                                   525 1451   89
 1.0E-08 - 0.1               0.5                     0.21          525 1451   90
     0.1 - 5.0               1.5                                   525 1451   91
     5.0 - 30.               3.0                     0.38          525 1451   92
     30. - 90.               5.0                                   525 1451   93
     90. - 150               10.0                    0.86          525 1451   94
     150 - 200               12.0                                  525 1451   95
     200 - 250               15.0                    0.79          525 1451   96
                                                                   525 1451   97
                                                                   525 1451   98
                                                                   525 1451   99
                     B-10(n,alpha1) Cross Section                  525 1451  100
                                                                   525 1451  101
    Energy Range    Estimated Uncertainty    Combined Analysis     525 1451  102
      (keV)              (percent)               (percent)         525 1451  103
                                                                   525 1451  104
 1.0E-08 - 0.1               0.2                    0.16           525 1451  105
     0.1 - 5.0               0.4                                   525 1451  106
     5.0 - 30.               0.6                    0.20           525 1451  107
     30. - 90.               1.0                                   525 1451  108
     90. - 150               1.5                    0.48           525 1451  109
     150 - 200               2.0                                   525 1451  110
     200 - 250               2.5                    0.62           525 1451  111
                                                                   525 1451  112
 ****************************************************************  525 1451  113
                                                                   525 1451  114
 mf=2 --------- resonance parameters ----------------------------  525 1451  115
                                                                   525 1451  116
   mt=151  effective scattering radius = 4.129038-13 cm            525 1451  117
                                                                   525 1451  118
 mf=3 --------- smooth cross sections ---------------------------  525 1451  119
                                                                   525 1451  120
      the 2200 m/s cross sections are as follows,                  525 1451  121
          mt=1    sigma = 3842.146  barns                          525 1451  122
          mt=2    sigma = 2.142435  barns                          525 1451  123
          mt=102  sigma = 0.5       barns                          525 1451  124
          mt=103  sigma = 0.000566  barns                          525 1451  125
          mt=107  sigma = 3839.496  barns                          525 1451  126
          mt=113  sigma = 0.0069993 barns                          525 1451  127
          mt=600  sigma = 0.000566  barns                          525 1451  128
          mt=800  sigma = 241.2677  barns                          525 1451  129
          mt=801  sigma = 3598.228  barns                          525 1451  130
                                                                   525 1451  131
   mt=1        total cross section                                 525 1451  132
      0 to 1 mev, calculated from r-matrix parameters obtained     525 1451  133
          from simultaneous standards analysis (ca85) used to      525 1451  134
          obtain the endf/b-vi standard cross sections.            525 1451  135
      1 to 20 mev, covariance analysis of measurements of di67,    525 1451  136
          ts62,fo61,co52,au79, and co54, constrained to match      525 1451  137
          r-matrix fit at 1 mev. glucs covariance analysis code    525 1451  138
          (he80) was used in the calculations.                     525 1451  139
                                                                   525 1451  140
                                                                   525 1451  141
   mt=107   (n,alpha) cross section                                525 1451  142
      0 to 20 mev, sum of mt=800,801.                              525 1451  143
                                                                   525 1451  144
   mt=800     (n,alpha0) cross section                             525 1451  145
      0 to 1 mev, calculated from the r-matrix parameters          525 1451  146
          described for mt=1. experimental (n,alpha0) data input   525 1451  147
          to the fit were those of ma68 and da61. in addition, the 525 1451  148
          angular distributions of va72 for the inverse reaction   525 1451  149
          were included in the analysis.                           525 1451  150
      1 to 20 mev, based on da61 measurements, with smooth extra-  525 1451  151
          polation from 8 to 20 mev using 14-MeV data of an69. The 525 1451  152
          da61 data above approximately 2 mev were renormalized    525 1451  153
          by a factor of approximately 1.4. Note that some of the  525 1451  154
          structure seen in da61 was expanded to give consistent   525 1451  155
          nonelastic, elastic, and total cross sections when       525 1451  156
          compared with experimental data.                         525 1451  157
                                                                   525 1451  158
   mt=801     (n,alpha1) cross section                             525 1451  159
      0 to 1 mev, calculated from the r-matrix parameters          525 1451  160
          described for mt=1. experimental (n,alpha1) data in-     525 1451  161
          cluded in the fit are those of sc76. in addition, the    525 1451  162
          absolute differential cross-section measurements of      525 1451  163
          se76 were included in the analysis.                      525 1451  164
      1 to 20 mev, smooth curve through measurements of da61 and   525 1451  165
          ne70, with smooth extrapolation from 15 to 20 mev. the   525 1451  166
          da61 data above approximately 2 mev were renormalized    525 1451  167
          by a factor of approximately 1.4. Note that some of the  525 1451  168
          structure seen in da61 was expanded to give consistent   525 1451  169
          nonelastic, elastic, and total cross sections when       525 1451  170
          compared with experimental data.                         525 1451  171
                                                                   525 1451  172
                                                                   525 1451  173
                                                                   525 1451  174
 ----------------------- references -----------------------------  525 1451  175
                                                                   525 1451  176
 aj75   f. ajzenberg-selove, nucl. phys. a248,6 (1975)             525 1451  177
 aj88   f. ajzenberg-selove, nucl. phys. a490,1 (1988)             525 1451  178
 an69   B. Antolkovic, Nuc.Phys.A139, 10 (1969).                   525 1451  179
 as70   a. asami and m.c. moxon, j.nucl.energy 24,85 (1970)        525 1451  180
 au79   g.auchampaugh et al., nucl.sci.eng.69,30(1979)             525 1451  181
 ba60   r.bardes and g.e. owen, phys.rev.120,1369 (1960)           525 1451  182
 be56   r.l. becker and h.h. barschall, phys.rev.102,1384 (1956)   525 1451  183
 bo51   c.k.bockelman et al., phys.rev. 84,69 (1951)               525 1451  184
 bo69   d.bogart and l.l.nichols, nucl.phys.a125,463 (1969)        525 1451  185
 ca85   a.carlson et al., nuc.data for basic & applied science,    525 1451  186
        santa fe, nm (1985) p.1429.                                525 1451  187
 co52   j.h.coon et al., phys.rev. 88,562 (1952)                   525 1451  188
 co54   c.f.cook and t.w. bonner,phys.rev. 94,651 (1954)           525 1451  189
 co67   s.a. cox and f.r. pontet, j.nucl.energy 21,271 (1967)      525 1451  190
 co69   j.a. cookson and j.g.locke,nucl.phys.a146,417(1970)        525 1451  191
 co73   m.s. coates et al., priv. comm. to l.stewart (1973)        525 1451  192
 da56   r.b.day,phys.rev.102,767 (1956)                            525 1451  193
 da60   r.b. day and m.walt,phys.rev.117,1330 (1960)               525 1451  194
 da61   e.a. davis et al., nucl.phys.27,448 (1961)                 525 1451  195
 di67   k.m. diment, aere-r-5224 (1967)                            525 1451  196
 di88   j.k.dickens, proc.conf. on nuc.data for sci.& tech.,mito,  525 1451  197
        japan (1988) p.213.                                        525 1451  198
 fo61   d.m. fossan et al., phys.rev. 123,209 (1961)               525 1451  199
 fr56   g.m. frye and j.h. gammel,phys.rev. 103,328 (1956)         525 1451  200
 gl82   s.glendinning, nuc.sci.eng.80,256(1982)                    525 1451  201
 ha73   s.l.hausladen, thesis, ohio univ. coo-1717-5 (1973)        525 1451  202
 he80   d.hetrick & c.y.fu, ornl/tm-7341 (1980).                   525 1451  203
 hy69   m.hyakutake, eandc(j)-13 (1969) p.29                       525 1451  204
 ho69   j.c. hopkins, priv. comm. lasl (1969)                      525 1451  205
 ir67   d.c.irving, ornl-tm-1872 (1967)                            525 1451  206
 ka87   R.Kavanagh & R.Marcley, Phys.Rev.C36, 1194 (1987).         525 1451  207
 la71   r.o. lane et al., phys.rev.c4,380 (1971)                   525 1451  208
 ma68   r.l.macklin and j.h.gibbons,phys.rev.165,1147 (1968)       525 1451  209
 mo66   f.p.mooring et al.,nucl.phys.82,16 (1966)                  525 1451  210
 ne54   n.g.nereson,la-1655 (1954)                                 525 1451  211
 ne70   d.o.nellis et al., phys.rev. c1,847 (1970)                 525 1451  212
 po70   d.porter et al., awre o 45/70 (1970)                       525 1451  213
 qa85   S.Qaim et al., Santa Fe Conf. (1985)p.97.                  525 1451  214
 qa88   S.Qaim et al., Mito Conf. (1988) p.225.                    525 1451  215
 sa88   E.T. Sadowski, Ph.D thesis, Ohio U., (Nov.,1988).          525 1451  216
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 se76   r.m. sealock and j.c. overley, phys.rev.c13,2149 (1976)    525 1451  219
 si65   r.h.siemssen et al., nucl.phys.69,209 (1965)               525 1451  220
 sp73   r.r. spencer et al., eandc(e)147,al (1973)                 525 1451  221
 te62   k.tesch, nucl.phys.37,412 (1962)                           525 1451  222
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 wy58   m.e. wyman et al., phys.rev.112,1264 (1958)                525 1451  229
 ****************************************************************  525 1451  230
                                                                   525 1451  231
                                                                   525 1451  232
                                                                   525 1451  233
                                                                   525 1451  234
 ***************** Program LINEAR (VERSION 2002-1) *************** 525 1451  235
 For All Data Greater than 1.0000E-10 barns in Absolute Value      525 1451  236
 Data Linearized to Within an Accuracy of .100000000 per-cent      525 1451  237
 ***************** Program SIGMA1 (VERSION 2002-1) *************** 525 1451  238
 Data Doppler Broadened to 300.000000 Kelvin                       525 1451  239
 for All Data Greater than 1.0000E-10 barns in Absolute Value      525 1451  240
 Data Linearized to Within an Accuracy pf .100000000 per-cent      525 1451  241
 ***************** Program FIXUP (Version 2002-1) **************** 525 1451  242
 Corrected ZA/AWR in All Sections-----------------------------Yes  525 1451  243
 Corrected Thresholds-----------------------------------------Yes  525 1451  244
 Extended Cross Sections to 20 MeV----------------------------No   525 1451  245
 Allow Cross Section Deletion---------------------------------No   525 1451  246
 Allow Cross Section Reconstruction---------------------------No   525 1451  247
 Make All Cross Sections Non-Negative-------------------------Yes  525 1451  248
 Delete Energies Not in Ascending Order-----------------------Yes  525 1451  249
 Deleted Duplicate Points-------------------------------------Yes  525 1451  250
 Check for Ascending MAT/MF/MT Order--------------------------Yes  525 1451  251
 Check for Legal MF/MT Numbers--------------------------------Yes  525 1451  252
 Allow Creation of Missing Sections---------------------------No   525 1451  253
 Allow Insertion of Energy Points-----------------------------No   525 1451  254
 Create Uniform Energy Grid-----------------------------------No   525 1451  255
 Delete Section if Cross Section =0 at All Energies-----------Yes  525 1451  256
 ****************************************************************  525 1451  257
 ***************** Program GROUPIE (VERSION 2002-1) ************** 525 1451  258
 Unshielded Group Averages Using  640 Groups                       525 1451  259
 Weighting Spectrum: Flat (Constant) Spectrum                      525 1451  260
                                1        451        266          2 525 1451  261
                                2        151          4          1 525 1451  262
                                3        107        217          1 525 1451  263
                                3        800        217          1 525 1451  264
                                3        801        217          1 525 1451  265
                               33        107         26          1 525 1451  266
                                                                   525 1  099999
                                                                   525 0  0    0
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 1.000000-5 1.000000+4          0          0          0          0 525 2151    3
 3.000000+0 4.129038-1          0          0          0          0 525 2151    4
                                                                   525 2  099999
                                                                   525 0  0    0
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        641          1                                             525 3107    3
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 1.89999998 437.352915 2.00000000 426.522756 2.09999990 416.533362 525 3107   68
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                                                                   525 3  099999
                                                                   525 0  0    0
 5.01000E+3 9.92692E+0          0          0          0          1 52533107    1
 0.000000+0 0.000000+0          0        107          0          2 52533107    2
 0.000000+0 0.000000+0          1          5         36          8 52533107    3
 1.000000-5 1.010000+6 3.000000+6 5.000000+6 7.000000+6 1.100000+7 52533107    4
 1.500000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 52533107    5
 0.000000+0 0.000000+0 0.000000+0 2.250000-2 7.000000-3 2.000000-3 52533107    6
 0.000000+0 0.000000+0 0.000000+0 3.240000-2 1.000000-3 3.000000-4 52533107    7
 0.000000+0 0.000000+0 1.690000-2 6.000000-3 2.000000-3 0.000000+0 52533107    8
 2.040000-2 7.000000-3 2.000000-3 1.280000-2 4.000000-3 1.690000-2 52533107    9
 0.000000+0 0.000000+0          1          5         91         13 52533107   10
 1.000000-5 1.000000+0 1.000000+2 9.000001+2 9.000000+3 3.750000+4 52533107   11
 9.000000+4 1.350000+5 2.050000+5 2.750000+5 4.125000+5 6.750000+5 52533107   12
 1.010000+6 2.490741-6 2.484915-6 2.438099-6 2.368409-6 2.230656-6 52533107   13
 1.982202-6 1.807934-6 1.568326-6 1.552257-6 1.555066-6 1.157951-6 52533107   14
 1.015610-6 2.484192-6 2.461351-6 2.413927-6 2.243903-6 2.000165-6 52533107   15
 1.927335-6 1.633085-6 1.490809-6 1.647004-6 1.200942-6 1.128964-6 52533107   16
 2.552806-6 2.624028-6 2.350393-6 2.167907-6 2.540208-6 1.939686-6 52533107   17
 1.230224-6 2.113235-6 1.424748-6 1.662929-6 2.916571-6 2.927420-6 52533107   18
 3.121191-6 3.670394-6 2.363825-6 1.299338-6 2.929283-6 1.881633-6 52533107   19
 2.253798-6 4.641171-6 6.294455-6 5.607427-6 2.930722-6 2.917079-6 52533107   20
 4.089449-6 2.707325-6 2.287332-6 1.083199-5 1.198476-5 7.899932-6 52533107   21
 5.246804-6 7.085706-6 4.943829-6 5.243390-6 2.019061-5 1.881386-5 52533107   22
 8.922377-6 9.271985-6 7.711829-6 9.574556-6 2.834902-5 2.180783-5 52533107   23
 7.471345-6 8.265557-6 6.775191-6 3.334345-5 1.719968-5 8.391731-6 52533107   24
 6.705476-6 4.365900-5 1.552481-5 1.322365-5 4.232958-5 2.020522-5 52533107   25
 1.222438-4                                                        52533107   26
                                                                   52533  099999
                                                                   525 0  0    0
                                                                     0 0  0    0
 9.01900E+3 1.88352E+1          0          0         34         10 925 1451    1
 0.0        0.0                 0          0          0          6 925 1451    2
 1.00000E+0 3.00001E+7          0          0         10       2002 925 1451    3
 3.00000E+2 0.0                 1          0        164          4 925 1451    4
  9-F - 19 FEI        EVAL-OCT01 K.I.Zolotarev                     925 1451    5
                      DIST-Feb2004                                 925 1451    6
----IRDF-2002         MATERIAL  925                                925 1451    7
-----INCIDENT NEUTRON DATA                                         925 1451    8
------ENDF-6 FORMAT                                                925 1451    9
*****************************************************************  925 1451   10
  9-F -19  FEI        EVAL-OCT01 K.I.Zolotarev                     925 1451   11
                      DIST-JAN02                       20020125    925 1451   12
----BROND-2           MATERIAL  925                                925 1451   13
-----INCIDENT NEUTRON DATA                                         925 1451   14
------ENDF-6 FORMAT                                                925 1451   15
------Russian Reactor Dosimetry File RRDF-2002                     925 1451   16
*****************************************************************  925 1451   17
Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko            925 1451   18
*****************************************************************  925 1451   19
MF= 3                                                              925 1451   20
MT= 16 -(n,2n) cross section data                                  925 1451   21
--------------------------------------                             925 1451   22
    Excitation function for the  F-19(n,2n)F-18  reaction  in the  925 1451   23
energy region from threshold to 30 MeV was evaluated  by means of  925 1451   24
statistical analysis of experimental cross section data [1-17] and 925 1451   25
data from GNASH [18,19] calculation.                               925 1451   26
    Experimental data [2-3],[5],[9-13],[15-17]  were renormalized  925 1451   27
to  the new standards for monitor reactions cross sections.  Data  925 1451   28
of Mc Crary et al. [1], Rayburn et al.[2], Bormann et al.[4], and  925 1451   29
Shiokawa et al. [7]  were renormalized  to the results of precise  925 1451   30
measurements Vonach et al. [9] and Ikeda et al. [15] in the 14 MeV 925 1451   31
region. Data of Chatterjee et al. [8] were corrected to their pre- 925 1451   32
vious measurements at the 14.8 MeV point [6]. Results of measure-  925 1451   33
ments of Nagel [5] were taken only from SUBENT 005, EXFOR 20198.   925 1451   34
    Experimental cross section data from ref. [20-31] were rejec-  925 1451   35
ted due to their big discrepancy with the main bulk of experimen-  925 1451   36
al data [1-17] and data from theoretical model calculation.        925 1451   37
    The final procedure of evaluation  F-19(n,2n)F-18  excitation  925 1451   38
function from threshold to 30 MeV has been carried out within the  925 1451   39
framework of generalized least squares method.  Rational function  925 1451   40
was used  as  model function [32].  Calculations was performed by  925 1451   41
means of  Pade-2 code [33].                                        925 1451   42
     U-235 thermal fission [34] and  Cf-252 spontaneous  fission   925 1451   43
neutron spectra [35] averaged cross-sections calculated from the   925 1451   44
evaluated F-19(n,2n)F-18 excitation function are the following:    925 1451   45
                                                                   925 1451   46
 ----------------------------------------------------------------- 925 1451   47
    TYPE OF SPECTRUM   I <CS>,mb (calc.) I   <CS>, mb (measured)   925 1451   48
 ----------------------I-----------------I------------------------ 925 1451   49
 U-235 neutron fission I   0.007299      I 0.007200+-0.001000 [36] 925 1451   50
                       I                 I 0.006509+-0.000300 [37] 925 1451   51
                       I                 I 0.008653+-0.000464 [38] 925 1451   52
 ----------------------I-----------------I------------------------ 925 1451   53
 CF-252 spont. fission I   0.01615       I 0.01628+-0.00054   [39] 925 1451   54
                       I                 I 0.01612+-0.00054   [40] 925 1451   55
 ----------------------------------------------------------------- 925 1451   56
                                                                   925 1451   57
MF=33                                                              925 1451   58
MT= 16 -(n,2n) cross section cov. matrix                           925 1451   59
---------------------------------------------                      925 1451   60
    Uncertainties in the evaluated  excitation function  for the   925 1451   61
reaction  F-19(n,2n)F-18 are given in the form of relative covari- 925 1451   62
ance matrix  for the 26-neutron energy groups (LB=5).  Covariance  925 1451   63
matrix  of  uncertainties  was  calculated  simultaneously  with   925 1451   64
recommended cross section data by means of PADE-2 code.            925 1451   65
    Eigenvalues  of the  6-th digits  relative covariance matrix   925 1451   66
given in the 33-file are the following:                            925 1451   67
                                                                   925 1451   68
    3.67622E-08    3.74071E-08    3.79051E-08    3.91111E-08       925 1451   69
    4.11094E-08    4.32321E-08    4.68199E-08    4.98738E-08       925 1451   70
    5.55426E-08    6.01322E-08    7.00100E-08    7.85485E-08       925 1451   71
    9.57150E-08    1.06820E-07    1.28694E-07    1.47868E-07       925 1451   72
    2.58858E-07    6.32301E-07    3.80384E-06    5.45023E-04       925 1451   73
    1.36448E-03    3.28506E-03    8.26671E-03    1.39754E-02       925 1451   74
    1.58981E-02    6.37025E-02                                     925 1451   75
                                                                   925 1451   76
References :                                                       925 1451   77
 1. J.H.Mc Crary,I.L.Morgan  Bull. American Phys. Soc., v.5,       925 1451   78
    p.246, April 1960 ;                                            925 1451   79
    J.H.Mc Crary,I.L.Morgan  Report AFSWC-TR-60-30, 1960           925 1451   80
 2. L.A.Rayburn  Proc. of Conf. on Direct Interactions and Nuclear 925 1451   81
    Reaction Mechanisms, Padua, 3-8 September 1962,  Gordon and    925 1451   82
    Breach, New York, 1963, p.322. ;                               925 1451   83
    L.A.Rayburn  Bull. Am. Phys. Soc., v.7, p.335, April 1962      925 1451   84
 3. M.Cevolani, S.Petralia  Nuovo Cimento, v.26, p.1328, Dec.1962  925 1451   85
 4. M.Bormann et al. Nucl. Phys., v.63, p.438, March 1965          925 1451   86
 5. W.Nagel  EXFOR 20198.005, 1966                                 925 1451   87
 6. A.Chatterjee et al. Progress Report BARC-305, p.30, Nov. 1967  925 1451   88
 7. T.Shiokawa et al. J. Inorg. Nucl. Chem., v.30, p.1, Jan. 1968  925 1451   89
 8. A.Chatterjee e.a. Proc.of Symposium Nucl.Phys. and Solid State 925 1451   90
    Phys., Roorke, India, 1969, v.2, p.117, December 1969          925 1451   91
 9. H.K.Vonach et al.  Proc. of 2-nd Conference on Nuclear Cross-  925 1451   92
    Sections and Technology, Washington D.C., 4-7 March 1968, v.2, 925 1451   93
    p.885                                                          925 1451   94
10. R.C.Barrall et al.  Report AFWL-TR-68-134, March 1969          925 1451   95
11. R.Mogharrab, H.Neuert Atomkernenergie, v.19, p.107, April 1972 925 1451   96
12. J.C.Robertson et al.  J. Nucl. Energ., v.27, p.531, Aug. 1973  925 1451   97
13. R.A.Sigg  Dissert. Abstr., sect. B, v.37, p.2237, Nov. 1976    925 1451   98
14. T.B.Ryves et al.  J. of Physics, pt.G, v.4, n.11, p.1783, 1978 925 1451   99
15. Y.Ikeda et al.  Report JAERI-1312, 1988                        925 1451  100
16. I.Kimura, K.Kobayashi  Nucl. Sci. Eng., v.106, p.332, 1990     925 1451  101
17. C.L.Hartmann, P.M.DeLuca  Nucl. Sci. Eng., v.109, p.319, 1991  925 1451  102
18. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear     925 1451  103
    Model Code for Calculation of Cross Section and Emission       925 1451  104
    Spectra. Report LA-6947, Los Alamos, 1977                      925 1451  105
19. E.L.Trykov, G.Ya.Tertychnyi  Private communication, IPPE,      925 1451  106
    Obninsk, May 1999                                              925 1451  107
20. E.B.Paul, R.L.Clarke  Canadian J. Phys., v.31, p.267, 1953     925 1451  108
21. V.J.Ashby e.a.  Phys. Rev., v.111, p.616, 1958                 925 1451  109
22. L.A.Rayburn  Phys. Rev., v.122, p.168, 1961                    925 1451  110
23. O.D.Brill et al.  Doklady Akademii Nauk, v.136,n.1,p.55, 1961; 925 1451  111
    O.D.Brill et al.  Soviet Physics-Doklady, v.6, p.24, 1961      925 1451  112
24. J.Picard, C.F.Williamson  Nucl. Phys., v.63, p.673, April 1965 925 1451  113
25. J.E.Strain, W.J.Ross  Report ORNL-3672, January 1965           925 1451  114
26. J.Csikai  Report EANDC-50 S, paper 102, July 1965              925 1451  115
27. A.Pasquarelli  Nucl. Phys. A, v.93, p.218, March 1967          925 1451  116
28. M.Bormann, I.Riehle  Zeitschrift f.Physik, v.207, p.64,        925 1451  117
    October 1967                                                   925 1451  118
29. H.O.Menlove et al.  Phys. Rev., v.163, p.1308, 1967            925 1451  119
30. D.Crumpton  J.Inorg. Nucl. Chem., v.31, p.3727, December 1969  925 1451  120
31. J.Araminowicz, J.Dresler  Report INR-1464, p.14, May 1973      925 1451  121
32. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali-  925 1451  122
    st's Meeting on Evaluation and Processing of Covariance Data,  925 1451  123
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105   925 1451  124
33. S.A.Badikov et.al.  Preprint FEI-1686, Obninsk, 1985           925 1451  125
34. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI  925 1451  126
    Library, MAT=9228, MF=5, MT=18, eval. April 1989               925 1451  127
35. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987         925 1451  128
36. F.Nasyrov, B.D.Sciborskij  Atomnaja Energija, v.25, no.5,      925 1451  129
    p.437, November 1968                                           925 1451  130
37. M.Najzer, J.Rant  Report IAEA-208, v.2, p.247, 1978            925 1451  131
38. W.Mannhart   Progress Report INDC(Ger)-045, pp.40-43, 1999     925 1451  132
39. W.Mannhart  Handbook on Nuclear Activation Data. IAEA Tech-    925 1451  133
    nical Report series No.273, p.413, 1987                        925 1451  134
40. W.Mannhart  Validation of Differential Cross Sections with     925 1451  135
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna,  925 1451  136
    September 2002                                                 925 1451  137
*****************************************************************  925 1451  138
 File 2 added to the pointwise file containing only the effective  925 1451  139
 scattering radius with no resonance parameters given.             925 1451  140
 Taken from ENDF/B-VI                                              925 1451  141
                                                                   925 1451  142
*****************************************************************  925 1451  143
 ***************** Program LINEAR (VERSION 2002-1) *************** 925 1451  144
 For All Data Greater than 1.0000E-10 barns in Absolute Value      925 1451  145
 Data Linearized to Within an Accuracy of .100000000 per-cent      925 1451  146
 ***************** Program SIGMA1 (VERSION 2002-1) *************** 925 1451  147
 Data Doppler Broadened to 300.000000 Kelvin                       925 1451  148
 for All Data Greater than 1.0000E-10 barns in Absolute Value      925 1451  149
 Data Linearized to Within an Accuracy pf .100000000 per-cent      925 1451  150
 ***************** Program FIXUP (Version 2002-1) **************** 925 1451  151
 Corrected ZA/AWR in All Sections-----------------------------Yes  925 1451  152
 Corrected Thresholds-----------------------------------------Yes  925 1451  153
 Extended Cross Sections to 20 MeV----------------------------No   925 1451  154
 Allow Cross Section Deletion---------------------------------No   925 1451  155
 Allow Cross Section Reconstruction---------------------------No   925 1451  156
 Make All Cross Sections Non-Negative-------------------------Yes  925 1451  157
 Delete Energies Not in Ascending Order-----------------------Yes  925 1451  158
 Deleted Duplicate Points-------------------------------------Yes  925 1451  159
 Check for Ascending MAT/MF/MT Order--------------------------Yes  925 1451  160
 Check for Legal MF/MT Numbers--------------------------------Yes  925 1451  161
 Allow Creation of Missing Sections---------------------------No   925 1451  162
 Allow Insertion of Energy Points-----------------------------No   925 1451  163
 Create Uniform Energy Grid-----------------------------------No   925 1451  164
 Delete Section if Cross Section =0 at All Energies-----------Yes  925 1451  165
 ***************** Program GROUPIE (VERSION 2002-1) ************** 925 1451  166
 Unshielded Group Averages Using  640 Groups                       925 1451  167
 Weighting Spectrum: Flat (Constant) Spectrum                      925 1451  168
                                1        451        172          1 925 1451  169
                                2        151          4          1 925 1451  170
                                3         16         34          1 925 1451  171
                               33         16         71          1 925 1451  172
                                                                   925 1  099999
                                                                   925 0  0    0
 9.01900E+3 1.88352E+1          0          0          1          0 925 2151    1
 9.019000+3 1.000000+0          0          0          1          0 925 2151    2
 1.000000-5 2.000000+7          0          0          0          0 925 2151    3
 5.000000-1 5.360000-1          0          0          0          0 925 2151    4
                                                                   925 2  099999
                                                                   925 0  0    0
 9.01900E+3 1.88352E+1          0          0          0          0 925 3 16    1
-1.04322E+7-1.04322E+7          0          0          1         92 925 3 16    2
         92          1                                             925 3 16    3
 10900000.0 2.02752E-6 11000000.0 5.63229E-5 11100000.0 .000137655 925 3 16    4
 11200000.0 .000292275 11300000.0 .000548721 11400000.0 .000917543 925 3 16    5
 11500000.0 .001402145 11600000.0 .002002095 11700000.0 .002714490 925 3 16    6
 11800000.0 .003534705 11900000.0 .004456885 12000000.0 .005474310 925 3 16    7
 12100000.0 .006579685 12200000.0 .007765400 12300000.0 .009023740 925 3 16    8
 12400000.0 .010347050 12500000.0 .011727850 12600000.0 .013159000 925 3 16    9
 12700000.0 .014633700 12800000.0 .016152650 12900000.0 .017695750 925 3 16   10
 13000000.0 .019265950 13100000.0 .020863250 13200000.0 .022460550 925 3 16   11
 13300000.0 .024071763 13400000.0 .025696888 13500000.0 .027322013 925 3 16   12
 13600000.0 .028947138 13700000.0 .030572263 13800000.0 .032197388 925 3 16   13
 13900000.0 .033822513 14000000.0 .035447638 14100000.0 .037049625 925 3 16   14
 14200000.0 .038628475 14300000.0 .040207325 14400000.0 .041786175 925 3 16   15
 14500000.0 .043331888 14600000.0 .044844463 14700000.0 .046357038 925 3 16   16
 14800000.0 .047869613 14900000.0 .049339675 15000000.0 .050767225 925 3 16   17
 15100000.0 .052194775 15200000.0 .053622325 15300000.0 .054999450 925 3 16   18
 15400000.0 .056326150 15500000.0 .057652850 15600000.0 .058979550 925 3 16   19
 15700000.0 .060248850 15800000.0 .061460750 15900000.0 .062672650 925 3 16   20
 16000000.0 .063884550 16100000.0 .065033000 16200000.0 .066118000 925 3 16   21
 16300000.0 .067203000 16400000.0 .068288000 16500000.0 .069304550 925 3 16   22
 16600000.0 .070252650 16700000.0 .071200750 16800000.0 .072148850 925 3 16   23
 16900000.0 .073024838 17000000.0 .073828713 17100000.0 .074632588 925 3 16   24
 17200000.0 .075436463 17300000.0 .076166188 17400000.0 .076821763 925 3 16   25
 17500000.0 .077477338 17600000.0 .078132913 17700000.0 .078714000 925 3 16   26
 17800000.0 .079220600 17900000.0 .079727200 18000000.0 .080233800 925 3 16   27
 18100000.0 .080667413 18200000.0 .081028038 18300000.0 .081388663 925 3 16   28
 18400000.0 .081749288 18500000.0 .082040025 18600000.0 .082260875 925 3 16   29
 18700000.0 .082481725 18800000.0 .082702575 18900000.0 .082858125 925 3 16   30
 19000000.0 .082948375 19100000.0 .083038625 19200000.0 .083128875 925 3 16   31
 19300000.0 .083180900 19400000.0 .083152770 19500000.0 .083082710 925 3 16   32
 19600000.0 .083012650 19700000.0 .082942590 19800000.0 .082872530 925 3 16   33
 19900000.0 .082740370 20000000.0 0.0                              925 3 16   34
                                                                   925 3  099999
                                                                   925 0  0    0
 9.01900E+3 1.88352E+1          0          0          0          1 92533 16    1
 0.000000+0 0.000000+0          0         16          0          1 92533 16    2
 0.000000+0 0.000000+0          1          5        406         28 92533 16    3
 1.000000-5 1.090000+7 1.200000+7 1.250000+7 1.300000+7 1.350000+7 92533 16    4
 1.400000+7 1.450000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7 92533 16    5
 1.700000+7 1.750000+7 1.800000+7 1.850000+7 1.900000+7 1.950000+7 92533 16    6
 2.000000+7 2.100000+7 2.200000+7 2.300000+7 2.400000+7 2.500000+7 92533 16    7
 2.700000+7 2.800000+7 2.900000+7 3.000000+7 0.000000+0 0.000000+0 92533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16   12
 0.000000+0 7.844560-3 4.898350-3 3.027060-3 1.929170-3 1.321910-3 92533 16   13
 9.926111-4 8.097050-4 6.990610-4 6.218640-4 5.596050-4 5.048120-4 92533 16   14
 4.555230-4 4.121780-4 3.758470-4 3.473540-4 3.269110-4 3.140740-4 92533 16   15
 3.073570-4 3.120960-4 3.231580-4 3.310920-4 3.298620-4 3.041000-4 92533 16   16
 2.525070-4 2.039030-4 1.464150-4 3.648070-3 2.360540-3 1.449110-3 92533 16   17
 9.104930-4 6.319380-4 5.059420-4 4.569550-4 4.388680-4 4.266530-4 92533 16   18
 4.088340-4 3.819840-4 3.470900-4 3.071470-4 2.656870-4 2.259100-4 92533 16   19
 1.902720-4 1.486420-4 1.141580-4 1.016320-4 1.039070-4 1.134800-4 92533 16   20
 1.281520-4 1.350840-4 1.314670-4 1.212070-4 1.826270-3 1.354210-3 92533 16   21
 9.782671-4 7.059900-4 5.267220-4 4.207220-4 3.665780-4 3.449020-4 92533 16   22
 3.398810-4 3.397380-4 3.365240-4 3.256910-4 3.054490-4 2.760780-4 92533 16   23
 2.392420-4 1.754770-4 8.900070-5 1.611170-5-3.205140-5-5.099350-5 92533 16   24
-2.365820-5 5.330250-5 1.291950-4 2.188860-4 1.233180-3 1.050650-3 92533 16   25
 8.482810-4 6.625510-4 5.129570-4 4.047920-4 3.347390-4 2.952800-4 92533 16   26
 2.776250-4 2.733860-4 2.755370-4 2.787900-4 2.796490-4 2.762050-4 92533 16   27
 2.614270-4 2.288330-4 1.889520-4 1.513570-4 1.231830-4 1.085890-4 92533 16   28
 1.236560-4 1.520640-4 1.922260-4 1.030240-3 9.309550-4 7.910340-4 92533 16   29
 6.422140-4 5.056870-4 3.931520-4 3.093600-4 2.543630-4 2.252570-4 92533 16   30
 2.174790-4 2.257800-4 2.449250-4 2.701550-4 3.105180-4 3.558030-4 92533 16   31
 3.811660-4 3.836510-4 3.655150-4 3.091160-4 2.316670-4 1.739440-4 92533 16   32
 1.144030-4 9.301140-4 8.611210-4 7.506000-4 6.229440-4 4.974770-4 92533 16   33
 3.876710-4 3.015590-4 2.426370-4 2.107830-4 2.032840-4 2.157690-4 92533 16   34
 2.430530-4 3.003160-4 3.817500-4 4.465680-4 4.803090-4 4.784630-4 92533 16   35
 4.115300-4 2.889300-4 1.821310-4 6.207860-5 8.648120-4 8.135850-4 92533 16   36
 7.261930-4 6.210140-4 5.137590-4 4.162000-4 3.360620-4 2.773020-4 92533 16   37
 2.407400-4 2.248090-4 2.263440-4 2.532360-4 3.094430-4 3.658040-4 92533 16   38
 4.035410-4 4.133410-4 3.692840-4 2.697090-4 1.753330-4 6.488820-5 92533 16   39
 8.276580-4 7.994630-4 7.403910-4 6.622230-4 5.756870-4 4.895590-4 92533 16   40
 4.102830-4 3.420170-4 2.868660-4 2.452630-4 2.075860-4 1.890180-4 92533 16   41
 1.937990-4 2.070150-4 2.180840-4 2.167570-4 1.920930-4 1.606910-4 92533 16   42
 1.194350-4 8.367870-4 8.381600-4 8.077220-4 7.513760-4 6.760250-4 92533 16   43
 5.886680-4 4.958200-4 4.031020-4 3.150170-4 2.001340-4 8.278800-5 92533 16   44
 1.074360-5-2.078540-5-2.009100-5 2.343720-5 9.478700-5 1.508320-4 92533 16   45
 2.094530-4 9.030970-4 9.293760-4 9.163470-4 8.669560-4 7.869960-4 92533 16   46
 6.839560-4 5.660230-4 4.412210-4 2.582200-4 4.586960-5-1.068070-4 92533 16   47
-1.912730-4-2.107930-4-1.358110-4 2.138250-5 1.612100-4 3.183170-4 92533 16   48
 1.012600-3 1.049310-3 1.037800-3 9.812610-4 8.866920-4 7.633760-4 92533 16   49
 6.215440-4 3.970180-4 1.170730-4-1.006010-4-2.340860-4-2.800390-4 92533 16   50
-1.974460-4 1.093280-5 2.077500-4 4.350440-4 1.136340-3 1.170610-3 92533 16   51
 1.152160-3 1.086070-3 9.810220-4 8.476920-4 6.195350-4 3.158060-4 92533 16   52
 6.329550-5-1.052330-4-1.794050-4-1.175480-4 9.273780-5 3.048660-4 92533 16   53
 5.562250-4 1.254720-3 1.286290-3 1.267530-3 1.204830-3 1.107390-3 92533 16   54
 9.184080-4 6.431870-4 3.946850-4 2.121830-4 1.124980-4 1.261560-4 92533 16   55
 2.843660-4 4.638940-4 6.851270-4 1.376450-3 1.420770-3 1.422120-3 92533 16   56
 1.386320-3 1.278440-3 1.085040-3 8.822720-4 7.106800-4 5.921990-4 92533 16   57
 5.353610-4 5.914810-4 6.921020-4 8.298950-4 1.539830-3 1.622460-3 92533 16   58
 1.669850-3 1.679580-3 1.616300-3 1.498950-3 1.363950-3 1.236560-3 92533 16   59
 1.094900-3 1.009270-3 9.922760-4 1.001160-3 1.798240-3 1.944450-3 92533 16   60
 2.099870-3 2.205700-3 2.207720-3 2.133310-3 2.009010-3 1.777510-3 92533 16   61
 1.524740-3 1.362900-3 1.209860-3 2.198710-3 2.517890-3 2.820120-3 92533 16   62
 2.967440-3 2.974120-3 2.866070-3 2.549010-3 2.119470-3 1.798830-3 92533 16   63
 1.465550-3 3.093180-3 3.712880-3 4.106620-3 4.263970-3 4.206430-3 92533 16   64
 3.790030-3 3.114020-3 2.560510-3 1.957740-3 4.741660-3 5.470710-3 92533 16   65
 5.854090-3 5.903210-3 5.430360-3 4.514070-3 3.710880-3 2.809610-3 92533 16   66
 6.497010-3 7.107000-3 7.299680-3 6.881850-3 5.882950-3 4.952680-3 92533 16   67
 3.884000-3 7.920590-3 8.280630-3 8.031330-3 7.128890-3 6.218540-3 92533 16   68
 5.143690-3 8.820440-3 8.840330-3 8.205440-3 7.459920-3 6.540140-3 92533 16   69
 9.408330-3 9.443150-3 9.180490-3 8.759390-3 1.037760-2 1.080020-2 92533 16   70
 1.110710-2 1.176100-2 1.264710-2 1.416170-2                       92533 16   71
                                                                   92533  099999
                                                                   925 0  0    0
                                                                     0 0  0    0
 1.10230E+4 2.27923E+1          0          0         34         101125 1451    1
 0.0        0.0                 0          0          0          61125 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20021125 1451    3
 3.00000E+2 0.0                 1          0        214          61125 1451    4
 11-Na- 23 ORNL,TOH   EVAL-DEC77 D. C. LARSON,S.IWASAKI           1125 1451    5
                      DIST-Feb2004                                1125 1451    6
----IRDF-2002         MATERIAL 1125                               1125 1451    7
-----INCIDENT NEUTRON DATA                                        1125 1451    8
------ENDF-6 FORMAT                                               1125 1451    9
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1125 1451   10
DOSIMETRY                                                         1125 1451   11
******************************************************************1125 1451   12
 11-NA- 23 ORNL       EVAL-DEC77 D. C. LARSON                     1125 1451   13
                      DIST-SEP 1 REV1-JUL91            20010926   1125 1451   14
----ENDF/B-VI         MATERIAL 1125         REVISION 1            1125 1451   15
                                                                  1125 1451   16
 **************************************************************** 1125 1451   17
 11-NA- 23 TOH        EVAL-AUG96 S.IWASAKI                        1125 1451   18
                      DIST-JUL98                                  1125 1451   19
----JENDL/D-99        MATERIAL 1125                               1125 1451   20
-----INCIDENT NEUTRON DATA                                        1125 1451   21
------ENDF-6 FORMAT                                               1125 1451   22
 <DOSIMETRY CROSS SECTION>                                        1125 1451   23
      NA-23 (N,2N) NA-22 (HALF-LIFE = 2.6019Y)                    1125 1451   24
 **************************************************************** 1125 1451   25
 ================================================================ 1125 1451   26
 **************  Start of ENDF/B-VI Bibliography  **************  1125 1451   27
 ================================================================ 1125 1451   28
 ENDF/B-VI MOD 2 Revision, September 2000, S.C.Frankle, R.C.Reedy,1125 1451   29
                 P.G.Young (LANL)                                 1125 1451   30
                                                                  1125 1451   31
 The secondary gamma-ray spectrum for radiative capture (MF 12,   1125 1451   32
 MT 102) has been updated using new experimental data.            1125 1451   33
 The previous evaluation (MOD 1: 61 gamma rays) is replaced with  1125 1451   34
 292 discrete gamma rays based on thermal neutron experimental    1125 1451   35
 data. Thermal spectrum assumed to 20 MeV.                        1125 1451   36
 The Q-value for radiative capture was also updated in File 3.    1125 1451   37
                                                                  1125 1451   38
 Gas production added as MF=3, MT=203,207                         1125 1451   39
                                                                  1125 1451   40
 Details of these changes are described in Frankle et al. [Fr01]. 1125 1451   41
                                                                  1125 1451   42
****************************************************************  1125 1451   43
                                                                  1125 1451   44
 ENDF/B-VI MOD 1 Revision, July 1991, V. McLane (NNDC)            1125 1451   45
                                                                  1125 1451   46
 REVISION 1 CORRECTION                                            1125 1451   47
                                                                  1125 1451   48
 Corrected number of energy ranges in File 32, MT = 151 to be 1.  1125 1451   49
                                                                  1125 1451   50
****************************************************************  1125 1451   51
                                                                  1125 1451   52
 ENDF/B-VI MOD 0, January 1990 (NNDC)                             1125 1451   53
                                                                  1125 1451   54
 ENDF/B-V Material 1311 converted to ENDF-6 format by NNDC.       1125 1451   55
                                                                  1125 1451   56
****************************************************************  1125 1451   57
                                                                  1125 1451   58
 ENDF/B-V Evaluation, December 1977, D. C. Larson (ORNL)          1125 1451   59
                                                                  1125 1451   60
MF=2                                                              1125 1451   61
   Resonance parameters are used from 600 eV to 500 keV.  The     1125 1451   62
 thermal capture cross section is given as 528 mb, in agreement   1125 1451   63
 with the experimental results of 526.9+-4.5 mb [RY71], as well   1125 1451   64
 as earlier results summarized in [RY71].  Using resonance        1125 1451   65
 parameters E=2.81 keV, GN=376 eV, and GG=0.353 eV for the large  1125 1451   66
 2.81 keV resonance gives the correct thermal capture value using 1125 1451   67
 a Breit-Wigner shape, and this form is used to calculate the     1125 1451   68
 capture crposs section from 1.0E-5 to 600 eV.  The capture       1125 1451   69
 width GG=0.353 eV is consistent with a recent result by Wilson   1125 1451   70
 [WI77] where they find 0.24<GG<0.4 eV with a 90% confidence      1125 1451   71
 level, and with a recent preliminary result of Macklin [MA76]    1125 1451   72
 where he found GG=0.385+-0.04 eV.  The GN and ER values are      1125 1451   73
 taken from Seltzer [SE74].  From 600 eV to 500 keV, the capture  1125 1451   74
 cross section is generated from resonance areas reported by      1125 1451   75
 Musgrove [MU77], and neutron widths and spins obtained from      1125 1451   76
 a multilevel analysis of the transmission data of Larson [LA76]. 1125 1451   77
                                                                  1125 1451   78
MF=3                                                              1125 1451   79
   MT=1  Resonance parameters + data of Larson [LA76].            1125 1451   80
   MT=2  MT=1 - MT=3                                              1125 1451   81
   MT=102  As discussed above, the shape of the capture cross     1125 1451   82
     section from 1.E-5 eV to 600 eV was taken from a single      1125 1451   83
     level Breit-Wigner form from 600 eV to 500 keV, File 3 gives 1125 1451   84
     no contribution.  From 500 keV to 20 MeV the capture file is 1125 1451   85
     the same as the ENDF/B-IV file by Pitterle and Paik [PI72].  1125 1451   86
MF=33                                                             1125 1451   87
   Uncertainty files for the capture cross section are estimated  1125 1451   88
 from the literature, and the spread in the various data sets.    1125 1451   89
                                                                  1125 1451   90
***************************************************************** 1125 1451   91
                                                                  1125 1451   92
REFERENCES                                                        1125 1451   93
                                                                  1125 1451   94
[Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos       1125 1451   95
   National Laboratory Report, LA-13812 (2001).                   1125 1451   96
[HE75] Hermsdorf et al., Report INDC(GDR)-2/L                     1125 1451   97
[KI76] W.E. Kinney and F.G. Perey, private communication          1125 1451   98
[LA76] D.C. Larson, J. Harvey and Hill, Oak Ridge National        1125 1451   99
   report ORNL-TM-5614 (1976)                                     1125 1451  100
[LA77] D.C. Larson and G.L. Morgan, to be published               1125 1451  101
[MA76] R.L. Macklin, private communication (1976)                 1125 1451  102
[MU77] Musgrove, Allen, and R.L. Macklin, preprint (1977)         1125 1451  103
[PI72] Pitterle and Paik, report WARD 3045T4B-2, Appendix A (1972)1125 1451  104
[RY71] T.B. Ryves, 71 Canterbury Conference p. 139                1125 1451  105
[SE74] J. Seltzer and F.W.K. Firk, Nucl.Sci.Eng. 53, 415 (1974)   1125 1451  106
[WI77] Wilson, Jackson, and Thomas, Nucl.Sci.Eng. 63, 55 (1977)   1125 1451  107
 ================================================================ 1125 1451  108
 ******** Processing history of ENDF/B-VI (n,g) component ******* 1125 1451  109
 ================================================================ 1125 1451  110
 ************************ C O N T E N T S *********************** 1125 1451  111
 ***************** Program LINEAR (VERSION 2002-1) ***************1125 1451  112
 For All Data Greater than 1.0000E-10 barns in Absolute Value     1125 1451  113
 Data Linearized to Within an Accuracy of .100000000 per-cent     1125 1451  114
 ***************** Program RECENT (VERSION 2002-1) ***************1125 1451  115
 for All Data Greater than 1.0000E-10 barns in Absolute Value     1125 1451  116
 Data Linearized to within an Accuracy of .100000000 per-cent     1125 1451  117
 ***************** Program SIGMA1 (VERSION 2002-1) ***************1125 1451  118
 Data Doppler Broadened to 300.000000 Kelvin                      1125 1451  119
 for All Data Greater than 1.0000E-10 barns in Absolute Value     1125 1451  120
 Data Linearized to Within an Accuracy pf .100000000 per-cent     1125 1451  121
 ***************** Program FIXUP (Version 2002-1) ****************1125 1451  122
 Corrected ZA/AWR in All Sections-----------------------------Yes 1125 1451  123
 Corrected Thresholds-----------------------------------------Yes 1125 1451  124
 Extended Cross Sections to 20 MeV----------------------------No  1125 1451  125
 Allow Cross Section Deletion---------------------------------No  1125 1451  126
 Allow Cross Section Reconstruction---------------------------No  1125 1451  127
 Make All Cross Sections Non-Negative-------------------------Yes 1125 1451  128
 Delete Energies Not in Ascending Order-----------------------Yes 1125 1451  129
 Deleted Duplicate Points-------------------------------------Yes 1125 1451  130
 Check for Ascending MAT/MF/MT Order--------------------------Yes 1125 1451  131
 Check for Legal MF/MT Numbers--------------------------------Yes 1125 1451  132
 Allow Creation of Missing Sections---------------------------No  1125 1451  133
 Allow Insertion of Energy Points-----------------------------No  1125 1451  134
 Create Uniform Energy Grid-----------------------------------No  1125 1451  135
 Delete Section if Cross Section =0 at All Energies-----------Yes 1125 1451  136
***************************************************************** 1125 1451  137
 ================================================================ 1125 1451  138
 *************  End of ENDF/B-VI Bibliography (n,g) ************* 1125 1451  139
 ================================================================ 1125 1451  140
 ================================================================ 1125 1451  141
  **********  Start of JENDL/D-99 (n,2n) Bibliography  *********  1125 1451  142
 ================================================================ 1125 1451  143
 11-NA- 23 TOH        EVAL-AUG96 S.IWASAKI                        1125 1451  144
                      DIST-JUL98                                  1125 1451  145
----JENDL/D-99        MATERIAL 1125                               1125 1451  146
-----INCIDENT NEUTRON DATA                                        1125 1451  147
------ENDF-6 FORMAT                                               1125 1451  148
HISTORY                                                           1125 1451  149
96-08  (N,2N) CROSS SECTIONS WERE EVALUATED BY S. IWASAKI (TOH).  1125 1451  150
                                                                  1125 1451  151
            ===== POINT-WISE DATA FILE =====                      1125 1451  152
                                                                  1125 1451  153
 <DOSIMETRY CROSS SECTION>                                        1125 1451  154
      NA-23 (N,2N) NA-22 (HALF-LIFE = 2.6019Y)                    1125 1451  155
                                                                  1125 1451  156
MF=1  GENERAL INFORMATION                                         1125 1451  157
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          1125 1451  158
                                                                  1125 1451  159
MF=3  NEUTRON CROSS SECTIONS                                      1125 1451  160
 MT=16  (N,2N) CROSS SECTION                                      1125 1451  161
     EVALUATED USING SPLINE FITTING METHOD /6/TO A SET OF         1125 1451  162
     SELECTED EXPERIMENTAL DATA /9-14/ TAKEN FROM NESTOR-2/8/.    1125 1451  163
     MAINLY BASED ON THE EXPERIMENTAL DATA OF ADAMSKI/6/.         1125 1451  164
                                                                  1125 1451  165
MF=33  COVARIANCES OF NEUTRON CROSS SECTIONS                      1125 1451  166
 MT=16                                                            1125 1451  167
    GENERATED USING SPLINE FITTING METHOD /6/                     1125 1451  168
                                                                  1125 1451  169
REFERENCES                                                        1125 1451  170
 6) S. IWASAKI, NUCLEAR DATA FOR SCINECE AND TECHNOLOGY,          1125 1451  171
    GATLINBURG,TENNESSEE, MAY 9 13, 1994. PROCEEDINGS, VOL 2, 614,1125 1451  172
    ANS, INC., (1994).                                            1125 1451  173
 8) T. NAKAGAWA : THE JAERI NUCLEAR DATA CENTER, UNPUBLISHED.     1125 1451  174
 9) H.O. MENLOVE, ET AL. PHYS. REV. 163,1308 (1967).              1125 1451  175
10) L. ADAMSKI, ET AL. ANN. NUCL. ENERGY, 7, (7), 397, (1980).    1125 1451  176
11) Y. IKEDA, ET AL., JAERI-1312 (1988).                          1125 1451  177
12) LU HAN-LIN , ET AL. INDC(CRP)-16 (1989).                      1125 1451  178
13) B.STROHMAIER, ET AL. ANN. NUCL. ENERG., 20,8 , 533-545 (1991).1125 1451  179
14) M. SAKUMA, S. IWASAKI, H. SHIMADA, N. ODANO, K. SUDA,         1125 1451  180
    J.R. DUMAIS,AND K. SUGIYAMA, JAERI-M 92-027, P. 278 (1992).   1125 1451  181
 ================================================================ 1125 1451  182
 ******* Processing history of JENDL/D99 (n,2n) component ******* 1125 1451  183
 ================================================================ 1125 1451  184
 ***************** Program LINEAR (VERSION 2002-1) ***************1125 1451  185
 For All Data Greater than 1.0000E-10 barns in Absolute Value     1125 1451  186
 Data Linearized to Within an Accuracy of .100000000 per-cent     1125 1451  187
 ***************** Program SIGMA1 (VERSION 2002-1) ***************1125 1451  188
 Data Doppler Broadened to 300.000000 Kelvin                      1125 1451  189
 for All Data Greater than 1.0000E-10 barns in Absolute Value     1125 1451  190
 Data Linearized to Within an Accuracy pf .100000000 per-cent     1125 1451  191
 ***************** Program FIXUP (Version 2002-1) ****************1125 1451  192
 Corrected ZA/AWR in All Sections-----------------------------Yes 1125 1451  193
 Corrected Thresholds-----------------------------------------Yes 1125 1451  194
 Extended Cross Sections to 20 MeV----------------------------No  1125 1451  195
 Allow Cross Section Deletion---------------------------------No  1125 1451  196
 Allow Cross Section Reconstruction---------------------------No  1125 1451  197
 Make All Cross Sections Non-Negative-------------------------Yes 1125 1451  198
 Delete Energies Not in Ascending Order-----------------------Yes 1125 1451  199
 Deleted Duplicate Points-------------------------------------Yes 1125 1451  200
 Check for Ascending MAT/MF/MT Order--------------------------Yes 1125 1451  201
 Check for Legal MF/MT Numbers--------------------------------Yes 1125 1451  202
 Allow Creation of Missing Sections---------------------------No  1125 1451  203
 Allow Insertion of Energy Points-----------------------------No  1125 1451  204
 Create Uniform Energy Grid-----------------------------------No  1125 1451  205
 Delete Section if Cross Section =0 at All Energies-----------Yes 1125 1451  206
 ================================================================ 1125 1451  207
 ***********   End of JENDL/D-99 (n,2n) Bibliography  *********** 1125 1451  208
 ================================================================ 1125 1451  209
                                                                  1125 1451  210
                                                                  1125 1451  211
                                                                  1125 1451  212
                                                                  1125 1451  213
***************************************************************** 1125 1451  214
 ************************ C O N T E N T S *********************** 1125 1451  215
 ***************** Program GROUPIE (VERSION 2002-1) **************1125 1451  216
 Unshielded Group Averages Using  640 Groups                      1125 1451  217
 Weighting Spectrum: Flat (Constant) Spectrum                     1125 1451  218
                                1        451        224          21125 1451  219
                                2        151          4          01125 1451  220
                                3         16         27          11125 1451  221
                                3        102        217          21125 1451  222
                               33         16         32          11125 1451  223
                               33        102          5          01125 1451  224
                                                                  1125 1  099999
                                                                  1125 0  0    0
 1.10230E+4 2.27922E+1          0          0          1          01125 2151    1
 1.10230E+4 1.00000E+0          0          0          1          01125 2151    2
 6.00000E+2 5.00000E+5          0          0          0          01125 2151    3
 1.50000E+0 5.41000E-1          0          0          0          01125 2151    4
                                                                  1125 2  099999
                                                                  1125 0  0    0
 1.10230E+4 2.27923E+1          0          0          0          01125 3 16    1
-1.24184E+7-1.24184E+7          0          0          1         721125 3 16    2
         72          1                                            1125 3 16    3
 12900000.0 .000146800 13000000.0 .001190000 13100000.0 .0019700001125 3 16    4
 13200000.0 .002750000 13300000.0 .003530000 13400000.0 .0043100001125 3 16    5
 13500000.0 .005940000 13600000.0 .008420000 13700000.0 .0109000001125 3 16    6
 13800000.0 .013380000 13900000.0 .015860000 14000000.0 .0187000001125 3 16    7
 14100000.0 .021900000 14200000.0 .025100000 14300000.0 .0283000001125 3 16    8
 14400000.0 .031500000 14500000.0 .034400000 14600000.0 .0370000001125 3 16    9
 14700000.0 .039600000 14800000.0 .042200000 14900000.0 .0448000001125 3 16   10
 15000000.0 .047060000 15100000.0 .048980000 15200000.0 .0509000001125 3 16   11
 15300000.0 .052820000 15400000.0 .054740000 15500000.0 .0565000001125 3 16   12
 15600000.0 .058100000 15700000.0 .059700000 15800000.0 .0613000001125 3 16   13
 15900000.0 .062900000 16000000.0 .064470000 16100000.0 .0660100001125 3 16   14
 16200000.0 .067550000 16300000.0 .069090000 16400000.0 .0706300001125 3 16   15
 16500000.0 .072250000 16600000.0 .073950000 16700000.0 .0756500001125 3 16   16
 16800000.0 .077350000 16900000.0 .079050000 17000000.0 .0807799901125 3 16   17
 17100000.0 .082539970 17200000.0 .084299950 17300000.0 .0860599301125 3 16   18
 17400000.0 .087819910 17500000.0 .089519910 17600000.0 .0911599301125 3 16   19
 17700000.0 .092799950 17800000.0 .094439970 17900000.0 .0960799901125 3 16   20
 18000000.0 .097550000 18100000.0 .098850000 18200000.0 .1001500001125 3 16   21
 18300000.0 .101450000 18400000.0 .102750000 18500000.0 .1038000001125 3 16   22
 18600000.0 .104600000 18700000.0 .105400000 18800000.0 .1062000001125 3 16   23
 18900000.0 .107000000 19000000.0 .107550000 19100000.0 .1078500001125 3 16   24
 19200000.0 .108150000 19300000.0 .108450000 19400000.0 .1087500001125 3 16   25
 19500000.0 .109010000 19600000.0 .109230000 19700000.0 .1094500001125 3 16   26
 19800000.0 .109670000 19900000.0 .109890000 20000000.0 0.0       1125 3 16   27
                                                                  1125 3  099999
 1.10230E+4 2.27922E+1          0          0          0          01125 3102    1
 6.95944E+6 6.95944E+6          0          0          1        6411125 3102    2
        641          1                                            1125 3102    3
 .000100000 8.30164087 .000105000 8.10805815 .000110000 7.924152501125 3102    4
 .000115000 7.75468967 .000120000 7.55659008 .000127500 7.336806781125 3102    5
 .000135000 7.13599486 .000142500 6.95145136 .000150000 6.751723291125 3102    6
 .000160000 6.54365768 .000170000 6.35434403 .000180000 6.180565381125 3102    7
 .000190000 6.01887822 .000200000 5.87126599 .000210000 5.732385051125 3102    8
 .000220000 5.60338070 .000230000 5.48352961 .000240000 5.342854671125 3102    9
 .000255000 5.18826207 .000270000 5.06896675 .000280000 4.936165701125 3102   10
 .000300000 4.77421396 .000320000 4.62757432 .000340000 4.493275061125 3102   11
 .000360000 4.36957608 .000380000 4.25665906 .000400000 4.138934231125 3102   12
 .000425000 4.01846711 .000450000 3.90841334 .000475000 3.807498011125 3102   13
 .000500000 3.71258783 .000525000 3.62585567 .000550000 3.543924191125 3102   14
 .000575000 3.46772455 .000600000 3.38962227 .000630000 3.309273501125 3102   15
 .000660000 3.23575512 .000690000 3.16523166 .000720000 3.090195551125 3102   16
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                                                                  112533  099999
 1.10230E+4 2.27922E+1          0          0          0          1112533102    1
 0.000000+0 0.000000+0          0        102          0          1112533102    2
 0.000000+0 0.000000+0          0          1         12          6112533102    3
 1.000000-5 4.000000-4 5.000000+1 2.500000-3 6.000000+2 1.000000-2112533102    4
 5.000000+5 4.000000-2 5.000000+6 6.250000-2 2.000000+7 0.000000+0112533102    5
                                                                  112533  099999
                                                                  1125 0  0    0
                                                                     0 0  0    0
 1.20240E+4 2.37790E+1          0          0         34         101225 1451    1
 0.0        0.0                 0          0          0          61225 1451    2
 1.00000E+0 2.10000E+7          0          0         10       20021225 1451    3
 3.00000E+2 0.0                 1          0         40          41225 1451    4
 12-Mg- 24 IRK-VIENNA EVAL-APR90                                  1225 1451    5
                      DIST-Feb2004                                1225 1451    6
----IRDF-2002         MATERIAL 1225                               1225 1451    7
-----INCIDENT NEUTRON DATA                                        1225 1451    8
------ENDF-6 FORMAT                                               1225 1451    9
 *****************************************************************1225 1451   10
 12-MG- 24 IRK-VIENNA EVAL-APR90                                  1225 1451   11
                      DIST-JUN90                                  1225 1451   12
    IRK-EVAL.NLIB 25  1225                                        1225 1451   13
 *****************************************************************1225 1451   14
  The Q values and threshold energies were updated prior to pro-  1225 1451   15
  cessing through the codes to comply with the values obtained    1225 1451   16
  using the NNDC calculation program which is based on the 1995   1225 1451   17
  Update to the Atomic mass Evaluation.                           1225 1451   18
*****************************************************************11225 1451   19
 ***************** Program LINEAR (VERSION 2002-1) ***************1225 1451   20
 For All Data Greater than 1.0000E-10 barns in Absolute Value     1225 1451   21
 Data Linearized to Within an Accuracy of .100000000 per-cent     1225 1451   22
 ***************** Program SIGMA1 (VERSION 2002-1) ***************1225 1451   23
 Data Doppler Broadened to 300.000000 Kelvin                      1225 1451   24
 for All Data Greater than 1.0000E-10 barns in Absolute Value     1225 1451   25
 Data Linearized to Within an Accuracy pf .100000000 per-cent     1225 1451   26
 ***************** Program FIXUP (Version 2002-1) ****************1225 1451   27
 Corrected ZA/AWR in All Sections-----------------------------Yes 1225 1451   28
 Corrected Thresholds-----------------------------------------Yes 1225 1451   29
 Extended Cross Sections to 20 MeV----------------------------No  1225 1451   30
 Allow Cross Section Deletion---------------------------------No  1225 1451   31
 Allow Cross Section Reconstruction---------------------------No  1225 1451   32
 Make All Cross Sections Non-Negative-------------------------Yes 1225 1451   33
 Delete Energies Not in Ascending Order-----------------------Yes 1225 1451   34
 Deleted Duplicate Points-------------------------------------Yes 1225 1451   35
 Check for Ascending MAT/MF/MT Order--------------------------Yes 1225 1451   36
 Check for Legal MF/MT Numbers--------------------------------Yes 1225 1451   37
 Allow Creation of Missing Sections---------------------------No  1225 1451   38
 Allow Insertion of Energy Points-----------------------------No  1225 1451   39
 Create Uniform Energy Grid-----------------------------------No  1225 1451   40
 Delete Section if Cross Section =0 at All Energies-----------Yes 1225 1451   41
 ***************** Program GROUPIE (VERSION 2002-1) **************1225 1451   42
 Unshielded Group Averages Using  640 Groups                      1225 1451   43
 Weighting Spectrum: Flat (Constant) Spectrum                     1225 1451   44
                                1        451         48          11225 1451   45
                                2        151          4          11225 1451   46
                                3        103         54          11225 1451   47
                               33        103        191          11225 1451   48
                                                                  1225 1  099999
                                                                  1225 0  0    0
 1.20240E+4 2.37790E+1          0          0          1          01225 2151    1
 1.20240E+4 1.00000E+0          0          0          1          01225 2151    2
 1.00000E+0 2.00000E+7          0          0          0          01225 2151    3
 2.50000E+0 3.15000E-1          0          0          0          01225 2151    4
                                                                  1225 2  099999
                                                                  1225 0  0    0
 1.20240E+4 2.37790E+1          0          0          0          01225 3103    1
-4.73343E+6-4.73343E+6          0          0          1        1521225 3103    2
        152          1                                            1225 3103    3
 4900000.00 1.93283E-5 5000000.00 3.23719E-5 5100000.00 3.45514E-51225 3103    4
 5200000.00 3.67308E-5 5300000.00 3.89103E-5 5400000.00 6.00000E-51225 3103    5
 5500000.00 .000100000 5600000.00 .000140000 5700000.00 .0002770001225 3103    6
 5800000.00 .000996000 5900000.00 .001812000 6000000.00 .0028100001225 3103    7
 6100000.00 .003990000 6200000.00 .005570000 6300000.00 .0075500001225 3103    8
 6400000.00 .016340000 6500000.00 .031940000 6600000.00 .0408375001225 3103    9
 6700000.00 .043032500 6800000.00 .042140000 6900000.00 .0381600001225 3103   10
 7000000.00 .040623659 7100000.00 .049530976 7200000.00 .0528273841225 3103   11
 7300000.00 .049316098 7400000.00 .053993284 7500000.00 .0706220001225 3103   12
 7600000.00 .082643470 7700000.00 .087805600 7800000.00 .0932863651225 3103   13
 7900000.00 .102252203 8000000.00 .112065763 8100000.00 .1207659151225 3103   14
 8200000.00 .121246102 8300000.00 .120063051 8400000.00 .1193610961225 3103   15
 8500000.00 .121545714 8600000.00 .124211429 8700000.00 .1268771431225 3103   16
 8800000.00 .128100000 8900000.00 .127880000 9000000.00 .1276600001225 3103   17
 9100000.00 .127440000 9200000.00 .127341500 9300000.00 .1279720001225 3103   18
 9400000.00 .128724000 9500000.00 .129476000 9600000.00 .1302280001225 3103   19
 9700000.00 .131544250 9800000.00 .136246000 9900000.00 .1415120001225 3103   20
 10000000.0 .146778000 10100000.0 .152044000 10200000.0 .1567137501225 3103   21
 10300000.0 .157806000 10400000.0 .158302000 10500000.0 .1587980001225 3103   22
 10600000.0 .159294000 10700000.0 .159863149 10800000.0 .1608711881225 3103   23
 10900000.0 .161952376 11000000.0 .163033564 11100000.0 .1641147521225 3103   24
 11200000.0 .165790158 11300000.0 .171852500 11400000.0 .1788025001225 3103   25
 11500000.0 .185752500 11600000.0 .191120432 11700000.0 .1848084061225 3103   26
 11800000.0 .176133043 11900000.0 .167457681 12000000.0 .1671883331225 3103   27
 12100000.0 .175325000 12200000.0 .183461667 12300000.0 .1922175001225 3103   28
 12400000.0 .201592500 12500000.0 .204542500 12600000.0 .2010675001225 3103   29
 12700000.0 .199315000 12800000.0 .199285000 12900000.0 .1972900001225 3103   30
 13000000.0 .193330000 13100000.0 .195717500 13200000.0 .2044525001225 3103   31
 13300000.0 .209240000 13400000.0 .210080000 13500000.0 .2089375001225 3103   32
 13600000.0 .205812500 13700000.0 .200547500 13800000.0 .1931425001225 3103   33
 13900000.0 .191160000 14000000.0 .194600000 14100000.0 .1964175001225 3103   34
 14200000.0 .196612500 14300000.0 .195085000 14400000.0 .1918350001225 3103   35
 14500000.0 .187510000 14600000.0 .182110000 14700000.0 .1771375001225 3103   36
 14800000.0 .172592500 14900000.0 .170535714 15000000.0 .1709671431225 3103   37
 15100000.0 .171398571 15200000.0 .171377821 15300000.0 .1686440001225 3103   38
 15400000.0 .165458000 15500000.0 .162272000 15600000.0 .1590860001225 3103   39
 15700000.0 .156102250 15800000.0 .154332000 15900000.0 .1527640001225 3103   40
 16000000.0 .151196000 16100000.0 .149628000 16200000.0 .1478917501225 3103   41
 16300000.0 .145146000 16400000.0 .142232000 16500000.0 .1393180001225 3103   42
 16600000.0 .136404000 16700000.0 .133591417 16800000.0 .1313873331225 3103   43
 16900000.0 .129284667 17000000.0 .127182000 17100000.0 .1250793331225 3103   44
 17200000.0 .122976667 17300000.0 .120874000 17400000.0 .1187713331225 3103   45
 17500000.0 .117321500 17600000.0 .116524500 17700000.0 .1157275001225 3103   46
 17800000.0 .114930500 17900000.0 .114133500 18000000.0 .1133365001225 3103   47
 18100000.0 .112539500 18200000.0 .111742500 18300000.0 .1109455001225 3103   48
 18400000.0 .110148500 18500000.0 .109096000 18600000.0 .1077880001225 3103   49
 18700000.0 .106480000 18800000.0 .105172000 18900000.0 .1038640001225 3103   50
 19000000.0 .102556000 19100000.0 .101248000 19200000.0 .0999400001225 3103   51
 19300000.0 .098632000 19400000.0 .097324000 19500000.0 .0957966671225 3103   52
 19600000.0 .094050000 19700000.0 .092303333 19800000.0 .0905566671225 3103   53
 19900000.0 .088810000 20000000.0 0.0                             1225 3103   54
                                                                  1225 3  099999
                                                                  1225 0  0    0
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 0.000000+0 0.000000+0          0        103          0          1122533103    2
 0.000000+0 0.000000+0          1          5       1128         47122533103    3
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 6.300000+6 6.500000+6 6.700000+6 6.900000+6 7.100000+6 7.310000+6122533103    5
 7.510000+6 7.710000+6 8.010000+6 8.300000+6 8.600000+6 9.000000+6122533103    6
 9.500000+6 1.000000+7 1.050000+7 1.100000+7 1.151000+7 1.180000+7122533103    7
 1.220000+7 1.240000+7 1.260000+7 1.280000+7 1.300000+7 1.320000+7122533103    8
 1.340000+7 1.360000+7 1.380000+7 1.400000+7 1.420000+7 1.440000+7122533103    9
 1.460000+7 1.480000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7122533103   10
 1.700000+7 1.800000+7 1.900000+7 2.000000+7 2.100000+7 0.000000+0122533103   11
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 0.000000+0 0.000000+0 0.000000+0 1.066000-1 3.220000-2 6.133000-2122533103   19
 6.012000-3 6.717000-3 8.477000-3 4.984000-3 1.658000-3 8.689000-3122533103   20
 4.479000-3 7.315000-3 5.031000-3 6.263000-3 4.552000-3 3.861000-3122533103   21
 4.224000-3 5.310000-3 4.534000-3 1.182000-3 9.344000-4 1.397000-3122533103   22
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 3.939000-2 3.652000-2 1.008000-2 5.253000-3 4.352000-3 3.842000-3122533103   27
 2.780000-3 5.661000-3 2.720000-3 4.687000-3 3.072000-3 3.722000-3122533103   28
 2.440000-3 2.017000-3 2.290000-3 3.012000-3 2.602000-3 1.982000-3122533103   29
 1.567000-3 2.342000-3 2.033000-3 0.000000+0 0.000000+0 5.088000-4122533103   30
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 9.664000-5 0.000000+0122533103   31
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 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0122533103   33
 0.000000+0 0.000000+0 9.281000-2 1.082000-2 7.552000-3 7.813000-3122533103   34
 5.562000-3 2.984000-3 8.913000-3 4.445000-3 7.445000-3 5.006000-3122533103   35
 6.155000-3 4.273000-3 3.585000-3 3.985000-3 5.110000-3 4.386000-3122533103   36
 2.127000-3 1.681000-3 2.513000-3 2.182000-3 0.000000+0 0.000000+0122533103   37
 5.460000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.037000-4122533103   38
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0122533103   39
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 0.000000+0 0.000000+0 0.000000+0 2.176000-2 3.668000-3 2.980000-3122533103   41
 3.042000-3 3.099000-3 3.499000-3 1.545000-3 2.901000-3 1.982000-3122533103   42
 2.307000-3 1.262000-3 4.879000-4 5.908000-4 8.342000-4 7.329000-4122533103   43
 1.083000-3 8.565000-4 1.280000-3 1.112000-3 0.000000+0 0.000000+0122533103   44
 2.782000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0 5.283000-5122533103   45
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 9.929000-4 1.612000-3 7.577000-4 1.344000-3 9.182000-4 1.098000-3122533103   49
 6.815000-4 4.190000-4 4.750000-4 6.239000-4 5.387000-4 4.016000-4122533103   50
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 8.973000-4 1.399000-3 9.860001-4 1.387000-3 7.806000-4 5.545000-4122533103   56
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 1.901000-3 8.209000-4 1.285000-3 6.400000-4 1.073000-3 7.400000-4122533103   62
 9.659000-4 5.425000-4 3.413000-4 3.507000-4 4.601000-4 3.971000-4122533103   63
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 7.842000-4 5.345000-4 6.224000-4 3.405000-4 1.346000-4 1.630000-4122533103   69
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 6.293000-4 2.604000-4 2.874000-4 3.654000-4 3.129000-4 1.215000-4122533103  104
 9.602000-5 1.436000-4 1.246000-4 0.000000+0 0.000000+0 3.119000-5122533103  105
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 3.262000-4 2.618000-4 3.538000-4 2.978000-4 1.194000-4 3.910000-5122533103  110
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 1.204000-4 9.316000-5 6.087000-5 1.426000-4 0.000000+0 2.386000-5122533103  116
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 4.197000-4 1.628000-4 5.331000-5 1.080000-4 7.306000-5 4.773000-5122533103  125
 1.118000-4 0.000000+0 2.130000-5 2.749000-5 0.000000+0 3.518000-6122533103  126
 0.000000+0 0.000000+0 4.066000-6 0.000000+0 0.000000+0 0.000000+0122533103  127
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0122533103  128
 1.398000-3 7.188000-4 9.864999-4 8.085000-4 3.534000-4 1.197000-4122533103  129
 2.088000-4 1.586000-4 1.078000-4 2.427000-4 0.000000+0 4.136000-5122533103  130
 5.967000-5 0.000000+0 7.962000-6 0.000000+0 0.000000+0 8.824000-6122533103  131
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0122533103  132
 0.000000+0 0.000000+0 0.000000+0 8.888000-4 7.738000-4 6.493000-4122533103  133
 2.855000-4 9.347000-5 1.678000-4 1.281000-4 8.368000-5 1.961000-4122533103  134
 0.000000+0 3.323000-5 4.820000-5 0.000000+0 6.168000-6 0.000000+0122533103  135
 0.000000+0 7.128000-6 0.000000+0 0.000000+0 0.000000+0 0.000000+0122533103  136
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.631000-3122533103  137
 8.744000-4 3.691000-4 1.256000-4 2.256000-4 1.656000-4 1.132000-4122533103  138
 2.535000-4 0.000000+0 4.462000-5 6.231000-5 0.000000+0 8.360000-6122533103  139
 0.000000+0 0.000000+0 9.215000-6 0.000000+0 0.000000+0 0.000000+0122533103  140
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0122533103  141
 1.131000-3 3.060000-4 1.002000-4 1.896000-4 1.373000-4 8.970000-5122533103  142
 2.102000-4 0.000000+0 3.747000-5 5.167000-5 0.000000+0 6.611000-6122533103  143
 0.000000+0 0.000000+0 7.640000-6 0.000000+0 0.000000+0 0.000000+0122533103  144
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0122533103  145
 7.059000-4 9.051000-5 1.168000-4 1.025000-4 8.654000-5 1.850000-4122533103  146
 4.997000-5 3.263000-5 3.437000-5 4.754000-6 7.243000-6 4.016000-6122533103  147
 6.730000-7 9.572000-6 1.904000-5 3.476000-5 5.464000-5 3.826000-5122533103  148
 3.348000-5 3.995000-5 9.178000-5 3.089000-5 0.000000+0 2.849000-4122533103  149
 1.090000-4 1.013000-4 1.121000-4 1.346000-4 6.140000-5 4.787000-5122533103  150
 4.006000-5 8.346000-6 2.419000-6 1.289000-6 2.179000-7 3.102000-6122533103  151
 6.121000-6 1.116000-5 1.756000-5 1.228000-5 1.075000-5 1.284000-5122533103  152
 2.950000-5 1.000000-5 0.000000+0 3.994000-4 1.073000-4 1.165000-4122533103  153
 1.538000-4 6.293000-5 6.038000-5 4.136000-5 1.129000-5 3.033000-6122533103  154
 4.522000-6 3.690000-6 6.919000-6 8.987000-6 1.587000-5 2.106000-5122533103  155
 1.747000-5 4.102000-5 3.878000-5 1.003000-4 1.366000-4 7.423000-4122533103  156
 3.689000-4 1.499000-4 1.471000-4 1.234000-4 6.027000-5 7.013000-5122533103  157
 7.715000-6 7.101000-6 6.377000-7 6.900000-6 8.037000-6 9.057000-6122533103  158
 7.065000-5 9.992000-5 7.427000-5 6.883000-5 5.504000-5 1.462000-4122533103  159
 2.198000-4 0.000000+0 3.917000-4 1.415000-4 1.163000-4 6.212000-5122533103  160
 6.163000-5 9.348000-6 5.029000-6 1.392000-6 4.268000-6 6.262000-6122533103  161
 6.583000-6 4.990000-5 6.943000-5 5.552000-5 4.795000-5 3.995000-5122533103  162
 1.171000-4 1.481000-4 0.000000+0 6.314000-4 7.655000-5 6.174000-5122533103  163
 5.043000-5 1.095000-5 6.171000-6 2.942000-6 8.958000-7 7.855000-6122533103  164
 2.145000-5 4.271000-5 5.936000-5 4.065000-5 4.325000-5 3.943000-5122533103  165
 5.687000-5 0.000000+0 0.000000+0 4.217000-4 5.631000-5 6.805000-5122533103  166
 9.824000-6 6.191000-6 4.993000-6 1.063000-5 1.087000-5 2.519000-5122533103  167
 8.153000-5 1.136000-4 9.074000-5 7.833000-5 6.488000-5 1.916000-4122533103  168
 2.484000-4 0.000000+0 1.364000-4 2.742000-5 5.675000-6 4.078000-6122533103  169
 2.047000-6 3.265000-6 6.286000-6 7.306000-6 3.756000-5 3.566000-5122533103  170
 3.666000-5 3.988000-5 3.708000-5 6.163000-5 8.552000-5 1.954000-4122533103  171
 2.193000-4 4.042000-5 3.101000-5 3.731000-5 4.210000-5 2.190000-5122533103  172
 6.633000-6 2.502000-5 3.546000-5 2.793000-5 2.402000-5 1.868000-5122533103  173
 5.986000-5 9.835000-5 0.000000+0 2.990000-5 1.234000-5 1.606000-5122533103  174
 1.677000-5 8.438000-6 2.638000-6 2.727000-6 4.223000-6 3.176000-6122533103  175
 5.216000-6 5.098000-6 1.078000-5 1.432000-5 7.229000-5 2.146000-5122533103  176
 1.217000-5 1.304000-5 7.310000-6 1.286000-6 1.058000-5 1.034000-5122533103  177
 1.053000-5 9.525000-6 8.492000-6 1.116000-5 1.378000-5 0.000000+0122533103  178
 2.728000-5 1.661000-5 8.260000-6 1.834000-6 1.729000-6 2.294000-6122533103  179
 1.904000-6 3.962000-6 4.040000-6 9.790000-6 1.247000-5 6.928000-5122533103  180
 3.051000-5 8.964000-6 1.622000-6 5.904000-6 8.294000-6 5.994000-6122533103  181
 8.828000-6 7.746000-6 2.092000-5 3.809000-5 9.510000-5 3.034000-5122533103  182
 1.586000-5 1.302000-5 1.255000-5 1.343000-5 1.401000-5 1.257000-5122533103  183
 2.020000-5 2.765000-5 6.808000-5 1.409000-4 1.474000-5 2.281000-5122533103  184
 1.493000-5 1.676000-5 1.412000-5 2.123000-5 1.232000-5 2.577000-5122533103  185
 4.629000-4 1.240000-4 1.180000-4 1.074000-4 9.052000-5 1.470000-4122533103  186
 1.828000-4 0.000000+0 4.242000-4 1.303000-4 1.194000-4 9.884000-5122533103  187
 2.045000-4 2.627000-4 0.000000+0 4.462000-4 1.101000-4 9.018000-5122533103  188
 1.636000-4 2.041000-4 0.000000+0 3.819000-4 1.030000-4 1.966000-4122533103  189
 2.921000-4 6.338000-4 3.281000-4 1.682000-4 2.465000-4 5.976000-4122533103  190
 1.025000-3 7.385000-4 1.611000-3 2.111000-3 3.391000-3 2.720000-2122533103  191
                                                                  122533  099999
                                                                  1225 0  0    0
                                                                     0 0  0    0
 1.30270E+4 2.67497E+1          0          0         34         101325 1451    1
 0.0        0.0                 0          0          0          61325 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20021325 1451    3
 3.00000E+2 0.0                 1          0        325          61325 1451    4
 13-Al- 27 FEI/IRK    EVAL-APR90 K.I.Zolotarev, M.Wagner et al.   1325 1451    5
                      DIST-Feb2004                                1325 1451    6
----IRDF-2002         MATERIAL 1325                               1325 1451    7
-----INCIDENT NEUTRON DATA                                        1325 1451    8
------ENDF-6 FORMAT                                               1325 1451    9
 *****************************************************************1325 1451   10
 13-AL- 27 FEI        EVAL-May03 K.I.Zolotarev                    1325 1451   11
                      DIST-Sep03                                  1325 1451   12
----BROND-3           MATERIAL 1325                               1325 1451   13
-----INCIDENT NEUTRON DATA                                        1325 1451   14
------ENDF-6 FORMAT                                               1325 1451   15
***************************************************************** 1325 1451   16
------Russian Reactor Dosimetry File RRDF-2002                    1325 1451   17
***************************************************************** 1325 1451   18
Authors of evaluation: K.Zolotarev, A.Pashchenko, J.Csikai        1325 1451   19
***************************************************************** 1325 1451   20
MF=3                                                              1325 1451   21
MT=103 - (n,p) cross section                                      1325 1451   22
 *****************************************************************1325 1451   23
 13-AL- 27 IRK-VIENNA EVAL-APR90                                  1325 1451   24
                      DIST-JUN90                                  1325 1451   25
    IRK-EVAL.NLIB 25  1325                                        1325 1451   26
MF=3                                                              1325 1451   27
MT=107 - (n,a) cross section                                      1325 1451   28
******************************************************************1325 1451   29
***************************************************************** 1325 1451   30
 **********   Start of (N,P) bibliographical component ********** 1325 1451   31
***************************************************************** 1325 1451   32
------Russian Reactor Dosimetry File RRDF-2002                    1325 1451   33
***************************************************************** 1325 1451   34
Authors of evaluation: K.Zolotarev, A.Pashchenko, J.Csikai        1325 1451   35
***************************************************************** 1325 1451   36
MF=3                                                              1325 1451   37
MT=103 - (n,p) cross section                                      1325 1451   38
-------------------------------------                             1325 1451   39
    Microscopic experimental data  [1-76]  were  analyzed in  the 1325 1451   40
process of preparation  of input data base  for the evaluation of 1325 1451   41
cross sections  and  their uncertainty  for the  Al-27(n,p)Mg-27  1325 1451   42
reaction.  During this procedure all experimental data  if it was 1325 1451   43
possible were corrected to the new recommended cross section data 1325 1451   44
for monitor reactions used in the measurements and to the new re- 1325 1451   45
commended decay data from ref. [77].                              1325 1451   46
    Excitation function for the  Al-27(n,p)Mg-27 reaction in the  1325 1451   47
energy region from threshold to 23.0 MeV was evaluated by  means  1325 1451   48
of statistical analysis of experimental cross section data [1-58].1325 1451   49
    Special correction was done with experimental data [3], [8],  1325 1451   50
[12], [13], [15], [17], [27], [28], [47] and [58].                1325 1451   51
    Experimental data of Hudson and Morgan [3], Gabbard et al.[8],1325 1451   52
Ferguson and Albergotti [15] , Cuzzocrea et al. [17] , Csikai and 1325 1451   53
Chimoe et al. [47]  were renormalized  to the results  of precise 1325 1451   54
absolute measurements of Ikeda et al.[53] in the overlapping ener-1325 1451   55
gy ranges. Correction factors for the experimental data [3], [8], 1325 1451   56
[15], [17]  were Fc=0.87555, Fc=1.41467, Fc=1.60840, Fc=0.89474,  1325 1451   57
respectively.  Data  of independent  measurements  of Csikai  and 1325 1451   58
Chimoe et al. [47] were multiplied to the coefficients Fc=0.89370 1325 1451   59
and Fc=0.92320, respectively.                                     1325 1451   60
    Cross sections for the  Al-27(n,p)Mg-27 reaction  measured by 1325 1451   61
Bass et al. [12] in the neutron energy range 6.00 - 9.00 MeV with 1325 1451   62
25 keV step were recalculated by averaging original  experimental 1325 1451   63
data over 100 keV energy intervals.                               1325 1451   64
    Experimental data of Calvi et al. [13] and Shimizu et al.[58] 1325 1451   65
were corrected  to the results  of Smith and Meadows measurements 1325 1451   66
with Li-7(p,n)Be-7 neutron source [27]  in the overlapping energy 1325 1451   67
intervals. Correction factors were Fc=0.96506 and Fc=1.47768, res-1325 1451   68
pectively. For the experimental data [58]  value Fc=1.47768 is a  1325 1451   69
total correction factor.  On the first step of correction data of 1325 1451   70
Shimizu et al. [58]  were renormalized to the new evaluated cross 1325 1451   71
sections for the monitor reaction In-115(n,n')In-115m [78].       1325 1451   72
    Data of  Smith and Meadows [27] measured  with using neutrons 1325 1451   73
from  D(d,n)He3 reaction were renormalized to the results of this 1325 1451   74
experiment obtained with  Li7(p,n)Be7 neutron source in the over- 1325 1451   75
lapping interval 5.398 - 5.870 MeV.  D(d,n)He3 data in the energy 1325 1451   76
range 5.398 - 9.897 MeV were increased to the factor Fc=1.083 .   1325 1451   77
    Data given in ref. [28] by Mostafa  were renormalized  to the 1325 1451   78
absolute cross section value for Al-27(n,p)Mg-27  reaction evalu- 1325 1451   79
ated at 7.1 MeV with taking into account  experimental data [12], 1325 1451   80
[14] and [27].                                                    1325 1451   81
    Experimental data [5], [8], [12] and [44] were used partially.1325 1451   82
Data of Mani et al. [5]  were taken into account  only  for the 9 1325 1451   83
neutron energies: 11.92, 13.82, 14.75, 16.20, 16.63, 17.83, 18.13,1325 1451   84
20.15 and 21.72 MeV. Renormalized experimental data of Gabbard et 1325 1451   85
al. [8] were used  only  for the 8 neutron energies: 12.90, 13.10,1325 1451   86
13.70, 14.40, 14.90, 15.45, 16.80 and 17.40 MeV.  Information ob- 1325 1451   87
tained from Bass et al. experiment [12] was taken into account in 1325 1451   88
the evaluation in the energy region 6.0 - 8.6 MeV.  In the energy 1325 1451   89
interval 8.6 - 9.0 MeV  this experiment gives significantly over- 1325 1451   90
estimated cross sections in a comparison with corrected experimen-1325 1451   91
tal data [24], [27] and new experimental data [55]. Cross section 1325 1451   92
measured by Bradley et al. [44] for the neutron energy 11 MeV was 1325 1451   93
not input in the data base for evaluation  due to a very big dis- 1325 1451   94
crepancy with new experimental data of Csikai et al. [55].        1325 1451   95
    Experimental cross section data [59-76] were rejected  due to 1325 1451   96
their discrepancy with the main bulk of experimental data [1-58]. 1325 1451   97
    In the rejected experiments [59-70] and [75-76] cross section 1325 1451   98
values were measured  only  in a one energy point in the interval 1325 1451   99
14 - 15 MeV.                                                      1325 1451  100
    Statistical analysis of input cross section data  was carried 1325 1451  101
out by means of PADE-2 code [79].  Rational function  was used as 1325 1451  102
the model function [80].                                          1325 1451  103
    Evaluated excitation function  for the reaction Al27(n,p)Mg27 1325 1451  104
was  tested with  using integral experimental  data  [81-83]  for 1325 1451  105
U-235 thermal fission neutron spectrum and evaluated integral ex- 1325 1451  106
perimental data [83] for Cf-252 spontaneous fission neutron spec- 1325 1451  107
trum.  Calculated  and  measured average cross section values for 1325 1451  108
U-235 thermal fission neutron spectrum [84]  and  Cf-252  sponta- 1325 1451  109
neous fission neutron spectrum [85] are given in the table 1.     1325 1451  110
                                                      Table 1     1325 1451  111
  1325 1451  112
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  1325 1451  113
  1325 1451  114
 U-235 neutron fission     4.0768         4.133 +- 0.074  [81]  1325 1451  115
                                          3.914 +- 0.070  [82]  1325 1451  116
                                          3.902 +- 0.069  [83]  1325 1451  117
  1325 1451  118
 CF-252 spont. fission     4.9070         4.880 +- 0.104  [83]  1325 1451  119
  1325 1451  120
                                                                  1325 1451  121
MF=33                                                             1325 1451  122
MT=103 - (n,p) cross section cov. matrix                          1325 1451  123
----------------------------------------                          1325 1451  124
    Uncertainties in the evaluated  excitation function  for  the 1325 1451  125
reaction Al-27(n,p)Mg-27 are given in the form of relative covari-1325 1451  126
ance matrix for the  49-neutron energy groups (LB=5).  Covariance 1325 1451  127
matrix  of  uncertainties  was  calculated  simultaneously  with  1325 1451  128
recommended cross section data by means of PADE-2 code [79].      1325 1451  129
    Eigenvalues  of the  6-th digits  relative covariance matrix  1325 1451  130
given in the 33-file are the following:                           1325 1451  131
                                                                  1325 1451  132
    9.62022E-08    9.94230E-08    1.04190E-07    1.09967E-07      1325 1451  133
    1.15699E-07    1.20174E-07    1.24951E-07    1.30570E-07      1325 1451  134
    1.37068E-07    1.43716E-07    1.50173E-07    1.58001E-07      1325 1451  135
    1.68205E-07    1.76372E-07    1.86739E-07    1.94590E-07      1325 1451  136
    2.06816E-07    2.14527E-07    2.29525E-07    2.40453E-07      1325 1451  137
    2.53581E-07    2.82127E-07    2.99422E-07    3.49389E-07      1325 1451  138
    3.68505E-07    4.35939E-07    5.42544E-07    7.20462E-07      1325 1451  139
    9.45090E-07    2.44284E-06    1.77944E-05    8.88268E-05      1325 1451  140
    1.54306E-04    2.21515E-04    2.92421E-04    3.30954E-04      1325 1451  141
    3.45302E-04    3.84750E-04    4.56266E-04    6.07458E-04      1325 1451  142
    1.31442E-03    1.53210E-03    1.76053E-03    2.87076E-03      1325 1451  143
    4.69639E-03    5.64972E-03    1.04479E-02    1.48842E-02      1325 1451  144
    5.19587E-02                                                   1325 1451  145
                                                                  1325 1451  146
References :                                                      1325 1451  147
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40. A.Chiadli et al.  Proc. of International Conference Nuclear   1325 1451  202
    Data for Science and Technology, 6 - 10 September 1982,       1325 1451  203
    Antwerp, Holland, D.Reidel Publishing Company, p.404, 1983    1325 1451  204
41. J.Janczyszyn  Proc. of Int. Conference Nuclear Data for       1325 1451  205
    Science and Technology, 6 - 10 September 1982, Antwerp,       1325 1451  206
    Holland, D.Reidel Publishing Company, p.869, 1983             1325 1451  207
42. H.A.Husain, S.E.Hunt  International J. of Applied Radiation   1325 1451  208
    and Isotopes, v.34, no.4, p.731, 1983                         1325 1451  209
43. V.T.Shchebolev et al.  Atomnaya Energiya, v.54, no.6, p.417,  1325 1451  210
    June 1983                                                     1325 1451  211
44. D.A.Bradley et al.  Proc. of Int. Symp. on Fast Neutrons in   1325 1451  212
    Science and Technology, Chiang Mai, 4-8 February 1985, p.19   1325 1451  213
45. W.Enz et al.  Annalen der Physik, v.42, no.3, p.283, 1985     1325 1451  214
46. I.Garlea et al.  Rev. Roum. Phys., v.30, no.8, p.673, 1985    1325 1451  215
47. J.Csikai, T.Chimoye et al.   Zeitschrift fuer Physik, Sec.A,  1325 1451  216
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48. J.W.Meadows et al.  Ann. Nucl. Energ., v.14, p.489, Sep. 1987 1325 1451  218
49. Y.Ikeda,C.Konno,K.Oishi et al. Report JAERI-1312, March 1988  1325 1451  219
50. K.Kudo et.al.  Proc. of International Conference Nuclear Data 1325 1451  220
    for Science and Technology, Mito, Japan, 30 May - 3 June 1988,1325 1451  221
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51. I.Kimura, K.Kobayashi  Nucl. Sci. Eng., v.106, p.332, 1990 ;  1325 1451  223
    K.Kobayashi, I.Kimura  Proc. of the Intern. Conf. on Nuclear  1325 1451  224
    Data for Science and Technology, 30 May - 3 June 1988, Mito,  1325 1451  225
    Japan, Saikon Publishing Co., LTD, pp.261-265, 1989 ;         1325 1451  226
    K.Kobayashi, I.Kimura Progress Report NEANDC(J)-116, Sep.1985 1325 1451  227
52. A.Ercan et al.  Proc. of an Intern. Conf. on Nuclear Data for 1325 1451  228
    Science and Technology, 13-17 May 1991, Julich, FRG, Springer-1325 1451  229
    Verlag, 1992                                                  1325 1451  230
53. Y.Ikeda et al.  Journal of Nuclear Science and Technology,    1325 1451  231
    v.30, n.9, pp.870-880, September 1993                         1325 1451  232
54. Zhou Hongyu et al.  Proc. of Int. Conf. on Nuclear Data for   1325 1451  233
    Science and Technology, Gatlinburg, Tennessee, USA, May 9-13, 1325 1451  234
    1994, Vol.1, pp. 166-169                                      1325 1451  235
55. J.Csikai et al. Private communication, Debrecen, April 1998   1325 1451  236
56. A.A.Filatenkov et al. Report RI-252, St.Petersburg, May 1999; 1325 1451  237
    A.A.Filatenkov et al. VANT, Ser.:Yadernye Konstanty, v.2, p.8,1325 1451  238
    Moscow, 1996                                                  1325 1451  239
57. A.Fessler, A.J.M.Plompen et al. Nucl. Sci. Eng., v.134, no.2, 1325 1451  240
    pp.171-200, February 2000                                     1325 1451  241
58. T.Shimizu, S.Furuichi, H.Sakane, M.Shibata, K.Kawade          1325 1451  242
    Proc. of The 2000 Symposium on Nuclear Data, November 16-17,  1325 1451  243
    2000 JAERI, Tokai, Japan, pp.194-199                          1325 1451  244
59. E.B.Paul, R.L.Clarke  Canadian Journal of Physics, v.31,      1325 1451  245
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60. S.Yasumi  Journal of the Physical Society of Japan, v.12,     1325 1451  247
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61. G.Brown et al.  Philosophical Magazine, v.2, p.785, 1957      1325 1451  249
62. A.Poularikas, R.W.Fink  Phys. Rev., v.115, p.989, 1959        1325 1451  250
63. C.S.Khurana, H.S.Hans  Proc. of 4th Nuclear Physics and Solid 1325 1451  251
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64. R.S.Storey,W.Jack,A.Ward  Proc. Phys. Soc., v.75, p.526, 1960 1325 1451  253
65. M.Sakisaka et al.  Journal of the Physical Society of Japan,  1325 1451  254
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66. J.Kantele, D.G.Gardner  Nucl. Phys, v.35, p.353, 1962         1325 1451  256
67. W.Langmann  EXFOR 20903.003, September 1962                   1325 1451  257
68. F.L.Hassler, R.A.Peck jr  Phys. Rev., v.125, p.1011, 1962     1325 1451  258
69. B.Mitra, A.M.Ghose  Nucl. Phys., v.83, p.157, July 1966       1325 1451  259
70. R.Prasad, D.C.Sarkar  Nuovo Cimento, v.A3, no.3, p.467, 1971  1325 1451  260
71. J.C.Robertson, K.J.Zieba  Annals of Nucl. Energy, v.26, no.1, 1325 1451  261
    p.1, 1972                                                     1325 1451  262
72. R.A.Jarjis  J. of Physics, pt.G, v.4, n.3, p.445, 1978        1325 1451  263
73. J.Csikai  Proc. of International Conference Nuclear Data for  1325 1451  264
    Science and Technology, 6 - 10 September 1982, Antwerp,       1325 1451  265
    Holland, D.Reidel Publishing Company, p.414, 1983             1325 1451  266
74. Tahir    Indian Journal of Pure and Applied Physics, v.23,    1325 1451  267
    p.439, September 1985                                         1325 1451  268
75. J.P.Gupta et.al.  Indian J. Pramana, v.24, p.637, 1985        1325 1451  269
76. L.I.Klochkova et al.  Vopr. Atomn. Nauki i Tekhn., Serija:    1325 1451  270
    Jadernye Konstanty v.1, p.27, 1992 ;                          1325 1451  271
    L.I.Klochkova et al.  Proc. of the 1-st Int. Conf. on Neutron 1325 1451  272
    Phys., Kiev, USSR, 14 - 18 Sep.1987, v.3, p.315, Moscow 1988  1325 1451  273
77. R.B.Firestone   Table of Isotopes, Eighth edition, Vol. 1,    1325 1451  274
    John Wiley & Sons, Inc., New York, 1995                       1325 1451  275
78. K.I.Zolotarev, P.K.Zolotarev The In-115(n,n')In-115m reaction 1325 1451  276
    excitation function  in the energy range  from threshold  to  1325 1451  277
    20 MeV, Obninsk, IPPE, eval. March 2003                       1325 1451  278
79. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          1325 1451  279
80. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 1325 1451  280
    st's Meeting on Evaluation and Processing of Covariance Data, 1325 1451  281
    Oak Ridge, USA, 1992, OECD, Paris, 1993, p.105                1325 1451  282
81. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 1325 1451  283
    Washington D.C., 25-28 April 1989, v.2, p.923                 1325 1451  284
82. W.Mannhart  Prog. Report INDC(Ger)-045, pp.40-43, June 1999   1325 1451  285
83. W.Mannhart  Validation of Differential Cross Sections with    1325 1451  286
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 1325 1451  287
    September 2002                                                1325 1451  288
84. L.W.Weston et al.  Evaluated Neutron Data  for  Uranium-235,  1325 1451  289
    ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989    1325 1451  290
85. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        1325 1451  291
***************************************************************** 1325 1451  292
**********   End of (N,2N) bibliographical component   ********** 1325 1451  293
================================================================= 1325 1451  294
***************************************************************** 1325 1451  295
  The Q values and threshold energies were updated prior to pro-  1325 1451  296
  cessing through the codes to comply with the values obtained    1325 1451  297
  using the NNDC calculation program which is based on the 1995   1325 1451  298
  Update to the Atomic mass Evaluation.Additional points were     1325 1451  299
  added near threshold for MF/MT=3/107                            1325 1451  300
 File 2 added to the pointwise file containing only the effective 1325 1451  301
 scattering radius with no resonance parameters given.            1325 1451  302
 Taken from ENDF/B-VI                                             1325 1451  303
***************************************************************** 1325 1451  304
 ***************** Program LINEAR (VERSION 2002-1) ***************1325 1451  305
 For All Data Greater than 1.0000E-10 barns in Absolute Value     1325 1451  306
 Data Linearized to Within an Accuracy of .100000000 per-cent     1325 1451  307
 ***************** Program SIGMA1 (VERSION 2002-1) ***************1325 1451  308
 Data Doppler Broadened to 300.000000 Kelvin                      1325 1451  309
 for All Data Greater than 1.0000E-10 barns in Absolute Value     1325 1451  310
 Data Linearized to Within an Accuracy pf .100000000 per-cent     1325 1451  311
 ***************** Program FIXUP (Version 2002-1) ****************1325 1451  312
 Corrected ZA/AWR in All Sections-----------------------------Yes 1325 1451  313
 Corrected Thresholds-----------------------------------------Yes 1325 1451  314
 Extended Cross Sections to 20 MeV----------------------------No  1325 1451  315
 Allow Cross Section Deletion---------------------------------No  1325 1451  316
 Allow Cross Section Reconstruction---------------------------No  1325 1451  317
 Make All Cross Sections Non-Negative-------------------------Yes 1325 1451  318
 Delete Energies Not in Ascending Order-----------------------Yes 1325 1451  319
 Deleted Duplicate Points-------------------------------------Yes 1325 1451  320
 Check for Ascending MAT/MF/MT Order--------------------------Yes 1325 1451  321
 Check for Legal MF/MT Numbers--------------------------------Yes 1325 1451  322
 Allow Creation of Missing Sections---------------------------No  1325 1451  323
 Allow Insertion of Energy Points-----------------------------No  1325 1451  324
 Create Uniform Energy Grid-----------------------------------No  1325 1451  325
 Delete Section if Cross Section =0 at All Energies-----------Yes 1325 1451  326
 ***************** Program GROUPIE (VERSION 2002-1) **************1325 1451  327
 Unshielded Group Averages Using  640 Groups                      1325 1451  328
 Weighting Spectrum: Flat (Constant) Spectrum                     1325 1451  329
                                1        451        335          11325 1451  330
                                2        151          4          11325 1451  331
                                3        103         64          11325 1451  332
                                3        107         60          11325 1451  333
                               33        103        224          11325 1451  334
                               33        107        224          11325 1451  335
                                                                  1325 1  099999
                                                                  1325 0  0    0
 1.30270E+4 2.67497E+1          0          0          1          01325 2151    1
 1.302700+4 1.000000+0          0          0          1          01325 2151    2
 1.000000-5 1.000000+3          0          0          0          01325 2151    3
 2.500000+0 3.275200-1          0          0          0          01325 2151    4
                                                                  1325 2  099999
                                                                  1325 0  0    0
 1.30270E+4 2.67497E+1          0          0          0          01325 3103    1
-1.82797E+6-1.82797E+6          0          0          1        1831325 3103    2
        183          1                                            1325 3103    3
 1800000.00 7.5592E-10 1900000.00 5.94923E-7 2000000.00 1.70291E-61325 3103    4
 2100000.00 2.81090E-6 2200000.00 3.91889E-6 2300000.00 5.02688E-61325 3103    5
 2400000.00 1.36533E-5 2500000.00 5.31887E-5 2600000.00 9.60656E-51325 3103    6
 2700000.00 .000197747 2800000.00 .000422101 2900000.00 .0007430851325 3103    7
 3000000.00 .001163323 3100000.00 .001664055 3200000.00 .0021825181325 3103    8
 3300000.00 .002660038 3400000.00 .005813040 3500000.00 .0059058401325 3103    9
 3600000.00 .005923953 3700000.00 .007376778 3800000.00 .0053420301325 3103   10
 3900000.00 .006590330 4000000.00 .006400630 4100000.00 .0058240901325 3103   11
 4200000.00 .010016250 4300000.00 .011382425 4400000.00 .0120621751325 3103   12
 4500000.00 .017318350 4600000.00 .018967950 4700000.00 .0161955251325 3103   13
 4800000.00 .015435425 4900000.00 .023968600 5000000.00 .0268780501325 3103   14
 5100000.00 .028133700 5200000.00 .028140700 5300000.00 .0276018001325 3103   15
 5400000.00 .036424900 5500000.00 .041505550 5600000.00 .0478750101325 3103   16
 5700000.00 .058418765 5800000.00 .042922684 5900000.00 .0452353451325 3103   17
 6000000.00 .048209582 6100000.00 .051044500 6200000.00 .0536079001325 3103   18
 6300000.00 .055899200 6400000.00 .057914600 6500000.00 .0596261001325 3103   19
 6600000.00 .061243488 6700000.00 .062934663 6800000.00 .0646258381325 3103   20
 6900000.00 .066317013 7000000.00 .067955880 7100000.00 .0695424401325 3103   21
 7200000.00 .071129000 7300000.00 .072715560 7400000.00 .0743021201325 3103   22
 7500000.00 .075839390 7600000.00 .077327370 7700000.00 .0788153501325 3103   23
 7800000.00 .080303330 7900000.00 .081791310 8000000.00 .0832272701325 3103   24
 8100000.00 .084611210 8200000.00 .085995150 8300000.00 .0873790901325 3103   25
 8400000.00 .088763030 8500000.00 .090087063 8600000.00 .0913511881325 3103   26
 8700000.00 .092615313 8800000.00 .093879438 8900000.00 .0950713751325 3103   27
 9000000.00 .096191125 9100000.00 .097310875 9200000.00 .0984306251325 3103   28
 9300000.00 .099468917 9400000.00 .100425750 9500000.00 .1013825831325 3103   29
 9600000.00 .102253820 9700000.00 .103039461 9800000.00 .1038251011325 3103   30
 9900000.00 .104511118 10000000.0 .105097471 10100000.0 .1056838241325 3103   31
 10200000.0 .106158000 10300000.0 .106520000 10400000.0 .1068820001325 3103   32
 10500000.0 .107122667 10600000.0 .107242000 10700000.0 .1073613331325 3103   33
 10800000.0 .107354500 10900000.0 .107221500 11000000.0 .1070885001325 3103   34
 11100000.0 .106830333 11200000.0 .106447000 11300000.0 .1060636671325 3103   35
 11400000.0 .105561500 11500000.0 .104940500 11600000.0 .1043195001325 3103   36
 11700000.0 .103591167 11800000.0 .102755500 11900000.0 .1019198331325 3103   37
 12000000.0 .100992733 12100000.0 .099974200 12200000.0 .0989556671325 3103   38
 12300000.0 .097854738 12400000.0 .096671413 12500000.0 .0954880881325 3103   39
 12600000.0 .094304763 12700000.0 .093050575 12800000.0 .0917255251325 3103   40
 12900000.0 .090400475 13000000.0 .089075425 13100000.0 .0877503751325 3103   41
 13200000.0 .086425325 13300000.0 .085082972 13400000.0 .0837233171325 3103   42
 13500000.0 .082363661 13600000.0 .081004006 13700000.0 .0796443501325 3103   43
 13800000.0 .078284694 13900000.0 .076925039 14000000.0 .0755653831325 3103   44
 14100000.0 .074205728 14200000.0 .072891140 14300000.0 .0716216201325 3103   45
 14400000.0 .070352100 14500000.0 .069082580 14600000.0 .0678130601325 3103   46
 14700000.0 .066586183 14800000.0 .065401950 14900000.0 .0642177171325 3103   47
 15000000.0 .063087163 15100000.0 .062010288 15200000.0 .0609334131325 3103   48
 15300000.0 .059856538 15400000.0 .058833300 15500000.0 .0578637001325 3103   49
 15600000.0 .056894100 15700000.0 .055924500 15800000.0 .0550073001325 3103   50
 15900000.0 .054142500 16000000.0 .053277700 16100000.0 .0524129001325 3103   51
 16200000.0 .051592388 16300000.0 .050816163 16400000.0 .0500399381325 3103   52
 16500000.0 .049263713 16600000.0 .048525338 16700000.0 .0478248131325 3103   53
 16800000.0 .047124288 16900000.0 .046423763 17000000.0 .0457559751325 3103   54
 17100000.0 .045120925 17200000.0 .044485875 17300000.0 .0438508251325 3103   55
 17400000.0 .043247580 17500000.0 .042676140 17600000.0 .0421047001325 3103   56
 17700000.0 .041533260 17800000.0 .040961820 17900000.0 .0404208401325 3103   57
 18000000.0 .039910320 18100000.0 .039399800 18200000.0 .0388892801325 3103   58
 18300000.0 .038378760 18400000.0 .037894430 18500000.0 .0374362901325 3103   59
 18600000.0 .036978150 18700000.0 .036520010 18800000.0 .0360618701325 3103   60
 18900000.0 .035626400 19000000.0 .035213600 19100000.0 .0348008001325 3103   61
 19200000.0 .034388000 19300000.0 .033975200 19400000.0 .0335821401325 3103   62
 19500000.0 .033208820 19600000.0 .032835500 19700000.0 .0324621801325 3103   63
 19800000.0 .032088860 19900000.0 .031734358 20000000.0 0.0       1325 3103   64
                                                                  1325 3  099999
 1.30270E+4 2.67497E+1          0          0          0          01325 3107    1
-3.13282E+6-3.13282E+6          0          0          1        1691325 3107    2
        169          1                                            1325 3107    3
 3200000.00 1.42951E-8 3300000.00 1.14142E-7 3400000.00 2.28210E-71325 3107    4
 3500000.00 3.42279E-7 3600000.00 4.56348E-7 3700000.00 5.70416E-71325 3107    5
 3800000.00 6.84485E-7 3900000.00 7.98554E-7 4000000.00 9.12622E-71325 3107    6
 4100000.00 1.02669E-6 4200000.00 1.14076E-6 4300000.00 1.25483E-61325 3107    7
 4400000.00 1.36890E-6 4500000.00 1.48297E-6 4600000.00 2.92250E-61325 3107    8
 4700000.00 5.68750E-6 4800000.00 8.45250E-6 4900000.00 1.12175E-51325 3107    9
 5000000.00 1.79500E-5 5100000.00 2.86500E-5 5200000.00 5.45634E-51325 3107   10
 5300000.00 9.56901E-5 5400000.00 .000136817 5500000.00 .0002041551325 3107   11
 5600000.00 .000465000 5700000.00 .000765000 5800000.00 .0010585941325 3107   12
 5900000.00 .001304898 6000000.00 .001541633 6100000.00 .0021375001325 3107   13
 6200000.00 .003092500 6300000.00 .004247500 6400000.00 .0056025001325 3107   14
 6500000.00 .007080000 6600000.00 .008680000 6700000.00 .0107375001325 3107   15
 6800000.00 .013252500 6900000.00 .015816667 7000000.00 .0184300001325 3107   16
 7100000.00 .020721208 7200000.00 .022225000 7300000.00 .0237352501325 3107   17
 7400000.00 .026175000 7500000.00 .028995000 7600000.00 .0319331251325 3107   18
 7700000.00 .035160000 7800000.00 .038347250 7900000.00 .0403740001325 3107   19
 8000000.00 .041926000 8100000.00 .043858250 8200000.00 .0467200001325 3107   20
 8300000.00 .049672375 8400000.00 .053689000 8500000.00 .0581410001325 3107   21
 8600000.00 .061977625 8700000.00 .064310000 8800000.00 .0665961671325 3107   22
 8900000.00 .069370000 9000000.00 .072343333 9100000.00 .0753166671325 3107   23
 9200000.00 .078127833 9300000.00 .079966000 9400000.00 .0816420001325 3107   24
 9500000.00 .083318000 9600000.00 .084994000 9700000.00 .0865785001325 3107   25
 9800000.00 .087614000 9900000.00 .088558000 10000000.0 .0895020001325 3107   26
 10100000.0 .090446000 10200000.0 .091575500 10300000.0 .0938180001325 3107   27
 10400000.0 .096246000 10500000.0 .098674000 10600000.0 .1011020001325 3107   28
 10700000.0 .103424000 10800000.0 .105110000 10900000.0 .1066900001325 3107   29
 11000000.0 .108270000 11100000.0 .109850000 11200000.0 .1113287501325 3107   30
 11300000.0 .112200000 11400000.0 .112970000 11500000.0 .1137400001325 3107   31
 11600000.0 .114510000 11700000.0 .115324861 11800000.0 .1164088891325 3107   32
 11900000.0 .117537778 12000000.0 .118666667 12100000.0 .1197955561325 3107   33
 12200000.0 .120802500 12300000.0 .121687500 12400000.0 .1225725001325 3107   34
 12500000.0 .123457500 12600000.0 .124150000 12700000.0 .1246500001325 3107   35
 12800000.0 .125150000 12900000.0 .125095000 13000000.0 .1244850001325 3107   36
 13100000.0 .124885000 13200000.0 .126295000 13300000.0 .1266200001325 3107   37
 13400000.0 .125874500 13500000.0 .125448000 13600000.0 .1248750001325 3107   38
 13700000.0 .123840000 13800000.0 .122775000 13900000.0 .1225800001325 3107   39
 14000000.0 .122205000 14100000.0 .121510000 14200000.0 .1204250001325 3107   40
 14300000.0 .118080000 14400000.0 .116097500 14500000.0 .1147725001325 3107   41
 14600000.0 .113300000 14700000.0 .112195000 14800000.0 .1110200001325 3107   42
 14900000.0 .109686154 15000000.0 .108778462 15100000.0 .1078707691325 3107   43
 15200000.0 .106744258 15300000.0 .105082857 15400000.0 .1033971431325 3107   44
 15500000.0 .101711429 15600000.0 .100025714 15700000.0 .0983604641325 3107   45
 15800000.0 .096818000 15900000.0 .095296000 16000000.0 .0937740001325 3107   46
 16100000.0 .092252000 16200000.0 .090685050 16300000.0 .0888484001325 3107   47
 16400000.0 .086966800 16500000.0 .085085200 16600000.0 .0832036001325 3107   48
 16700000.0 .081322000 16800000.0 .079440400 16900000.0 .0775588001325 3107   49
 17000000.0 .075677200 17100000.0 .073795600 17200000.0 .0719140001325 3107   50
 17300000.0 .070032400 17400000.0 .068150800 17500000.0 .0666965001325 3107   51
 17600000.0 .065669500 17700000.0 .064642500 17800000.0 .0636155001325 3107   52
 17900000.0 .062588500 18000000.0 .061561500 18100000.0 .0605345001325 3107   53
 18200000.0 .059507500 18300000.0 .058480500 18400000.0 .0574535001325 3107   54
 18500000.0 .056250500 18600000.0 .054871500 18700000.0 .0534925001325 3107   55
 18800000.0 .052113500 18900000.0 .050734500 19000000.0 .0493555001325 3107   56
 19100000.0 .047976500 19200000.0 .046597500 19300000.0 .0452185001325 3107   57
 19400000.0 .043839500 19500000.0 .042685667 19600000.0 .0417570001325 3107   58
 19700000.0 .040828333 19800000.0 .039899667 19900000.0 .0389710001325 3107   59
 20000000.0 0.0                                                   1325 3107   60
                                                                  1325 3  099999
                                                                  1325 0  0    0
 1.30270E+4 2.67497E+1          0          0          0          1132533103    1
 0.000000+0 0.000000+0          0        103          0          1132533103    2
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 0.000000+0 0.000000+0 0.000000+0 0.000000+0 5.396000-6 0.000000+0132533107  144
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 3.609000-6 0.000000+0132533107  145
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0132533107  146
 0.000000+0 0.000000+0 0.000000+0 1.010000-3 2.992000-4 1.806000-4132533107  147
 1.660000-4 2.322000-4 2.234000-4 0.000000+0 1.330000-5 1.251000-5132533107  148
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 6.788000-6 0.000000+0132533107  149
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 4.540000-6 0.000000+0132533107  150
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0132533107  151
 0.000000+0 0.000000+0 0.000000+0 4.855000-4 8.804000-5 7.789000-5132533107  152
 1.040000-4 1.097000-4 0.000000+0 5.960000-6 6.206000-6 0.000000+0132533107  153
 4.236000-7 0.000000+0 2.443000-5 1.718000-5 4.916000-7 0.000000+0132533107  154
 0.000000+0 0.000000+0 0.000000+0 2.404000-6 3.094000-7 0.000000+0132533107  155
 0.000000+0 5.120000-6 8.284000-6 1.677000-6 3.184000-6 4.056000-6132533107  156
 3.243000-6 2.131000-5 3.453000-4 8.158000-5 9.464000-5 8.616000-5132533107  157
 1.966000-5 1.112000-5 9.740000-6 4.520000-6 1.647000-6 1.590000-6132533107  158
 8.205000-7 1.824000-6 2.192000-6 1.838000-6 1.553000-6 1.498000-6132533107  159
 1.283000-6 2.557000-6 3.685000-6 0.000000+0 0.000000+0 4.776000-6132533107  160
 3.051000-5 1.483000-5 2.590000-5 3.784000-6 2.175000-5 1.987000-5132533107  161
 4.016000-4 1.151000-4 8.509000-5 3.282000-5 1.285000-5 1.225000-5132533107  162
 4.657000-6 2.891000-6 4.045000-6 1.028000-6 3.425000-6 4.567000-6132533107  163
 2.467000-6 2.052000-6 4.826000-6 1.723000-6 4.376000-6 4.736000-6132533107  164
 3.053000-6 1.194000-5 2.117000-5 7.369000-5 6.063000-5 5.182000-5132533107  165
 6.299000-5 9.099000-5 2.157000-4 6.095000-4 1.056000-4 6.041000-5132533107  166
 1.218000-5 6.391000-6 1.927000-6 4.300000-6 2.568000-6 1.325000-6132533107  167
 5.194000-6 2.800000-6 2.969000-6 1.525000-6 2.419000-6 2.071000-6132533107  168
 5.304000-6 1.489000-6 0.000000+0 1.702000-5 2.881000-5 4.408000-5132533107  169
 3.493000-5 2.563000-5 3.387000-5 5.310000-5 0.000000+0 4.263000-4132533107  170
 2.255000-5 6.734000-6 5.986000-6 1.518000-6 2.400000-6 1.871000-6132533107  171
 1.127000-6 2.268000-6 2.141000-6 3.429000-6 7.101000-7 2.293000-6132533107  172
 1.967000-6 3.160000-6 1.464000-6 2.543000-6 1.001000-5 2.145000-5132533107  173
 2.465000-5 1.183000-5 1.123000-5 5.215000-6 4.169000-6 2.739000-5132533107  174
 3.174000-4 1.346000-5 1.222000-6 6.710000-6 2.430000-6 1.950000-6132533107  175
 4.430000-6 1.021000-6 1.095000-5 2.295000-6 2.908000-6 1.474000-6132533107  176
 6.913000-6 2.020000-6 1.116000-6 1.787000-5 2.270000-5 3.705000-5132533107  177
 2.319000-5 4.090000-5 3.174000-5 4.151000-5 6.353000-5 0.000000+0132533107  178
 3.827000-5 5.049000-6 6.893000-6 6.458000-6 3.211000-6 3.274000-6132533107  179
 5.902000-6 3.559000-6 3.617000-6 2.739000-6 5.845000-6 5.289000-6132533107  180
 4.473000-6 5.006000-6 9.880000-6 2.368000-6 3.836000-6 1.297000-5132533107  181
 4.585000-6 9.582000-6 3.990000-6 6.133000-6 0.000000+0 2.759000-5132533107  182
 8.230000-6 8.382000-6 9.287000-6 4.591000-6 7.332000-6 9.476000-6132533107  183
 9.943000-6 2.963000-6 8.863000-6 7.289000-6 5.732000-6 6.401000-6132533107  184
 5.534000-6 1.510000-6 4.281000-7 7.702000-6 4.198000-6 7.054000-6132533107  185
 3.817000-6 5.174000-6 2.427000-5 2.309000-5 9.631000-6 8.920000-6132533107  186
 5.565000-6 8.421000-6 9.652000-6 9.836000-6 3.409000-6 8.706000-6132533107  187
 7.712000-6 5.500000-6 5.951000-6 6.299000-6 1.413000-6 2.956000-7132533107  188
 5.510000-6 2.934000-7 3.544000-6 0.000000+0 0.000000+0 0.000000+0132533107  189
 2.587000-5 1.013000-5 6.187000-6 1.044000-5 1.050000-5 1.130000-5132533107  190
 3.770000-6 9.896000-6 8.530000-6 6.826000-6 6.620000-6 5.294000-6132533107  191
 2.427000-6 2.037000-6 3.105000-6 2.047000-6 1.641000-6 1.702000-6132533107  192
 2.449000-6 1.500000-6 2.720000-5 5.727000-6 9.154000-6 1.179000-5132533107  193
 1.262000-5 3.263000-6 9.523000-6 7.688000-6 6.054000-6 5.990000-6132533107  194
 6.649000-6 1.693000-6 3.636000-7 0.000000+0 3.169000-6 2.126000-6132533107  195
 2.724000-6 4.036000-6 1.842000-5 1.401000-5 7.625000-6 6.399000-6132533107  196
 6.389000-6 2.064000-6 5.589000-6 6.165000-6 3.533000-6 4.086000-6132533107  197
 4.119000-6 6.104000-6 7.990000-6 3.653000-7 9.139000-6 1.862000-7132533107  198
 7.314000-6 7.362000-6 0.000000+0 2.226000-5 9.286000-6 1.017000-5132533107  199
 3.293000-6 8.898000-6 7.520000-6 6.178000-6 5.933000-6 5.487000-6132533107  200
 1.791000-6 1.026000-6 2.690000-6 1.244000-6 9.128000-7 1.946000-6132533107  201
 2.979000-6 0.000000+0 2.972000-5 1.275000-5 3.605000-6 9.483000-6132533107  202
 8.650000-6 6.052000-6 5.999000-6 7.951000-6 1.607000-6 4.184000-7132533107  203
 6.770000-7 3.569000-6 2.563000-6 3.282000-6 4.636000-6 2.169000-5132533107  204
 3.175000-5 3.608000-6 1.028000-5 8.672000-6 6.534000-6 6.473000-6132533107  205
 7.902000-6 2.498000-6 1.207000-6 1.075000-6 7.427000-7 5.481000-7132533107  206
 0.000000+0 0.000000+0 0.000000+0 8.157000-6 3.191000-6 2.883000-6132533107  207
 2.181000-6 2.292000-6 2.408000-6 8.151000-7 5.990000-7 2.563000-6132533107  208
 6.847000-7 1.592000-6 4.822000-7 7.560000-7 0.000000+0 2.659000-5132533107  209
 8.918000-6 7.709000-6 7.517000-6 1.023000-5 1.849000-6 6.097000-7132533107  210
 8.763000-7 4.169000-6 2.837000-6 3.064000-6 4.538000-6 2.071000-5132533107  211
 2.310000-5 5.627000-6 6.838000-6 6.688000-6 1.269000-5 1.707000-5132533107  212
 7.534000-7 1.952000-5 3.840000-7 1.564000-5 1.574000-5 0.000000+0132533107  213
 1.663000-5 5.067000-6 6.248000-6 1.517000-6 1.349000-6 1.744000-6132533107  214
 2.882000-6 1.078000-5 1.169000-5 1.572000-5 1.178000-5 1.555000-5132533107  215
 5.900000-6 7.406000-6 1.009000-5 4.208000-6 1.284000-5 3.768000-6132533107  216
 1.077000-5 1.148000-5 1.088000-5 7.103000-5 4.890000-6 1.567000-6132533107  217
 2.252000-6 3.467000-6 1.148000-6 1.616000-6 1.783000-6 8.398000-6132533107  218
 1.958000-4 1.062000-4 1.967000-5 1.202000-4 2.103000-5 1.000000-4132533107  219
 1.130000-4 0.000000+0 3.040000-4 3.899000-5 1.845000-4 3.677000-5132533107  220
 1.565000-4 1.772000-4 1.813000-5 4.736000-4 3.914000-5 5.423000-5132533107  221
 5.088000-5 7.374000-5 2.934000-5 4.221000-4 7.744000-5 2.208000-4132533107  222
 2.874000-4 2.662000-4 4.119000-4 1.790000-4 2.601000-4 1.574000-4132533107  223
 5.736000-4 4.115000-4 2.375000-4 1.008000-3 3.285000-4 2.638000-3132533107  224
                                                                  132533  099999
                                                                  1325 0  0    0
                                                                     0 0  0    0
 1.50310E+4 3.07076E+1          0          0         34         101525 1451    1
 0.0        0.0                 0          0          0          61525 1451    2
 1.00000E+0 2.05000E+7          0          0         10       20021525 1451    3
 3.00000E+2 0.0                 1          0         40          41525 1451    4
 15-P - 31 IRK-VIENNA EVAL-JUN80                                  1525 1451    5
                      DIST-Feb2004                                1525 1451    6
----IRDF-2002         MATERIAL 1525                               1525 1451    7
-----INCIDENT NEUTRON DATA                                        1525 1451    8
------ENDF-6 FORMAT                                               1525 1451    9
 *****************************************************************1525 1451   10
                      DIST-JUN90                                  1525 1451   11
    IRK-EVAL.NLIB 25  1525                                        1525 1451   12
 *****************************************************************1525 1451   13
  The Q values and threshold energies were updated prior to pro-  1525 1451   14
  cessing through the codes to comply with the values obtained    1525 1451   15
  using the NNDC calculation program which is based on the 1995   1525 1451   16
  Update to the Atomic mass Evaluation.                           1525 1451   17
  Additional points were added near threshold for mf/mt= 3/103    1525 1451   18
 *****************************************************************1525 1451   19
 ***************** Program LINEAR (VERSION 2002-1) ***************1525 1451   20
 For All Data Greater than 1.0000E-10 barns in Absolute Value     1525 1451   21
 Data Linearized to Within an Accuracy of .100000000 per-cent     1525 1451   22
 ***************** Program SIGMA1 (VERSION 2002-1) ***************1525 1451   23
 Data Doppler Broadened to 300.000000 Kelvin                      1525 1451   24
 for All Data Greater than 1.0000E-10 barns in Absolute Value     1525 1451   25
 Data Linearized to Within an Accuracy pf .100000000 per-cent     1525 1451   26
 ***************** Program FIXUP (Version 2002-1) ****************1525 1451   27
 Corrected ZA/AWR in All Sections-----------------------------Yes 1525 1451   28
 Corrected Thresholds-----------------------------------------Yes 1525 1451   29
 Extended Cross Sections to 20 MeV----------------------------No  1525 1451   30
 Allow Cross Section Deletion---------------------------------No  1525 1451   31
 Allow Cross Section Reconstruction---------------------------No  1525 1451   32
 Make All Cross Sections Non-Negative-------------------------Yes 1525 1451   33
 Delete Energies Not in Ascending Order-----------------------Yes 1525 1451   34
 Deleted Duplicate Points-------------------------------------Yes 1525 1451   35
 Check for Ascending MAT/MF/MT Order--------------------------Yes 1525 1451   36
 Check for Legal MF/MT Numbers--------------------------------Yes 1525 1451   37
 Allow Creation of Missing Sections---------------------------No  1525 1451   38
 Allow Insertion of Energy Points-----------------------------No  1525 1451   39
 Create Uniform Energy Grid-----------------------------------No  1525 1451   40
 Delete Section if Cross Section =0 at All Energies-----------Yes 1525 1451   41
 ***************** Program GROUPIE (VERSION 2002-1) **************1525 1451   42
 Unshielded Group Averages Using  640 Groups                      1525 1451   43
 Weighting Spectrum: Flat (Constant) Spectrum                     1525 1451   44
                                1        451         48          11525 1451   45
                                2        151          4          11525 1451   46
                                3        103         69          11525 1451   47
                               33        103        108          11525 1451   48
                                                                  1525 1  099999
                                                                  1525 0  0    0
 1.50310E+4 3.07076E+1          0          0          1          01525 2151    1
 1.50310E+4 1.00000E+0          0          0          1          01525 2151    2
 1.00000E+0 2.00000E+7          0          0          0          01525 2151    3
 5.00000E-1 4.10000E-1          0          0          0          01525 2151    4
                                                                  1525 2  099999
                                                                  1525 0  0    0
 1.50310E+4 3.07076E+1          0          0          0          01525 3103    1
-7.09680E+5-7.09680E+5          0          0          1        1981525 3103    2
        198          1                                            1525 3103    3
 720000.000 4.99267E-7 760000.000 2.54695E-6 800000.000 4.70496E-61525 3103    4
 840000.000 6.86298E-6 880000.000 9.02099E-6 920000.000 1.43222E-51525 3103    5
 960000.000 2.27667E-5 1000000.00 3.75444E-5 1100000.00 8.10667E-51525 3103    6
 1200000.00 .000175412 1300000.00 .000440231 1400000.00 .0007334621525 3103    7
 1500000.00 .001126279 1600000.00 .003710000 1700000.00 .0064587501525 3103    8
 1800000.00 .007420000 1900000.00 .008352500 2000000.00 .0093375001525 3103    9
 2100000.00 .014567500 2200000.00 .024042500 2300000.00 .0318600001525 3103   10
 2400000.00 .038020000 2500000.00 .046500000 2600000.00 .0573000001525 3103   11
 2700000.00 .062522500 2800000.00 .062167500 2900000.00 .0614850001525 3103   12
 3000000.00 .060475000 3100000.00 .063037500 3200000.00 .0691725001525 3103   13
 3300000.00 .070750000 3400000.00 .067770000 3500000.00 .0675950001525 3103   14
 3600000.00 .070225000 3700000.00 .075490000 3800000.00 .0833900001525 3103   15
 3900000.00 .086990000 4000000.00 .086290000 4100000.00 .0890725001525 3103   16
 4200000.00 .095337500 4300000.00 .099325000 4400000.00 .1010350001525 3103   17
 4500000.00 .106707500 4600000.00 .116342500 4700000.00 .1218066671525 3103   18
 4800000.00 .123100000 4900000.00 .124393333 5000000.00 .1252008331525 3103   19
 5100000.00 .125522500 5200000.00 .125844167 5300000.00 .1261658331525 3103   20
 5400000.00 .126487500 5500000.00 .126809167 5600000.00 .1277855561525 3103   21
 5700000.00 .129416667 5800000.00 .131047778 5900000.00 .1326788891525 3103   22
 6000000.00 .134310000 6100000.00 .135941111 6200000.00 .1375722221525 3103   23
 6300000.00 .139203333 6400000.00 .140834444 6500000.00 .1411960001525 3103   24
 6600000.00 .140288000 6700000.00 .139380000 6800000.00 .1384720001525 3103   25
 6900000.00 .137564000 7000000.00 .136656000 7100000.00 .1357480001525 3103   26
 7200000.00 .134840000 7300000.00 .133932000 7400000.00 .1330240001525 3103   27
 7500000.00 .132823600 7600000.00 .133330800 7700000.00 .1338380001525 3103   28
 7800000.00 .134345200 7900000.00 .134852400 8000000.00 .1353596001525 3103   29
 8100000.00 .135866800 8200000.00 .136374000 8300000.00 .1368812001525 3103   30
 8400000.00 .137388400 8500000.00 .137895600 8600000.00 .1384028001525 3103   31
 8700000.00 .138892500 8800000.00 .139277200 8900000.00 .1396444001525 3103   32
 9000000.00 .140011600 9100000.00 .140378800 9200000.00 .1407460001525 3103   33
 9300000.00 .141113200 9400000.00 .141480400 9500000.00 .1418476001525 3103   34
 9600000.00 .142214800 9700000.00 .142582000 9800000.00 .1429492001525 3103   35
 9900000.00 .143316400 10000000.0 .143224500 10100000.0 .1426735001525 3103   36
 10200000.0 .142122500 10300000.0 .141571500 10400000.0 .1410205001525 3103   37
 10500000.0 .140469500 10600000.0 .139918500 10700000.0 .1393675001525 3103   38
 10800000.0 .138816500 10900000.0 .138265500 11000000.0 .1371955001525 3103   39
 11100000.0 .135606500 11200000.0 .134017500 11300000.0 .1324285001525 3103   40
 11400000.0 .130839500 11500000.0 .129250500 11600000.0 .1276615001525 3103   41
 11700000.0 .126072500 11800000.0 .124483500 11900000.0 .1228945001525 3103   42
 12000000.0 .121343750 12100000.0 .119831250 12200000.0 .1183187501525 3103   43
 12300000.0 .116806250 12400000.0 .115293750 12500000.0 .1137812501525 3103   44
 12600000.0 .112268750 12700000.0 .110756250 12800000.0 .1092437501525 3103   45
 12900000.0 .107731250 13000000.0 .106218750 13100000.0 .1047062501525 3103   46
 13200000.0 .103193750 13300000.0 .101681250 13400000.0 .1001687501525 3103   47
 13500000.0 .098656250 13600000.0 .097143750 13700000.0 .0956312501525 3103   48
 13800000.0 .094118750 13900000.0 .092606250 14000000.0 .0914250001525 3103   49
 14100000.0 .090575000 14200000.0 .089725000 14300000.0 .0888750001525 3103   50
 14400000.0 .088025000 14500000.0 .087175000 14600000.0 .0863250001525 3103   51
 14700000.0 .085475000 14800000.0 .084625000 14900000.0 .0837750001525 3103   52
 15000000.0 .082900500 15100000.0 .082001500 15200000.0 .0811025001525 3103   53
 15300000.0 .080203500 15400000.0 .079304500 15500000.0 .0784055001525 3103   54
 15600000.0 .077506500 15700000.0 .076607500 15800000.0 .0757085001525 3103   55
 15900000.0 .074809500 16000000.0 .073979000 16100000.0 .0732170001525 3103   56
 16200000.0 .072455000 16300000.0 .071693000 16400000.0 .0709310001525 3103   57
 16500000.0 .070169000 16600000.0 .069407000 16700000.0 .0686450001525 3103   58
 16800000.0 .067883000 16900000.0 .067121000 17000000.0 .0664115001525 3103   59
 17100000.0 .065754500 17200000.0 .065097500 17300000.0 .0644405001525 3103   60
 17400000.0 .063783500 17500000.0 .063126500 17600000.0 .0624695001525 3103   61
 17700000.0 .061812500 17800000.0 .061155500 17900000.0 .0604985001525 3103   62
 18000000.0 .059888500 18100000.0 .059325500 18200000.0 .0587625001525 3103   63
 18300000.0 .058199500 18400000.0 .057636500 18500000.0 .0570735001525 3103   64
 18600000.0 .056510500 18700000.0 .055947500 18800000.0 .0553845001525 3103   65
 18900000.0 .054821500 19000000.0 .054300000 19100000.0 .0538200001525 3103   66
 19200000.0 .053340000 19300000.0 .052860000 19400000.0 .0523800001525 3103   67
 19500000.0 .051900000 19600000.0 .051420000 19700000.0 .0509400001525 3103   68
 19800000.0 .050460000 19900000.0 .049980000 20000000.0 0.0       1525 3103   69
                                                                  1525 3  099999
                                                                  1525 0  0    0
 1.50310E+4 3.07076E+1          0          0          0          1152533103    1
 0.000000+0 0.000000+0          0        103          0          1152533103    2
 0.000000+0 0.000000+0          1          5        630         35152533103    3
 1.000000-5 7.200000+5 1.650000+6 1.800000+6 2.000000+6 2.200000+6152533103    4
 2.400000+6 2.600000+6 2.800000+6 3.000000+6 3.200000+6 3.400000+6152533103    5
 3.600000+6 3.800000+6 4.000000+6 4.200000+6 4.400000+6 4.600000+6152533103    6
 4.800000+6 5.200000+6 6.000000+6 7.000000+6 8.000000+6 9.500000+6152533103    7
 1.050000+7 1.150000+7 1.250000+7 1.350000+7 1.450000+7 1.550000+7152533103    8
 1.650000+7 1.750000+7 1.850000+7 1.950000+7 2.000000+7 0.000000+0152533103    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   13
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   14
 0.000000+0 0.000000+0 0.000000+0 3.607000-2 7.514000-3 8.546000-3152533103   15
 2.217000-2 5.044000-3 3.058000-3 0.000000+0 2.796000-3 0.000000+0152533103   16
 0.000000+0 2.393000-3 0.000000+0 0.000000+0 3.590000-3 0.000000+0152533103   17
 2.134000-3 0.000000+0 4.263000-3 3.713000-3 5.669000-3 5.545000-3152533103   18
 4.290000-3 4.277000-3 0.000000+0 0.000000+0 0.000000+0 1.946000-3152533103   19
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   20
 1.779000-2 1.151000-3 1.034000-2 3.241000-3 1.931000-3 1.425000-3152533103   21
 0.000000+0 2.246000-3 3.361000-3 1.655000-3 0.000000+0 1.815000-3152533103   22
 0.000000+0 2.383000-3 0.000000+0 0.000000+0 2.841000-3 2.969000-3152533103   23
 4.145000-3 4.006000-3 3.253000-3 2.777000-3 0.000000+0 0.000000+0152533103   24
 0.000000+0 1.190000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   25
 0.000000+0 0.000000+0 9.411000-3 1.093000-2 1.932000-3 2.345000-3152533103   26
 1.101000-3 2.315000-3 1.256000-3 2.303000-3 3.088000-3 2.223000-3152533103   27
 0.000000+0 1.553000-3 0.000000+0 9.231000-4 0.000000+0 1.844000-3152533103   28
 1.606000-3 2.452000-3 2.399000-3 1.856000-3 1.850000-3 0.000000+0152533103   29
 0.000000+0 0.000000+0 8.419000-4 0.000000+0 0.000000+0 0.000000+0152533103   30
 0.000000+0 0.000000+0 0.000000+0 4.199000-2 3.769000-3 5.643000-3152533103   31
 2.401000-3 4.436000-3 2.989000-3 5.133000-3 6.142000-3 2.746000-3152533103   32
 1.214000-3 3.859000-3 1.593000-3 2.294000-3 0.000000+0 6.482000-3152533103   33
 5.977000-3 8.864000-3 8.639000-3 6.786000-3 6.454000-3 0.000000+0152533103   34
 0.000000+0 0.000000+0 2.888000-3 0.000000+0 0.000000+0 0.000000+0152533103   35
 0.000000+0 0.000000+0 0.000000+0 6.128000-3 5.158000-4 6.021000-4152533103   36
 6.501000-4 7.921000-4 1.123000-3 9.830000-4 1.077000-3 0.000000+0152533103   37
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   38
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   39
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   40
 0.000000+0 0.000000+0 2.624000-3 7.177000-4 1.025000-3 1.021000-3152533103   41
 1.549000-3 1.617000-3 8.940000-4 3.405000-4 7.031000-4 4.469000-4152533103   42
 4.179000-4 0.000000+0 1.368000-3 1.284000-3 1.887000-3 1.837000-3152533103   43
 1.450000-3 1.358000-3 0.000000+0 0.000000+0 0.000000+0 6.044000-4152533103   44
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   45
 1.916000-3 5.914000-4 9.829000-4 1.584000-3 1.194000-3 1.051000-3152533103   46
 2.676000-4 2.477000-5 3.510000-4 1.203000-5 2.012000-5 4.213000-4152533103   47
 4.111000-4 5.738000-4 5.546000-4 4.503000-4 3.844000-4 0.000000+0152533103   48
 0.000000+0 0.000000+0 1.648000-4 0.000000+0 0.000000+0 0.000000+0152533103   49
 0.000000+0 0.000000+0 0.000000+0 3.823000-3 7.588000-4 1.130000-3152533103   50
 1.405000-3 1.053000-3 2.474000-5 6.807000-4 3.218000-5 4.005000-4152533103   51
 3.068000-5 8.060000-4 6.650000-4 1.015000-3 9.930000-4 7.682000-4152533103   52
 7.658000-4 0.000000+0 0.000000+0 0.000000+0 3.485000-4 0.000000+0152533103   53
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.146000-2152533103   54
 1.983000-3 1.462000-3 1.529000-3 7.614000-4 5.570000-5 9.714000-4152533103   55
 3.322000-4 4.292000-4 9.439000-4 9.748000-4 9.042000-4 8.740000-4152533103   56
 7.096000-4 6.058000-4 0.000000+0 0.000000+0 0.000000+0 2.596000-4152533103   57
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   58
 8.227000-3 2.589000-3 2.177000-3 6.663000-4 1.124000-4 8.736000-4152533103   59
 5.464000-5 9.134000-5 1.054000-3 9.694000-4 1.353000-3 1.308000-3152533103   60
 1.062000-3 9.065000-4 0.000000+0 0.000000+0 0.000000+0 3.885000-4152533103   61
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   62
 5.736000-3 1.907000-3 3.481000-4 6.364000-4 4.562000-4 3.689000-4152533103   63
 6.992000-5 1.207000-3 1.046000-3 1.535000-3 1.494000-3 1.180000-3152533103   64
 1.102000-3 0.000000+0 0.000000+0 0.000000+0 4.896000-4 0.000000+0152533103   65
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 5.580000-3152533103   66
 2.494000-4 3.084000-5 3.080000-4 2.276000-4 2.926000-4 2.168000-4152533103   67
 2.279000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   68
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   69
 0.000000+0 0.000000+0 0.000000+0 2.285000-3 6.715000-5 7.301000-4152533103   70
 2.234000-4 2.946000-4 7.401000-4 7.281000-4 7.308000-4 7.064000-4152533103   71
 5.735000-4 4.896000-4 0.000000+0 0.000000+0 0.000000+0 2.099000-4152533103   72
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   73
 3.230000-3 8.735000-5 5.405000-4 8.327000-5 1.096000-3 8.539000-4152533103   74
 1.304000-3 1.275000-3 9.864999-4 9.834000-4 0.000000+0 0.000000+0152533103   75
 0.000000+0 4.475000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   76
 0.000000+0 0.000000+0 3.690000-3 2.769000-4 3.660000-4 9.568000-4152533103   77
 9.384000-4 9.591000-4 9.271000-4 7.527000-4 6.426000-4 0.000000+0152533103   78
 0.000000+0 0.000000+0 2.754000-4 0.000000+0 0.000000+0 0.000000+0152533103   79
 0.000000+0 0.000000+0 0.000000+0 1.786000-3 2.632000-4 7.904000-4152533103   80
 6.972000-4 7.748000-4 7.579000-4 5.864000-4 5.845000-4 0.000000+0152533103   81
 0.000000+0 0.000000+0 2.660000-4 0.000000+0 0.000000+0 0.000000+0152533103   82
 0.000000+0 0.000000+0 0.000000+0 2.754000-3 2.846000-4 2.387000-4152533103   83
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   84
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   85
 0.000000+0 0.000000+0 5.841000-3 1.996000-3 2.692000-3 2.620000-3152533103   86
 2.069000-3 1.934000-3 0.000000+0 0.000000+0 0.000000+0 8.599000-4152533103   87
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   88
 3.286000-3 2.544000-3 2.474000-3 1.958000-3 1.818000-3 0.000000+0152533103   89
 0.000000+0 0.000000+0 8.061000-4 0.000000+0 0.000000+0 0.000000+0152533103   90
 0.000000+0 0.000000+0 0.000000+0 4.903000-3 3.626000-3 2.867000-3152533103   91
 2.670000-3 0.000000+0 0.000000+0 0.000000+0 1.186000-3 0.000000+0152533103   92
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 4.647000-3152533103   93
 2.789000-3 2.599000-3 0.000000+0 0.000000+0 0.000000+0 1.154000-3152533103   94
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0152533103   95
 3.739000-3 3.378000-3 4.381000-3 4.071000-3 3.459000-3 1.514000-3152533103   96
 1.984000-4-1.096000-3-2.519000-3-3.665000-3-4.531000-3-5.258000-3152533103   97
 3.602000-3 5.156000-3 4.879000-3 4.114000-3 1.819000-3 2.486000-4152533103   98
-1.353000-3-3.211000-3-4.813000-3-6.048000-3-7.052000-3 8.150000-3152533103   99
 7.875000-3 6.715000-3 3.008000-3 4.616000-4-2.013000-3-4.899000-3152533103  100
-7.395000-3-9.318000-3-1.087000-2 7.667000-3 6.600000-3 3.022000-3152533103  101
 5.465000-4-1.729000-3-4.440000-3-6.795000-3-8.611000-3-1.007000-2152533103  102
 5.775000-3 2.746000-3 6.217000-4-1.125000-3-3.301000-3-5.194000-3152533103  103
-6.656000-3-7.841000-3 1.439000-3 4.791000-4-7.138000-5-9.163000-4152533103  104
-1.679000-3-2.276000-3-2.766000-3 3.212000-4 5.254000-4 5.616000-4152533103  105
 5.582000-4 5.450000-4 5.245000-4 1.899000-3 3.081000-3 4.045000-3152533103  106
 4.771000-3 5.329000-3 5.515000-3 7.581000-3 9.161000-3 1.039000-2152533103  107
 1.064000-2 1.300000-2 1.484000-2 1.597000-2 1.828000-2 2.098000-2152533103  108
                                                                  152533  099999
                                                                  1525 0  0    0
                                                                     0 0  0    0
 1.60320E+4 3.16974E+1          0          0         34         101625 1451    1
 0.0        0.0                 0          0          0          61625 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20021625 1451    3
 3.00000E+2 0.0                 1          0         45          41625 1451    4
 16-S - 32                                                        1625 1451    5
                      DIST-Feb2004                                1625 1451    6
----IRDF-2002         MATERIAL 1625                               1625 1451    7
-----INCIDENT NEUTRON DATA                                        1625 1451    8
------ENDF-6 FORMAT                                               1625 1451    9
******************************************************************1625 1451   10
US EVALUATION 1989    DIST-FEB91                                  1625 1451   11
    ENDF/B-VI         MATERIAL 1625                               1625 1451   12
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1625 1451   13
DOSIMETRY                                                         1625 1451   14
******************************************************************1625 1451   15
 The Q values and threshold energies were updated prior to pro-   1625 1451   16
 cessing through the codes to comply with the values obtained     1625 1451   17
 using the NNDC calculation program which is based on the 1995    1625 1451   18
 Update to the Atomic mass Evaluation.                            1625 1451   19
                                                                  1625 1451   20
 File 2 added to the pointwise file containing only the effective 1625 1451   21
 scattering radius with no resonance parameters given.            1625 1451   22
 Taken from ENDF/B-VI                                             1625 1451   23
******************************************************************1625 1451   24
 ***************** Program LINEAR (VERSION 2002-1) ***************1625 1451   25
 For All Data Greater than 1.0000E-10 barns in Absolute Value     1625 1451   26
 Data Linearized to Within an Accuracy of .100000000 per-cent     1625 1451   27
 ***************** Program SIGMA1 (VERSION 2002-1) ***************1625 1451   28
 Data Doppler Broadened to 300.000000 Kelvin                      1625 1451   29
 for All Data Greater than 1.0000E-10 barns in Absolute Value     1625 1451   30
 Data Linearized to Within an Accuracy pf .100000000 per-cent     1625 1451   31
 ***************** Program FIXUP (Version 2002-1) ****************1625 1451   32
 Corrected ZA/AWR in All Sections-----------------------------Yes 1625 1451   33
 Corrected Thresholds-----------------------------------------Yes 1625 1451   34
 Extended Cross Sections to 20 MeV----------------------------No  1625 1451   35
 Allow Cross Section Deletion---------------------------------No  1625 1451   36
 Allow Cross Section Reconstruction---------------------------No  1625 1451   37
 Make All Cross Sections Non-Negative-------------------------Yes 1625 1451   38
 Delete Energies Not in Ascending Order-----------------------Yes 1625 1451   39
 Deleted Duplicate Points-------------------------------------Yes 1625 1451   40
 Check for Ascending MAT/MF/MT Order--------------------------Yes 1625 1451   41
 Check for Legal MF/MT Numbers--------------------------------Yes 1625 1451   42
 Allow Creation of Missing Sections---------------------------No  1625 1451   43
 Allow Insertion of Energy Points-----------------------------No  1625 1451   44
 Create Uniform Energy Grid-----------------------------------No  1625 1451   45
 Delete Section if Cross Section =0 at All Energies-----------Yes 1625 1451   46
 ***************** Program GROUPIE (VERSION 2002-1) **************1625 1451   47
 Unshielded Group Averages Using  640 Groups                      1625 1451   48
 Weighting Spectrum: Flat (Constant) Spectrum                     1625 1451   49
                                1        451         53          11625 1451   50
                                2        151          4          11625 1451   51
                                3        103         68          11625 1451   52
                               33        103        183          11625 1451   53
                                                                  1625 1  099999
                                                                  1625 0  0    0
 1.60320E+4 3.16974E+1          0          0          1          01625 2151    1
 1.603200+4 1.000000+0          0          0          1          01625 2151    2
 1.000000-5 2.000000+7          0          0          0          01625 2151    3
 0.000000+0 3.100000-1          0          0          0          01625 2151    4
                                                                  1625 2  099999
                                                                  1625 0  0    0
 1.60320E+4 3.16974E+1          0          0          0          01625 3103    1
 0.0       -9.28310E+5          0          0          1        1931625 3103    2
        193          1                                            1625 3103    3
 920000.000 2.17952E-8 960000.000 6.76274E-6 1000000.00 1.89000E-51625 3103    4
 1100000.00 3.75000E-5 1200000.00 8.10000E-5 1300000.00 .0001710001625 3103    5
 1400000.00 .000350000 1500000.00 .000688000 1600000.00 .0014590001625 3103    6
 1700000.00 .002604000 1800000.00 .006027000 1900000.00 .0090950001625 3103    7
 2000000.00 .013095000 2100000.00 .031680400 2200000.00 .0543095001625 3103    8
 2300000.00 .068355500 2400000.00 .071605250 2500000.00 .0723635001625 3103    9
 2600000.00 .066761000 2700000.00 .079601500 2800000.00 .0940746001625 3103   10
 2900000.00 .112995500 3000000.00 .160350000 3100000.00 .1612500001625 3103   11
 3200000.00 .147160000 3300000.00 .203350000 3400000.00 .2110525001625 3103   12
 3500000.00 .227087500 3600000.00 .226475000 3700000.00 .1787000001625 3103   13
 3800000.00 .178425000 3900000.00 .251806667 4000000.00 .3165733331625 3103   14
 4100000.00 .340450000 4200000.00 .349000000 4300000.00 .3469636361625 3103   15
 4400000.00 .296862864 4500000.00 .278430000 4600000.00 .2780800001625 3103   16
 4700000.00 .272954286 4800000.00 .257940851 4900000.00 .2369763641625 3103   17
 5000000.00 .220432500 5100000.00 .213717500 5200000.00 .2020425001625 3103   18
 5300000.00 .185407500 5400000.00 .200845000 5500000.00 .2483550001625 3103   19
 5600000.00 .278015000 5700000.00 .289825000 5800000.00 .2966925001625 3103   20
 5900000.00 .298617500 6000000.00 .300240000 6100000.00 .3015600001625 3103   21
 6200000.00 .302880000 6300000.00 .304200000 6400000.00 .3055200001625 3103   22
 6500000.00 .307460000 6600000.00 .310020000 6700000.00 .3125800001625 3103   23
 6800000.00 .315140000 6900000.00 .317700000 7000000.00 .3208110001625 3103   24
 7100000.00 .324473000 7200000.00 .328135000 7300000.00 .3317970001625 3103   25
 7400000.00 .335459000 7500000.00 .334650000 7600000.00 .3293700001625 3103   26
 7700000.00 .324090000 7800000.00 .318810000 7900000.00 .3135300001625 3103   27
 8000000.00 .312126000 8100000.00 .314598000 8200000.00 .3170700001625 3103   28
 8300000.00 .319542000 8400000.00 .322014000 8500000.00 .3238300001625 3103   29
 8600000.00 .324990000 8700000.00 .326150000 8800000.00 .3273100001625 3103   30
 8900000.00 .328470000 9000000.00 .330531000 9100000.00 .3334930001625 3103   31
 9200000.00 .336455000 9300000.00 .339417000 9400000.00 .3423790001625 3103   32
 9500000.00 .345761000 9600000.00 .349563000 9700000.00 .3533650001625 3103   33
 9800000.00 .357167000 9900000.00 .360969000 10000000.0 .3643230001625 3103   34
 10100000.0 .367229000 10200000.0 .370135000 10300000.0 .3730410001625 3103   35
 10400000.0 .375947000 10500000.0 .378436000 10600000.0 .3805080001625 3103   36
 10700000.0 .382580000 10800000.0 .384652000 10900000.0 .3867240001625 3103   37
 11000000.0 .387142000 11100000.0 .385906000 11200000.0 .3846700001625 3103   38
 11300000.0 .383434000 11400000.0 .382198000 11500000.0 .3822350001625 3103   39
 11600000.0 .383545000 11700000.0 .384855000 11800000.0 .3861650001625 3103   40
 11900000.0 .387475000 12000000.0 .384360000 12100000.0 .3768200001625 3103   41
 12200000.0 .369280000 12300000.0 .361740000 12400000.0 .3542000001625 3103   42
 12500000.0 .347640000 12600000.0 .342060000 12700000.0 .3364800001625 3103   43
 12800000.0 .330900000 12900000.0 .325320000 13000000.0 .3194190001625 3103   44
 13100000.0 .313197000 13200000.0 .306975000 13300000.0 .3007530001625 3103   45
 13400000.0 .294531000 13500000.0 .287643000 13600000.0 .2800890001625 3103   46
 13700000.0 .272535000 13800000.0 .264981000 13900000.0 .2574270001625 3103   47
 14000000.0 .250686000 14100000.0 .244758000 14200000.0 .2388300001625 3103   48
 14300000.0 .232902000 14400000.0 .226974000 14500000.0 .2226780001625 3103   49
 14600000.0 .220014000 14700000.0 .217350000 14800000.0 .2146860001625 3103   50
 14900000.0 .212022000 15000000.0 .208361500 15100000.0 .2037045001625 3103   51
 15200000.0 .199047500 15300000.0 .194390500 15400000.0 .1897335001625 3103   52
 15500000.0 .185076500 15600000.0 .180419500 15700000.0 .1757625001625 3103   53
 15800000.0 .171105500 15900000.0 .166448500 16000000.0 .1622415001625 3103   54
 16100000.0 .158484500 16200000.0 .154727500 16300000.0 .1509705001625 3103   55
 16400000.0 .147213500 16500000.0 .143456500 16600000.0 .1396995001625 3103   56
 16700000.0 .135942500 16800000.0 .132185500 16900000.0 .1284285001625 3103   57
 17000000.0 .125255000 17100000.0 .122665000 17200000.0 .1200750001625 3103   58
 17300000.0 .117485000 17400000.0 .114895000 17500000.0 .1123050001625 3103   59
 17600000.0 .109715000 17700000.0 .107125000 17800000.0 .1045350001625 3103   60
 17900000.0 .101945000 18000000.0 .099952300 18100000.0 .0985569001625 3103   61
 18200000.0 .097161500 18300000.0 .095766100 18400000.0 .0943707001625 3103   62
 18500000.0 .092975300 18600000.0 .091579900 18700000.0 .0901845001625 3103   63
 18800000.0 .088789100 18900000.0 .087393700 19000000.0 .0861977001625 3103   64
 19100000.0 .085201100 19200000.0 .084204500 19300000.0 .0832079001625 3103   65
 19400000.0 .082211300 19500000.0 .081214700 19600000.0 .0802181001625 3103   66
 19700000.0 .079221500 19800000.0 .078224900 19900000.0 .0772283001625 3103   67
 20000000.0 0.0                                                   1625 3103   68
                                                                  1625 3  099999
                                                                  1625 0  0    0
 1.60320E+4 3.16974E+1          0          0          0          1162533103    1
 0.0000E+00 0.0000E+00          0        103          0          6162533103    2
 0.0000E+00 0.0000E+00         77          4        308        154162533103    3
 1.0000E-05 0.0000E+00 9.5700E+05-6.0000E-01 1.5800E+06-1.0000E+00162533103    4
 1.6300E+06-1.0000E+00 1.6800E+06-1.0000E+00 1.7800E+06-1.0000E+00162533103    5
 1.8300E+06-1.0000E+00 1.8800E+06-1.0000E+00 1.9200E+06-1.0000E+00162533103    6
 1.9600E+06-1.0000E+00 2.0000E+06-1.0000E+00 2.0400E+06-1.0000E+00162533103    7
 2.0800E+06-1.0000E+00 2.1200E+06-1.0000E+00 2.1600E+06-1.0000E+00162533103    8
 2.2000E+06-1.0000E+00 2.2500E+06-1.0000E+00 2.3000E+06-1.0000E+00162533103    9
 2.3500E+06-1.0000E+00 2.4000E+06-1.0000E+00 2.4500E+06-1.0000E+00162533103   10
 2.5000E+06-1.0000E+00 2.5500E+06-1.0000E+00 2.6000E+06-1.0000E+00162533103   11
 2.6500E+06-1.0000E+00 2.7000E+06-1.0000E+00 2.7500E+06-1.0000E+00162533103   12
 2.8000E+06-1.0000E+00 2.8400E+06-1.0000E+00 2.9000E+06-1.0000E+00162533103   13
 2.9500E+06-1.0000E+00 3.0000E+06-1.0000E+00 3.0500E+06-1.0000E+00162533103   14
 3.1000E+06-1.0000E+00 3.1500E+06-1.0000E+00 3.2000E+06-1.0000E+00162533103   15
 3.2400E+06-1.0000E+00 3.2800E+06-1.0000E+00 3.3300E+06-1.0000E+00162533103   16
 3.3700E+06-1.0000E+00 3.4000E+06-1.0000E+00 3.4400E+06-1.0000E+00162533103   17
 3.4700E+06-1.0000E+00 3.5100E+06-1.0000E+00 3.5500E+06-1.0000E+00162533103   18
 3.6000E+06-1.0000E+00 3.6500E+06-1.0000E+00 3.7000E+06-1.0000E+00162533103   19
 3.7500E+06-1.0000E+00 3.8000E+06-1.0000E+00 3.8500E+06-1.0000E+00162533103   20
 3.9000E+06-1.0000E+00 3.9400E+06-1.0000E+00 3.9800E+06-1.0000E+00162533103   21
 4.0400E+06-1.0000E+00 4.1000E+06-1.0000E+00 4.1900E+06-1.0000E+00162533103   22
 4.3000E+06-9.7000E-01 5.2000E+06-3.2000E-01 5.6000E+06-1.0000E+00162533103   23
 5.8000E+06-1.0000E+00 6.0000E+06-1.0000E+00 6.5000E+06-1.0000E+00162533103   24
 7.0000E+06-5.7000E-01 8.5000E+06-1.0000E+00 9.0000E+06-1.0000E+00162533103   25
 9.5000E+06-1.0000E+00 1.0000E+07-1.0000E+00 1.0500E+07-4.5000E-01162533103   26
 1.2000E+07-7.3000E-01 1.3500E+07-1.0000E+00 1.4000E+07-8.4000E-01162533103   27
 1.6000E+07-1.0000E+00 1.7000E+07-1.0000E+00 1.8000E+07-1.0000E+00162533103   28
 1.9000E+07-1.0000E+00 2.0000E+07 0.0000E+00 1.0000E-05 0.0000E+00162533103   29
 9.5700E+05 4.3725E-01 1.5800E+06 4.0602E-01 1.6300E+06 2.2757E-01162533103   30
 1.6800E+06 2.9271E-01 1.7800E+06 4.3861E-01 1.8300E+06 2.2645E-01162533103   31
 1.8800E+06 2.8648E-01 1.9200E+06 3.5525E-01 1.9600E+06 4.1335E-01162533103   32
 2.0000E+06 4.9340E-01 2.0400E+06 6.0066E-01 2.0800E+06 5.4379E-01162533103   33
 2.1200E+06 4.7401E-01 2.1600E+06 1.4893E-01 2.2000E+06 9.0955E-02162533103   34
 2.2500E+06 1.2562E-01 2.3000E+06 1.1533E-01 2.3500E+06 2.0570E-01162533103   35
 2.4000E+06 1.0432E-01 2.4500E+06 1.2650E-01 2.5000E+06 1.6181E-01162533103   36
 2.5500E+06 1.0266E-01 2.6000E+06 1.6317E-01 2.6500E+06 1.2862E-01162533103   37
 2.7000E+06 2.5907E-01 2.7500E+06 1.6019E-01 2.8000E+06 1.0416E-01162533103   38
 2.8400E+06 1.2622E-01 2.9000E+06 1.1459E-01 2.9500E+06 1.3695E-01162533103   39
 3.0000E+06 1.4834E-01 3.0500E+06 1.8369E-01 3.1000E+06 1.6221E-01162533103   40
 3.1500E+06 1.9655E-01 3.2000E+06 1.5083E-01 3.2400E+06 2.3966E-01162533103   41
 3.2800E+06 1.7087E-01 3.3300E+06 1.8401E-01 3.3700E+06 1.4962E-01162533103   42
 3.4000E+06 1.3864E-01 3.4400E+06 1.6099E-01 3.4700E+06 1.7271E-01162533103   43
 3.5100E+06 1.4944E-01 3.5500E+06 1.0342E-01 3.6000E+06 1.5026E-01162533103   44
 3.6500E+06 1.2707E-01 3.7000E+06 1.7492E-01 3.7500E+06 2.3126E-01162533103   45
 3.8000E+06 1.8419E-01 3.8500E+06 2.1541E-01 3.9000E+06 2.8759E-01162533103   46
 3.9400E+06 3.7783E-01 3.9800E+06 2.6294E-01 4.0400E+06 1.3806E-01162533103   47
 4.1000E+06 3.4473E-01 4.1900E+06 3.8025E-01 4.3000E+06 2.3099E-01162533103   48
 5.2000E+06 5.1845E-01 5.6000E+06 1.2626E-01 5.8000E+06 1.2742E-01162533103   49
 6.0000E+06 8.9710E-02 6.5000E+06 5.4451E-02 7.0000E+06 3.8618E-02162533103   50
 8.5000E+06 3.7710E-02 9.0000E+06 3.8965E-02 9.5000E+06 3.9717E-02162533103   51
 1.0000E+07 3.6543E-02 1.0500E+07 3.6762E-02 1.2000E+07 4.0115E-02162533103   52
 1.3500E+07 4.2948E-02 1.4000E+07 1.1829E-01 1.6000E+07 1.3460E-01162533103   53
 1.7000E+07 1.3626E-01 1.8000E+07 1.4464E-01 1.9000E+07 1.5243E-01162533103   54
 2.0000E+07 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00162533103   55
 0.0000E+00 0.0000E+00          0          1        198         99162533103   56
 1.0000E-05 0.0000E+00 9.5700E+05 1.0324E-01 1.0000E+06 1.0324E-01162533103   57
 1.1000E+06 1.0324E-01 1.2000E+06 1.0324E-01 1.3000E+06 1.0324E-01162533103   58
 1.4000E+06 1.0324E-01 1.5000E+06 1.0324E-01 1.5800E+06 1.4837E-01162533103   59
 1.6300E+06 4.6608E-02 1.6800E+06 7.7112E-02 1.7800E+06 1.7314E-01162533103   60
 1.8300E+06 4.6150E-02 1.8800E+06 7.3861E-02 1.9200E+06 1.1358E-01162533103   61
 1.9600E+06 1.5377E-01 2.0000E+06 2.1910E-01 2.0400E+06 3.2471E-01162533103   62
 2.0800E+06 2.6614E-01 2.1200E+06 2.0222E-01 2.1600E+06 1.9961E-02162533103   63
 2.2000E+06 7.4455E-03 2.2500E+06 1.4202E-02 2.3000E+06 1.1971E-02162533103   64
 2.3500E+06 3.8080E-02 2.4000E+06 9.7937E-03 2.4500E+06 1.4403E-02162533103   65
 2.5000E+06 2.3565E-02 2.5500E+06 9.4860E-03 2.6000E+06 2.3963E-02162533103   66
 2.6500E+06 1.4888E-02 2.7000E+06 6.0406E-02 2.7500E+06 2.3094E-02162533103   67
 2.8000E+06 9.7642E-03 2.8400E+06 1.4338E-02 2.9000E+06 1.1818E-02162533103   68
 2.9500E+06 1.6879E-02 3.0000E+06 1.9804E-02 3.0500E+06 3.0368E-02162533103   69
 3.1000E+06 2.3681E-02 3.1500E+06 3.4770E-02 3.2000E+06 2.0475E-02162533103   70
 3.2400E+06 5.1692E-02 3.2800E+06 2.6278E-02 3.3300E+06 3.0475E-02162533103   71
 3.3700E+06 2.0147E-02 3.4000E+06 1.7299E-02 3.4400E+06 2.3325E-02162533103   72
 3.4700E+06 2.6845E-02 3.5100E+06 2.0098E-02 3.5500E+06 9.6267E-03162533103   73
 3.6000E+06 2.0321E-02 3.6500E+06 1.4531E-02 3.7000E+06 2.7538E-02162533103   74
 3.7500E+06 4.8133E-02 3.8000E+06 3.0535E-02 3.8500E+06 4.1763E-02162533103   75
 3.9000E+06 7.4438E-02 3.9400E+06 1.2848E-01 3.9800E+06 6.2225E-02162533103   76
 4.0400E+06 1.7156E-02 4.1000E+06 1.0695E-01 4.1900E+06 1.3013E-01162533103   77
 4.3000E+06 4.6579E-02 4.4100E+06 4.6579E-02 4.4500E+06 4.6579E-02162533103   78
 4.6000E+06 4.6579E-02 4.7500E+06 4.6579E-02 4.8200E+06 4.6579E-02162533103   79
 4.8900E+06 4.6579E-02 5.0000E+06 4.6579E-02 5.2000E+06 7.7413E-02162533103   80
 5.4000E+06 7.7413E-02 5.6000E+06 1.4347E-02 5.8000E+06 1.4611E-02162533103   81
 6.0000E+06 7.2431E-03 6.5000E+06 2.6684E-03 7.0000E+06 7.6506E-04162533103   82
 7.5000E+06 7.6506E-04 8.0000E+06 7.6506E-04 8.5000E+06 1.2798E-03162533103   83
 9.0000E+06 1.3664E-03 9.5000E+06 1.4197E-03 1.0000E+07 1.2019E-03162533103   84
 1.0500E+07 5.4733E-04 1.1000E+07 5.4733E-04 1.1500E+07 5.4733E-04162533103   85
 1.2000E+07 1.0573E-03 1.2500E+07 1.0573E-03 1.3000E+07 1.0573E-03162533103   86
 1.3500E+07 1.6601E-03 1.4000E+07 1.0578E-02 1.4500E+07 1.0578E-02162533103   87
 1.5000E+07 1.0578E-02 1.6000E+07 1.6305E-02 1.7000E+07 1.6710E-02162533103   88
 1.8000E+07 1.8829E-02 1.9000E+07 2.0912E-02 2.0000E+07 0.0000E+00162533103   89
 0.0000E+00 0.0000E+00          0          8        198         99162533103   90
 1.0000E-05 0.0000E+00 9.5700E+05 4.6987E-13 1.0000E+06 4.0977E-12162533103   91
 1.1000E+06 1.6132E-11 1.2000E+06 7.5263E-11 1.3000E+06 3.3543E-10162533103   92
 1.4000E+06 1.4052E-09 1.5000E+06 4.6255E-09 1.5800E+06 1.8175E-08162533103   93
 1.6300E+06 1.1652E-08 1.6800E+06 4.5325E-08 1.7800E+06 3.0780E-07162533103   94
 1.8300E+06 2.0352E-07 1.8800E+06 5.1869E-07 1.9200E+06 9.9963E-07162533103   95
 1.9600E+06 1.6242E-06 2.0000E+06 2.7096E-06 2.0400E+06 6.4783E-06162533103   96
 2.0800E+06 1.1072E-05 2.1200E+06 1.9868E-05 2.1600E+06 3.3565E-06162533103   97
 2.2000E+06 1.9116E-06 2.2500E+06 5.7852E-06 2.3000E+06 5.7230E-06162533103   98
 2.3500E+06 2.1399E-05 2.4000E+06 5.8037E-06 2.4500E+06 7.8821E-06162533103   99
 2.5000E+06 1.2628E-05 2.5500E+06 5.9731E-06 2.6000E+06 1.4956E-05162533103  100
 2.6500E+06 5.6757E-06 2.7000E+06 3.0742E-05 2.7500E+06 2.1495E-05162533103  101
 2.8000E+06 9.6057E-06 2.8400E+06 1.4095E-05 2.9000E+06 1.4186E-05162533103  102
 2.9500E+06 2.7937E-05 3.0000E+06 4.9213E-05 3.0500E+06 9.8839E-05162533103  103
 3.1000E+06 7.4618E-05 3.1500E+06 9.1742E-05 3.2000E+06 4.4272E-05162533103  104
 3.2400E+06 1.2001E-04 3.2800E+06 9.5391E-05 3.3300E+06 1.4439E-04162533103  105
 3.3700E+06 1.0161E-04 3.4000E+06 8.4846E-05 3.4400E+06 1.1310E-04162533103  106
 3.4700E+06 1.3775E-04 3.5100E+06 1.0996E-04 3.5500E+06 5.8369E-05162533103  107
 3.6000E+06 1.2237E-04 3.6500E+06 7.8251E-05 3.7000E+06 1.1350E-04162533103  108
 3.7500E+06 1.4525E-04 3.8000E+06 8.7453E-05 3.8500E+06 1.7881E-04162533103  109
 3.9000E+06 4.5482E-04 3.9400E+06 9.2900E-04 3.9800E+06 6.0536E-04162533103  110
 4.0400E+06 2.0134E-04 4.1000E+06 1.3697E-03 4.1900E+06 1.7611E-03162533103  111
 4.3000E+06 6.2745E-04 4.4100E+06 5.0611E-04 4.4500E+06 4.0547E-04162533103  112
 4.6000E+06 4.0395E-04 4.7500E+06 3.7820E-04 4.8200E+06 3.4763E-04162533103  113
 4.8900E+06 3.0327E-04 5.0000E+06 2.5545E-04 5.2000E+06 3.9126E-04162533103  114
 5.4000E+06 4.9800E-04 5.6000E+06 1.2711E-04 5.8000E+06 1.4110E-04162533103  115
 6.0000E+06 7.1879E-05 6.5000E+06 2.8119E-05 7.0000E+06 8.8116E-06162533103  116
 7.5000E+06 8.4801E-06 8.0000E+06 8.4522E-06 8.5000E+06 1.5461E-05162533103  117
 9.0000E+06 1.7429E-05 9.5000E+06 2.0092E-05 1.0000E+07 1.8530E-05162533103  118
 1.0500E+07 9.0846E-06 1.1000E+07 9.2760E-06 1.1500E+07 9.1510E-06162533103  119
 1.2000E+07 1.6018E-05 1.2500E+07 1.3364E-05 1.3000E+07 1.1289E-05162533103  120
 1.3500E+07 1.4055E-05 1.4000E+07 6.9831E-05 1.4500E+07 5.7844E-05162533103  121
 1.5000E+07 4.2055E-05 1.6000E+07 3.8698E-05 1.7000E+07 2.3904E-05162533103  122
 1.8000E+07 1.8309E-05 1.9000E+07 1.5467E-05 2.0000E+07 0.0000E+00162533103  123
 0.0000E+00 0.0000E+00          0          1        118         59162533103  124
 1.0000E-05 0.0000E+00 9.5700E+05 1.9119E-01 1.5800E+06 1.6485E-01162533103  125
 1.6300E+06 5.1787E-02 1.6800E+06 8.5681E-02 1.7800E+06 1.9237E-01162533103  126
 1.8300E+06 5.1277E-02 1.8800E+06 8.2068E-02 1.9200E+06 1.2620E-01162533103  127
 1.9600E+06 1.7086E-01 2.0000E+06 2.4344E-01 2.0400E+06 3.6079E-01162533103  128
 2.0800E+06 2.9571E-01 2.1200E+06 2.2469E-01 2.1600E+06 2.2179E-02162533103  129
 2.2000E+06 8.2727E-03 2.2500E+06 1.5780E-02 2.3000E+06 1.3301E-02162533103  130
 2.3500E+06 4.2311E-02 2.4000E+06 1.0882E-02 2.4500E+06 1.6003E-02162533103  131
 2.5000E+06 2.6183E-02 2.5500E+06 1.0540E-02 2.6000E+06 2.6626E-02162533103  132
 2.6500E+06 1.6542E-02 2.7000E+06 6.7118E-02 2.7500E+06 2.5660E-02162533103  133
 2.8000E+06 1.0849E-02 2.8400E+06 1.5931E-02 2.9000E+06 1.3131E-02162533103  134
 2.9500E+06 1.8754E-02 3.0000E+06 2.2004E-02 3.0500E+06 3.3742E-02162533103  135
 3.1000E+06 2.6312E-02 3.1500E+06 3.8633E-02 3.2000E+06 2.2750E-02162533103  136
 3.2400E+06 5.7436E-02 3.2800E+06 2.9198E-02 3.3300E+06 3.3861E-02162533103  137
 3.3700E+06 2.2386E-02 3.4000E+06 1.9221E-02 3.4400E+06 2.5917E-02162533103  138
 3.4700E+06 2.9828E-02 3.5100E+06 2.2332E-02 3.5500E+06 1.0696E-02162533103  139
 3.6000E+06 2.2579E-02 3.6500E+06 1.6146E-02 3.7000E+06 3.0597E-02162533103  140
 3.7500E+06 5.3481E-02 3.8000E+06 3.3928E-02 3.8500E+06 4.6404E-02162533103  141
 3.9000E+06 8.2709E-02 3.9400E+06 1.4276E-01 3.9800E+06 6.9139E-02162533103  142
 4.0400E+06 1.9062E-02 4.1000E+06 1.1884E-01 4.1900E+06 1.4459E-01162533103  143
 4.3000E+06 5.3355E-02 5.2000E+06 0.0                             162533103  144
 0.0        0.0                 1          5        210         20162533103  145
 1.0000E-05 5.2000E+06 5.6000E+06 5.8000E+06 6.0000E+06 6.5000E+06162533103  146
 7.0000E+06 8.5000E+06 9.0000E+06 9.5000E+06 1.0000E+07 1.0500E+07162533103  147
 1.2000E+07 1.3500E+07 1.4000E+07 1.6000E+07 1.7000E+07 1.8000E+07162533103  148
 1.9000E+07 2.0000E+07 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00162533103  149
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00162533103  150
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00162533103  151
 0.0000E+00 0.0000E+00 0.0000E+00 2.6879E-01-1.6917E-04 7.6244E-05162533103  152
 7.6222E-04 6.2428E-04 5.0197E-04 5.2466E-04 5.5936E-04 5.5109E-04162533103  153
 5.3023E-04 5.2522E-04 4.1067E-04 3.3731E-04 7.0923E-04 7.5401E-04162533103  154
 1.2360E-03 1.2362E-03 1.2365E-03 1.5941E-02 1.3651E-02 9.8297E-04162533103  155
 6.7245E-04 5.9382E-04 6.0350E-04 6.3004E-04 6.2252E-04 6.0748E-04162533103  156
 5.6306E-04 3.8830E-04 2.8840E-04 7.8421E-04 8.4368E-04 1.5155E-03162533103  157
 1.5156E-03 1.5158E-03 1.6235E-02 9.6110E-04 6.8671E-04 5.8948E-04162533103  158
 6.0468E-04 6.3316E-04 6.2636E-04 6.1117E-04 5.6685E-04 3.9017E-04162533103  159
 2.9064E-04 7.9613E-04 8.5614E-04 1.5382E-03 1.5384E-03 1.5389E-03162533103  160
 8.0479E-03 2.5416E-03 6.7123E-04 7.8051E-04 8.0128E-04 7.5961E-04162533103  161
 7.2126E-04 6.5442E-04 4.3721E-04 3.8278E-04 5.5604E-04 5.8133E-04162533103  162
 8.6206E-04 8.6210E-04 8.6223E-04 2.9649E-03 5.5056E-04 7.2580E-04162533103  163
 7.6567E-04 7.1700E-04 6.7961E-04 6.3216E-04 4.3992E-04 3.8498E-04162533103  164
 4.6967E-04 4.8689E-04 6.5527E-04 6.5528E-04 6.5537E-04 1.4913E-03162533103  165
 6.4250E-04 6.5678E-04 6.2474E-04 5.9695E-04 5.2029E-04 3.8122E-04162533103  166
 3.4843E-04 3.9503E-04 4.0583E-04 5.1030E-04 5.1045E-04 5.1050E-04162533103  167
 1.4220E-03 7.3842E-04 6.8011E-04 7.0157E-04 6.0537E-04 4.1142E-04162533103  168
 3.7075E-04 4.1240E-04 4.2421E-04 5.3492E-04 5.3508E-04 5.3511E-04162533103  169
 1.5183E-03 9.1191E-04 6.9948E-04 6.0628E-04 4.2545E-04 3.8548E-04162533103  170
 4.3714E-04 4.4949E-04 5.7461E-04 5.7469E-04 5.7485E-04 1.5774E-03162533103  171
 7.0082E-04 6.9341E-04 4.1684E-04 3.6597E-04 4.2464E-04 4.3794E-04162533103  172
 5.6898E-04 5.6912E-04 5.6922E-04 1.3354E-03 8.5551E-04 4.5574E-04162533103  173
 3.6290E-04 4.0894E-04 4.2291E-04 5.4441E-04 5.4452E-04 5.4461E-04162533103  174
 1.3514E-03 5.3505E-04 3.6596E-04 3.9729E-04 4.1346E-04 5.1956E-04162533103  175
 5.1969E-04 5.1975E-04 1.6092E-03 3.8766E-04 3.3510E-04 3.4532E-04162533103  176
 3.5854E-04 3.5862E-04 3.5868E-04 1.8445E-03-1.5721E-03-4.2629E-04162533103  177
 2.6490E-04 2.6489E-04 2.6498E-04 1.3992E-02 5.9123E-03 7.7589E-04162533103  178
 7.7619E-04 7.7627E-04 1.8117E-02 8.3496E-04 8.3499E-04 8.3513E-04162533103  179
 1.8567E-02 1.3578E-02 1.3579E-02 2.0922E-02 1.3581E-02 2.3235E-02162533103  180
 0.0000E+00 0.0000E+00          0          1          8          4162533103  181
 1.0000E-05 0.0000E+00 9.2000E+05 1.9119E-01 9.5700E+05 0.0000E+00162533103  182
 2.0000E+07 0.0000E+00                                            162533103  183
                                                                  162533  099999
                                                                  1625 0  0    0
                                                                     0 0  0    0
 2.10450E+4 4.45700E+1          2          0          1          12126 1451    1
 0.0        0.0                 0          0          0          62126 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022126 1451    3
 3.00000E+2 0.0                 1          0        104          42126 1451    4
 21-Sc- 45 CNDC       EVAL-FEB91 Z.X.ZHAO                         2126 1451    5
                      DIST-                                       2126 1451    6
 ----- DOSIMETRY FILE                                             2126 1451    7
 ----- INCIDENT NEUTRON DATA                                      2126 1451    8
 ----- ENDF-6 FORMAT                                              2126 1451    9
    THIS EVALUATION IS MADE MAINLY BASED ON THE RESONANCE         2126 1451   10
 PARAMETERS GIVEN BY REF.[1], MEASURED DATA OF REFS.[2-10]        2126 1451   11
 AND THE SYSTEMATICS OF EXCITATION FUNCTION FOR (N,GAMMA)         2126 1451   12
 REACTION OF REF.[11]. A SET OF RESOLVED RESONANCE PARAMETERS     2126 1451   13
 ARE GIVEN FOR EN < 100 KEV. IN THE REGION OF EN > 100 KEV,       2126 1451   14
 THE SMOOTH CROSS SECTIONS ARE GIVEN.                             2126 1451   15
    MF=2 MT=251     RESONANCE PARAMETER                           2126 1451   16
       POSITIVE ENERGY RESONANCE PARAMETERS LISTED BELOW ARE      2126 1451   17
    BASED ON THOSE OF REF.[1]. TO FIT KENNY'S AVERAGE CROSS       2126 1451   18
    SECTIONS [2] (CORRECTED IN REF.[3]), THE CAPTURE WIDTHS       2126 1451   19
    HAVE BEEN ADJUSTED. THE NEGATIVE ENERGY LEVEL PARAMETERS      2126 1451   20
    ARE TAKEN FROM JENDL-3 EVALUATION [12] TO REPRODUCE           2126 1451   21
    THERMAL CROSS SECTION 27.2 B WHICH IS IN GOOD AGREEMENT       2126 1451   22
    WITH 27.2 +- 0.2 B GIVEN BY REF.[1].                          2126 1451   23
                                                                  2126 1451   24
    MF=3 MT=102     SMOOTH CROSS SECTION                          2126 1451   25
       THE SMOOTH CROSS SECTION CALCULATED FROM ZHAO'S            2126 1451   26
    SYSTEMATICS [11] ARE CONSISTENT WITH THE MEASURED DATA OF     2126 1451   27
    REFS.[2-9] FROM 1 KEV TO 20 MEV. THEREFORE THE SYSTEMATICS    2126 1451   28
    IS USED IN THIS EVALUATION TO GIVE THE SMOOTH CROSS           2126 1451   29
    SECTIONS FOR EN > 100 KEV.                                    2126 1451   30
                                                                  2126 1451   31
    MF=8 MT=102    RADIOACTIVE DECAY DATA                         2126 1451   32
       HALF-TIME OF SC-46 IS TAKEN FROM REF.[13]                  2126 1451   33
                                                                  2126 1451   34
    MF=32 AND 33  MT=102     COVARIANCE DATA                      2126 1451   35
       LONG-RANGE COMPONENT (GIVEN IN FILE 32):                   2126 1451   36
          10-5 EV TO 1 KEV----- THE ERROR OF THERMAL CROSS        2126 1451   37
                                SECTION.                          2126 1451   38
          1 KEV TO 100 KEV----- THE NORMALIZATION ERROR OF        2126 1451   39
                                KENNY'S MEASUREMENT.              2126 1451   40
          100 KEV TO 20 MEV---- THE SHAPE ERROR OF THE            2126 1451   41
                                SYSTEMATICS.                      2126 1451   42
       SHORT-RANGE COMPONENT:                                     2126 1451   43
          FOR EN < 100 KEV, THIS COMPONENT IS GIVEN IN FILE 32.   2126 1451   44
       IN THIS FILE, ONLY THE ERRORS OF SOME LARGE S-WAVE         2126 1451   45
       RESONANCE PARAMETERS ARE CONSIDERED. THE SHORT-RANGE       2126 1451   46
       COMPONENT FOR EN > 100 KEV ARE GIVEN IN FILE 33 BASED ON   2126 1451   47
       THE ERRORS OF PERKIN'S MEASUREMENT [6].                    2126 1451   48
                                                                  2126 1451   49
    REFERENCES                                                    2126 1451   50
     [1]  S. F. MUGHABGHAB ET AL., BNL-325, 4TH, VOL.1 (1981)     2126 1451   51
     [2]  M. J. KENNY ET AL., AUST. J. PHYS., 30, 605 (1977)      2126 1451   52
     [3]  B. J. ALLEN ET AL., NUCL. SCI. AND ENG., 82, 230 (1982) 2126 1451   53
     [4]  S. A. ROMANOV ET AL., YF, 1, 229 (1965)                 2126 1451   54
     [5]  R. BOOTH ET AL., PHYS. REV., 112, 226 (1958)            2126 1451   55
     [6]  J. L. PERKIN, J. NUCL. ENERGY, 17, 349 (1963)           2126 1451   56
     [7]  J. CSIKAI ET AL., NUCL. PHYS., A95, 229 (1967)          2126 1451   57
     [8]  M. WAGNER ET AL., APA, 52, 30 (1980)                    2126 1451   58
     [9]  M. BUDNAR ET AL., INDC(YUG)-6 (1979)                    2126 1451   59
     [10] W. MANNHART, ZP/A, 272, 273 (1975)                      2126 1451   60
     [11] Z. X. ZHAO ET AL., CHINESE NUCL. PHYS.,VOL.11, 71 (1989)2126 1451   61
     [12] T. NAKAGAWA ET AL., JAERI-M, 90-099 (1990)              2126 1451   62
     [13] J. TULI, NUCLEAR WALLET CARDS, NNDC, 1990               2126 1451   63
                                                                  2126 1451   64
 ================================================================ 2126 1451   65
  The Q values and threshold energies were updated prior to pro-  2126 1451   66
  cessing through the codes to comply with the values obtained    2126 1451   67
  using the NNDC calculation program which is based on the 1995   2126 1451   68
  Update to the Atomic mass Evaluation.                           2126 1451   69
                                                                  2126 1451   70
  Total and Elastic cross sections were only given upto 100 Kev   2126 1451   71
  in the original data.For these two reactions the energy region  2126 1451   72
  between 100 KeV and 20 Mev was taken the ENDF/B-6 library,      2126 1451   73
  linearised and added to this file.                              2126 1451   74
                                                                  2126 1451   75
  The original SC45G cross section set had uncertainties for the  2126 1451   76
  resonance parameters in file MF=32, which were converted in the 2126 1451   77
  extended SAND-II group structure and inserted in file MF=33 as  2126 1451   78
  extra "NI type" sub-subsections.                                2126 1451   79
                                                                  2126 1451   80
 ***************** Program LINEAR (VERSION 2002-1) ***************2126 1451   81
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2126 1451   82
 Data Linearized to Within an Accuracy of .100000000 per-cent     2126 1451   83
 ***************** Program RECENT (VERSION 2002-1) ***************2126 1451   84
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2126 1451   85
 Data Linearized to within an Accuracy of .100000000 per-cent     2126 1451   86
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2126 1451   87
 Data Doppler Broadened to 300.000000 Kelvin                      2126 1451   88
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2126 1451   89
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2126 1451   90
 ***************** Program FIXUP (Version 2002-1) ****************2126 1451   91
 Corrected ZA/AWR in All Sections-----------------------------Yes 2126 1451   92
 Corrected Thresholds-----------------------------------------Yes 2126 1451   93
 Extended Cross Sections to 20 MeV----------------------------No  2126 1451   94
 Allow Cross Section Deletion---------------------------------No  2126 1451   95
 Allow Cross Section Reconstruction---------------------------No  2126 1451   96
 Make All Cross Sections Non-Negative-------------------------Yes 2126 1451   97
 Delete Energies Not in Ascending Order-----------------------Yes 2126 1451   98
 Deleted Duplicate Points-------------------------------------Yes 2126 1451   99
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2126 1451  100
 Check for Legal MF/MT Numbers--------------------------------Yes 2126 1451  101
 Allow Creation of Missing Sections---------------------------No  2126 1451  102
 Allow Insertion of Energy Points-----------------------------No  2126 1451  103
 Create Uniform Energy Grid-----------------------------------No  2126 1451  104
 Delete Section if Cross Section =0 at All Energies-----------Yes 2126 1451  105
 ***************** Program GROUPIE (VERSION 2002-1) **************2126 1451  106
 Unshielded Group Averages Using  640 Groups                      2126 1451  107
 Weighting Spectrum: Flat (Constant) Spectrum                     2126 1451  108
                                1        451        112          12126 1451  109
                                2        151        201          12126 1451  110
                                3        102        217          12126 1451  111
                               33        102        150          12126 1451  112
                                                                  2126 1  099999
                                                                  2126 0  0    0
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 2.10450E+4 1.00000E+0          0          0          1          02126 2151    2
 1.00000E-5 1.00000E+5          1          2          0          02126 2151    3
 3.50000E+0 4.55000E-1          0          0          2          02126 2151    4
 4.45700E+1 0.0                 0          0        492         822126 2151    5
-700.000000 3.00000000 107.110000 106.700000 .410000000 0.0       2126 2151    6
-294.000000 4.00000000 30.6660000 30.2600000 .405500000 0.0       2126 2151    7
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 10662.0000 3.00000000 14.8180000 14.0000000 .818250000 0.0       2126 2151   13
 10740.0000 4.00000000 15.7910000 15.0000000 .790940000 0.0       2126 2151   14
 11580.0000 4.00000000 290.770000 290.000000 .772110000 0.0       2126 2151   15
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 15850.0000 3.00000000 5.79090000 5.00000000 .790940000 0.0       2126 2151   19
 18580.0000 3.00000000 32.7910000 32.0000000 .790940000 0.0       2126 2151   20
 18870.0000 4.00000000 62.6980000 62.0000000 .697730000 0.0       2126 2151   21
 20500.0000 4.00000000 80.9360000 80.0000000 .935510000 0.0       2126 2151   22
 20930.0000 3.00000000 750.670000 750.000000 .674650000 0.0       2126 2151   23
 24010.0000 3.00000000 51.2260000 50.0000000 1.22570000 0.0       2126 2151   24
 24315.0000 4.00000000 70.5200000 70.0000000 .519610000 0.0       2126 2151   25
 26925.0000 4.00000000 103.010000 102.000000 1.01200000 0.0       2126 2151   26
 27900.0000 3.00000000 110.910000 110.000000 .912460000 0.0       2126 2151   27
 29480.0000 4.00000000 30.6910000 30.0000000 .691420000 0.0       2126 2151   28
 29630.0000 4.00000000 50.7230000 50.0000000 .722840000 0.0       2126 2151   29
 32180.0000 3.00000000 571.150000 570.000000 1.15150000 0.0       2126 2151   30
 33730.0000 3.00000000 201.090000 200.000000 1.09270000 0.0       2126 2151   31
 34860.0000 3.00000000 114.990000 114.000000 .991700000 0.0       2126 2151   32
 35080.0000 4.00000000 150.690000 150.000000 .685020000 0.0       2126 2151   33
 39980.0000 4.00000000 181.350000 180.000000 1.35010000 0.0       2126 2151   34
 40500.0000 3.00000000 89.3740000 88.0000000 1.37400000 0.0       2126 2151   35
 40815.0000 4.00000000 124.690000 124.000000 .687000000 0.0       2126 2151   36
 43050.0000 4.00000000 151.150000 150.000000 1.14700000 0.0       2126 2151   37
 43215.0000 3.00000000 31.1530000 30.0000000 1.15300000 0.0       2126 2151   38
 45730.0000 3.00000000 420.560000 420.000000 .560000000 0.0       2126 2151   39
 47180.0000 3.00000000 60.5700000 60.0000000 .570000000 0.0       2126 2151   40
 48790.0000 4.00000000 40.5130000 40.0000000 .513000000 0.0       2126 2151   41
 49120.0000 3.00000000 40.4420000 40.0000000 .442000000 0.0       2126 2151   42
 51160.0000 4.00000000 841.400000 840.000000 1.39600000 0.0       2126 2151   43
 51685.0000 3.00000000 40.4320000 40.0000000 .432000000 0.0       2126 2151   44
 52025.0000 4.00000000 40.4970000 40.0000000 .497000000 0.0       2126 2151   45
 52330.0000 3.00000000 70.4490000 70.0000000 .449000000 0.0       2126 2151   46
 53075.0000 3.00000000 40.3040000 40.0000000 .304000000 0.0       2126 2151   47
 54730.0000 3.00000000 41.8900000 40.0000000 1.89000000 0.0       2126 2151   48
 55125.0000 3.00000000 40.4780000 40.0000000 .478000000 0.0       2126 2151   49
 57890.0000 3.00000000 35.5230000 35.0000000 .523000000 0.0       2126 2151   50
 58770.0000 3.00000000 1435.80000 1435.00000 .840000000 0.0       2126 2151   51
 59110.0000 3.00000000 51.1240000 50.0000000 1.12400000 0.0       2126 2151   52
 60140.0000 3.00000000 40.8350000 40.0000000 .835000000 0.0       2126 2151   53
 61890.0000 4.00000000 520.750000 520.000000 .751000000 0.0       2126 2151   54
 62490.0000 3.00000000 495.070000 494.000000 1.07400000 0.0       2126 2151   55
 62850.0000 4.00000000 50.5230000 50.0000000 .523000000 0.0       2126 2151   56
 66000.0000 3.00000000 40.3520000 40.0000000 .352000000 0.0       2126 2151   57
 66100.0000 4.00000000 941.930000 940.000000 1.93300000 0.0       2126 2151   58
 67850.0000 4.00000000 51.6150000 50.0000000 1.61500000 0.0       2126 2151   59
 68375.0000 3.00000000 45.5400000 44.0000000 1.54000000 0.0       2126 2151   60
 70110.0000 3.00000000 1550.70000 1550.00000 .731940000 0.0       2126 2151   61
 71700.0000 4.00000000 201.960000 200.000000 1.95940000 0.0       2126 2151   62
 73200.0000 3.00000000 62.1600000 61.0000000 1.16040000 0.0       2126 2151   63
 73600.0000 3.00000000 60.3910000 60.0000000 .390980000 0.0       2126 2151   64
 74700.0000 3.00000000 61.4400000 60.0000000 1.44000000 0.0       2126 2151   65
 75000.0000 4.00000000 46.7080000 45.0000000 1.70820000 0.0       2126 2151   66
 77025.0000 4.00000000 50.6360000 50.0000000 .636470000 0.0       2126 2151   67
 77500.0000 3.00000000 525.610000 525.000000 .608060000 0.0       2126 2151   68
 77925.0000 4.00000000 41.0060000 40.0000000 1.00590000 0.0       2126 2151   69
 79150.0000 3.00000000 89.0090000 88.0000000 1.00930000 0.0       2126 2151   70
 79800.0000 3.00000000 2452.40000 2450.00000 2.44020000 0.0       2126 2151   71
 81200.0000 4.00000000 600.350000 600.000000 .351570000 0.0       2126 2151   72
 85600.0000 4.00000000 850.440000 850.000000 .439170000 0.0       2126 2151   73
 86400.0000 3.00000000 241.240000 240.600000 .640060000 0.0       2126 2151   74
 87650.0000 4.00000000 69.9460000 66.6670000 3.27860000 0.0       2126 2151   75
 88600.0000 3.00000000 482.130000 481.000000 1.12830000 0.0       2126 2151   76
 90200.0000 4.00000000 135.840000 135.000000 .840000000 0.0       2126 2151   77
 91700.0000 3.00000000 481.840000 481.000000 .840000000 0.0       2126 2151   78
 94400.0000 3.00000000 620.840000 620.000000 .840000000 0.0       2126 2151   79
 95940.0000 3.00000000 30.4590000 30.0000000 .459000000 0.0       2126 2151   80
 99800.0000 3.00000000 1600.80000 1600.00000 .840000000 0.0       2126 2151   81
 100700.000 4.00000000 300.840000 300.000000 .840000000 0.0       2126 2151   82
 101000.000 3.00000000 400.840000 400.000000 .840000000 0.0       2126 2151   83
 102100.000 4.00000000 300.840000 300.000000 .840000000 0.0       2126 2151   84
 102300.000 3.00000000 350.840000 350.000000 .840000000 0.0       2126 2151   85
 104000.000 4.00000000 150.840000 150.000000 .840000000 0.0       2126 2151   86
 105700.000 4.00000000 150.840000 150.000000 .840000000 0.0       2126 2151   87
 4.45700E+1 0.0                 1          0        678        1132126 2151   88
 460.600000 3.00000000 .505000000 .005000000 .500000000 0.0       2126 2151   89
 1060.40000 3.00000000 .511000000 .011000000 .500000000 0.0       2126 2151   90
 2715.00000 4.00000000 .501000000 .008000000 .493000000 0.0       2126 2151   91
 2737.00000 3.00000000 .520000000 .027000000 .493000000 0.0       2126 2151   92
 3404.00000 4.00000000 2.17750000 2.00000000 .177480000 0.0       2126 2151   93
 3582.00000 3.00000000 .592000000 .099000000 .493000000 0.0       2126 2151   94
 5943.00000 4.00000000 .587770000 .021000000 .566770000 0.0       2126 2151   95
 7560.00000 3.00000000 .541100000 .017000000 .524100000 0.0       2126 2151   96
 8558.00000 4.00000000 .606100000 .082000000 .524100000 0.0       2126 2151   97
 9725.00000 4.00000000 3.86690000 3.50000000 .366870000 0.0       2126 2151   98
 10189.0000 3.00000000 .590800000 .120000000 .470800000 0.0       2126 2151   99
 11265.0000 2.00000000 4.38790000 4.00000000 .387940000 0.0       2126 2151  100
 14050.0000 3.00000000 2.89450000 2.50000000 .394530000 0.0       2126 2151  101
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 15280.0000 3.00000000 .622800000 .152000000 .470800000 0.0       2126 2151  103
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 17192.0000 3.00000000 3.73260000 3.50000000 .232580000 0.0       2126 2151  105
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 18504.0000 3.00000000 .482800000 .012000000 .470800000 0.0       2126 2151  107
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 20726.0000 4.00000000 4.36980000 4.00000000 .369800000 0.0       2126 2151  109
 21114.0000 4.00000000 10.3600000 10.0000000 .360370000 0.0       2126 2151  110
 21580.0000 5.00000000 5.39490000 5.00000000 .394950000 0.0       2126 2151  111
 23015.0000 3.00000000 .705800000 .182000000 .523800000 0.0       2126 2151  112
 23065.0000 4.00000000 .534800000 .011000000 .523800000 0.0       2126 2151  113
 23838.0000 3.00000000 .612800000 .089000000 .523800000 0.0       2126 2151  114
 27190.0000 4.00000000 .555800000 .032000000 .523800000 0.0       2126 2151  115
 28040.0000 2.00000000 6.41380000 6.00000000 .413800000 0.0       2126 2151  116
 28235.0000 3.00000000 .697800000 .174000000 .523800000 0.0       2126 2151  117
 29410.0000 4.00000000 10.1960000 10.0000000 .195900000 0.0       2126 2151  118
 30010.0000 3.00000000 9.41590000 9.00000000 .415950000 0.0       2126 2151  119
 31135.0000 2.00000000 12.3710000 12.0000000 .371300000 0.0       2126 2151  120
 32840.0000 2.00000000 .549750000 .256000000 .293750000 0.0       2126 2151  121
 32940.0000 5.00000000 5.48880000 5.00000000 .488800000 0.0       2126 2151  122
 33280.0000 3.00000000 8.40890000 8.00000000 .408900000 0.0       2126 2151  123
 35470.0000 5.00000000 8.41130000 8.00000000 .411250000 0.0       2126 2151  124
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 35955.0000 5.00000000 5.48060000 5.00000000 .480570000 0.0       2126 2151  126
 36310.0000 2.00000000 20.4320000 20.0000000 .432400000 0.0       2126 2151  127
 36390.0000 4.00000000 5.43480000 5.00000000 .434750000 0.0       2126 2151  128
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 38000.0000 5.00000000 4.44530000 4.00000000 .445320000 0.0       2126 2151  130
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 41740.0000 3.00000000 10.4690000 10.0000000 .469000000 0.0       2126 2151  132
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 42790.0000 4.00000000 .608000000 .108000000 .500000000 0.0       2126 2151  134
 42900.0000 3.00000000 20.5000000 20.0000000 .500000000 0.0       2126 2151  135
 43710.0000 4.00000000 .587000000 .087000000 .500000000 0.0       2126 2151  136
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 45300.0000 2.00000000 10.3400000 10.0000000 .340000000 0.0       2126 2151  139
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 45780.0000 3.00000000 15.2060000 15.0000000 .206000000 0.0       2126 2151  141
 47310.0000 5.00000000 10.3510000 10.0000000 .351000000 0.0       2126 2151  142
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 48530.0000 5.00000000 10.4850000 10.0000000 .485000000 0.0       2126 2151  144
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 50685.0000 3.00000000 5.32200000 5.00000000 .322000000 0.0       2126 2151  148
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 91600.0000 5.00000000 50.5950000 50.0000000 .595000000 0.0       2126 2151  188
 92250.0000 3.00000000 .552000000 .052000000 .500000000 0.0       2126 2151  189
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 95250.0000 3.00000000 10.5000000 10.0000000 .500000000 0.0       2126 2151  195
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 99080.0000 5.00000000 40.6480000 40.0000000 .648000000 0.0       2126 2151  200
 99200.0000 5.00000000 50.5170000 50.0000000 .517000000 0.0       2126 2151  201
                                                                  2126 2  099999
                                                                  2126 0  0    0
 2.10450E+4 4.45700E+1          0         99          0          02126 3102    1
 8.76070E+6 8.76070E+6          0          0          1        6412126 3102    2
        641          1                                            2126 3102    3
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 9.6000E+03 3.7763E-08 4.2315E-08 4.7390E-08 5.3093E-08 5.9566E-08212633102   26
 6.6997E-08 7.5641E-08 8.5854E-08 9.8153E-08 1.1813E-07 1.4994E-07212633102   27
 2.3619E-08 3.1075E-07 1.2496E-06 1.0171E-05 2.4915E-07 8.2664E-07212633102   28
 1.5264E-06 5.1139E-06 8.6721E-06 3.1180E-06 9.5912E-07 4.3529E-07212633102   29
 2.4124E-07 1.5010E-07 3.9620E-08 8.1735E-08 2.1458E-07 7.8258E-07212633102   30
 8.3717E-08 3.4105E-08 3.3464E-07 3.7590E-07 4.4039E-08 3.8738E-07212633102   31
 1.6208E-07 4.7458E-08 5.3197E-08 5.9656E-08 6.6998E-08 7.5439E-08212633102   32
 8.5275E-08 9.6920E-08 1.1097E-07 1.3387E-07 1.7052E-07 2.6962E-08212633102   33
 3.5749E-07 1.4617E-06 1.1984E-05 2.8959E-07 9.3604E-07 1.7170E-06212633102   34
 5.7460E-06 9.7464E-06 3.5065E-06 1.0796E-06 4.9026E-07 2.7177E-07212633102   35
 1.6899E-07 4.4517E-08 9.1184E-08 2.3382E-07 8.4762E-07 9.1740E-08212633102   36
 3.7552E-08 3.6276E-07 4.0100E-07 4.7260E-08 4.1299E-07 1.7306E-07212633102   37
 5.9687E-08 6.7002E-08 7.5329E-08 8.4920E-08 9.6116E-08 1.0940E-07212633102   38
 1.2547E-07 1.5173E-07 1.9402E-07 3.0802E-08 4.1184E-07 1.7139E-06212633102   39
 1.4157E-05 3.3724E-07 1.0593E-06 1.9283E-06 6.4440E-06 1.0933E-05212633102   40
 3.9357E-06 1.2128E-06 5.5113E-07 3.0558E-07 1.8992E-07 4.9927E-08212633102   41
 1.0153E-07 2.5399E-07 9.1475E-07 1.0026E-07 4.1256E-08 3.9178E-07212633102   42
 4.2612E-07 5.0545E-08 4.3852E-07 1.8406E-07 7.5294E-08 8.4750E-08212633102   43
 9.5661E-08 1.0842E-07 1.2360E-07 1.4201E-07 1.7221E-07 2.2112E-07212633102   44
 3.5259E-08 4.7573E-07 2.0171E-06 1.6790E-05 3.9400E-07 1.1992E-06212633102   45
 2.1638E-06 7.2182E-06 1.2248E-05 4.4120E-06 1.3608E-06 6.1882E-07212633102   46
 3.4320E-07 2.1320E-07 5.5934E-08 1.1291E-07 2.7521E-07 9.8413E-07212633102   47
 1.0935E-07 4.5257E-08 4.2173E-07 4.5126E-07 5.3907E-08 4.6397E-07212633102   48
 1.9510E-07 9.5514E-08 1.0796E-07 1.2255E-07 1.3994E-07 1.6110E-07212633102   49
 1.9595E-07 2.5274E-07 4.0499E-08 5.5184E-07 2.3869E-06 2.0025E-05212633102   50
 4.6255E-07 1.3596E-06 2.4280E-06 8.0814E-06 1.3713E-05 4.9431E-06212633102   51
 1.5261E-06 6.9450E-07 3.8530E-07 2.3925E-07 6.2642E-08 1.2552E-07212633102   52
 2.9764E-07 1.0560E-06 1.1910E-07 4.9607E-08 4.5274E-07 4.7649E-07212633102   53
 5.7365E-08 4.8940E-07 2.0621E-07 1.2221E-07 1.3895E-07 1.5897E-07212633102   54
 1.8340E-07 2.2383E-07 2.9017E-07 4.6746E-08 6.4391E-07 2.8449E-06212633102   55
 2.4065E-05 5.4663E-07 1.5454E-06 2.7264E-06 9.0492E-06 1.5355E-05212633102   56
 5.5386E-06 1.7117E-06 7.7963E-07 4.3269E-07 2.6858E-07 7.0184E-08212633102   57
 1.3958E-07 3.2147E-07 1.1307E-06 1.2963E-07 5.4373E-08 4.8491E-07212633102   58
 5.0188E-07 6.0943E-08 5.1483E-07 2.1742E-07 1.5829E-07 1.8148E-07212633102   59
 2.0988E-07 2.5709E-07 3.3520E-07 5.4325E-08 7.5728E-07 3.4230E-06212633102   60
 2.9203E-05 6.5165E-07 1.7636E-06 3.0663E-06 1.0141E-05 1.7206E-05212633102   61
 6.2104E-06 1.9216E-06 8.7602E-07 4.8642E-07 3.0184E-07 7.8726E-08212633102   62
 1.5538E-07 3.4692E-07 1.2085E-06 1.4108E-07 5.9642E-08 5.1839E-07212633102   63
 5.2752E-07 6.4673E-08 5.4034E-07 2.2877E-07 2.0856E-07 2.4186E-07212633102   64
 2.9754E-07 3.9044E-07 6.3705E-08 8.9987E-07 4.1684E-06 3.5878E-05212633102   65
 7.8568E-07 2.0238E-06 3.4571E-06 1.1381E-05 1.9305E-05 6.9733E-06212633102   66
 2.1604E-06 9.8596E-07 5.4781E-07 3.3988E-07 8.8484E-08 1.7330E-07212633102   67
 3.7429E-07 1.2899E-06 1.5365E-07 6.5522E-08 5.5334E-07 5.5353E-07212633102   68
 6.8596E-08 5.6597E-07 2.4030E-07 2.8137E-07 3.4784E-07 4.5981E-07212633102   69
 7.5598E-08 1.0838E-06 5.1546E-06 4.4775E-05 9.6111E-07 2.3401E-06212633102   70
 3.9112E-06 1.2800E-05 2.1702E-05 7.8454E-06 2.4343E-06 1.1124E-06212633102   71
 6.1856E-07 3.8377E-07 9.9739E-08 1.9382E-07 4.0395E-07 1.3752E-06212633102   72
 1.6756E-07 7.2161E-08 5.8994E-07 5.8000E-07 7.2761E-08 5.9177E-07212633102   73
 2.5209E-07 4.3328E-07 5.7922E-07 9.6332E-08 1.4114E-06 6.9676E-06212633102   74
 6.1270E-05 1.2794E-06 2.8602E-06 4.6076E-06 1.4919E-05 2.5270E-05212633102   75
 9.1462E-06 2.8447E-06 1.3028E-06 7.2551E-07 4.5029E-07 1.1680E-07212633102   76
 2.2470E-07 4.4550E-07 1.4893E-06 1.8766E-07 8.2002E-08 6.3885E-07212633102   77
 6.1425E-07 7.8482E-08 6.2455E-07 2.6740E-07 7.8714E-07 1.3309E-07212633102   78
 2.0096E-06 1.0413E-05 9.2939E-05 1.8739E-06 3.7044E-06 5.6069E-06212633102   79
 1.7800E-05 3.0087E-05 1.0910E-05 3.4069E-06 1.5661E-06 8.7465E-07212633102   80
 5.4357E-07 1.4078E-07 2.6761E-07 4.9614E-07 1.6146E-06 2.1370E-07212633102   81
 9.5360E-08 6.9271E-07 6.4845E-07 8.5139E-08 6.5563E-07 2.8290E-07212633102   82
 2.2866E-08 3.5517E-07 1.9201E-06 1.7342E-05 3.3943E-07 5.9449E-07212633102   83
 8.3507E-07 2.5821E-06 4.3514E-06 1.5812E-06 4.9629E-07 2.2925E-07212633102   84
 1.2853E-07 8.0069E-08 2.0730E-08 3.9037E-08 6.7924E-08 2.1488E-07212633102   85
 2.9936E-08 1.3649E-08 9.2255E-08 8.4481E-08 1.1418E-08 8.4861E-08212633102   86
 3.6933E-08 5.7820E-06 3.3369E-05 3.0616E-04 5.7305E-06 8.0793E-06212633102   87
 9.4646E-06 2.7073E-05 4.5174E-05 1.6515E-05 5.2597E-06 2.4645E-06212633102   88
 1.3982E-06 8.7856E-07 2.2830E-07 4.2504E-07 6.6183E-07 1.9753E-06212633102   89
 3.0563E-07 1.4544E-07 8.5161E-07 7.5803E-07 1.0883E-07 7.4987E-07212633102   90
 3.3273E-07 2.0963E-04 1.9379E-03 3.4155E-05 3.4355E-05 2.3371E-05212633102   91
 4.3038E-05 6.6431E-05 2.5386E-05 8.9490E-06 4.5915E-06 2.7974E-06212633102   92
 1.8542E-06 4.9895E-07 9.2670E-07 1.0662E-06 2.4945E-06 5.8495E-07212633102   93
 3.1928E-07 1.1255E-06 9.7470E-07 1.7988E-07 8.8768E-07 4.3584E-07212633102   94
 1.8310E-02 3.2576E-04 2.8938E-04 1.3803E-04 1.1212E-04 1.2320E-04212633102   95
 5.7938E-05 2.8618E-05 1.8113E-05 1.2562E-05 9.0537E-06 2.5688E-06212633102   96
 4.8481E-06 3.9722E-06 5.1392E-06 2.7835E-06 1.7502E-06 2.8066E-06212633102   97
 2.5018E-06 7.5487E-07 1.7106E-06 1.1796E-06 6.0844E-06 6.9310E-06212633102   98
 6.2869E-06 1.5456E-05 2.5212E-05 9.3414E-06 3.0736E-06 1.4842E-06212633102   99
 8.6228E-07 5.5061E-07 1.4373E-07 2.5891E-07 2.7967E-07 6.2654E-07212633102  100
 1.5322E-07 8.3156E-08 2.7751E-07 2.2733E-07 4.3656E-08 2.0351E-07212633102  101
 1.0156E-07 2.1420E-05 3.9156E-05 1.3226E-04 2.2500E-04 8.1404E-05212633102  102
 2.5305E-05 1.1547E-05 6.3848E-06 3.9080E-06 9.8334E-07 1.7063E-06212633102  103
 1.7295E-06 3.7268E-06 9.3236E-07 4.9759E-07 1.6066E-06 1.2634E-06212633102  104
 2.4505E-07 1.1182E-06 5.5889E-07 8.2376E-05 2.8835E-04 4.9153E-04212633102  105
 1.7730E-04 5.4890E-05 2.4924E-05 1.3711E-05 8.3456E-06 2.0843E-06212633102  106
 3.5510E-06 3.0519E-06 5.2665E-06 1.7699E-06 9.9046E-07 2.3172E-06212633102  107
 1.8166E-06 4.2118E-07 1.4473E-06 8.0185E-07 1.0186E-03 1.7344E-03212633102  108
 6.2471E-04 1.9346E-04 8.7819E-05 4.8271E-05 2.9334E-05 7.3006E-06212633102  109
 1.2276E-05 8.9112E-06 1.0675E-05 5.6377E-06 3.3209E-06 5.0173E-06212633102  110
 4.1306E-06 1.2302E-06 2.6350E-06 1.8117E-06 2.9922E-03 1.0875E-03212633102  111
 3.3573E-04 1.5214E-04 8.3555E-05 5.0747E-05 1.2622E-05 2.1180E-05212633102  112
 1.4928E-05 1.6361E-05 9.5985E-06 5.7041E-06 7.8220E-06 6.5105E-06212633102  113
 2.0601E-06 3.8693E-06 2.8536E-06 3.9777E-04 1.2262E-04 5.5543E-05212633102  114
 3.0517E-05 1.8559E-05 4.6303E-06 7.8604E-06 6.4671E-06 1.0325E-05212633102  115
 3.8327E-06 2.1689E-06 4.3923E-06 3.1927E-06 8.5061E-07 2.3383E-06212633102  116
 1.4256E-06 3.7889E-05 1.7207E-05 9.4876E-06 5.8048E-06 1.4671E-06212633102  117
 2.6099E-06 3.3811E-06 9.0932E-06 1.6277E-06 7.8228E-07 3.3150E-06212633102  118
 1.9151E-06 3.7767E-07 1.8012E-06 8.8737E-07 7.8447E-06 4.3534E-06212633102  119
 2.6974E-06 7.0139E-07 1.3760E-06 3.0715E-06 1.0712E-05 1.2243E-06212633102  120
 4.6912E-07 3.4699E-06 1.6492E-06 2.7246E-07 1.7667E-06 7.9571E-07212633102  121
 2.4461E-06 1.5543E-06 4.2703E-07 9.8619E-07 3.5720E-06 1.3965E-05212633102  122
 1.2612E-06 3.8683E-07 3.9869E-06 1.5685E-06 2.4285E-07 1.8345E-06212633102  123
 7.9547E-07 1.0380E-06 3.1496E-07 9.1294E-07 4.7837E-06 1.9682E-05212633102  124
 1.5729E-06 3.9925E-07 4.7579E-06 1.5139E-06 2.3795E-07 1.9312E-06212633102  125
 8.2324E-07 1.1255E-07 4.2344E-07 2.8478E-06 1.1982E-05 8.9628E-07212633102  126
 1.9429E-07 2.2608E-06 5.5343E-07 9.5443E-08 7.8940E-07 3.3449E-07212633102  127
 2.0742E-06 1.6466E-05 6.9671E-05 4.9909E-06 9.2554E-07 7.9133E-06212633102  128
 1.3090E-06 2.8949E-07 2.2393E-06 9.5624E-07 1.4433E-04 5.9024E-04212633102  129
 4.0501E-05 6.5832E-06 1.5000E-05 2.4583E-06 7.9553E-07 3.1192E-06212633102  130
 1.5155E-06 2.5686E-03 1.8228E-04 2.8441E-05 3.1009E-05 8.8389E-06212633102  131
 2.6695E-06 5.5532E-06 3.2812E-06 1.3371E-05 2.5234E-06 4.0262E-05212633102  132
 6.1624E-06 5.0010E-07 4.1452E-06 1.7801E-06 1.8179E-06 1.4569E-04212633102  133
 5.2352E-05 5.4077E-08 4.7205E-06 1.9613E-06 1.7427E-02 9.9573E-03212633102  134
 8.4587E-05 7.9004E-06 3.3483E-06 9.0737E-03 8.8884E-05 4.9176E-05212633102  135
 2.2947E-05 4.7205E-06 4.3502E-05 1.7438E-05 4.8803E-04 1.9935E-04212633102  136
 8.4828E-05                                                       212633102  137
 0.0        0.0                 1          5         10          4212633102  138
 1.1000E+04 1.1500E+04 1.2000E+04 1.2750E+04 3.0436E-05 1.0200E-04212633102  139
 7.2626E-06 3.8928E-04 2.8587E-05 2.1192E-06                      212633102  140
 0.0        0.0                 1          5         15          5212633102  141
 2.3000E+04 2.4000E+04 2.5500E+04 2.7000E+04 2.8000E+04 2.0221E-03212633102  142
 1.1416E-04 2.6389E-07 8.7044E-08 1.0575E-03 8.1002E-07 1.7944E-07212633102  143
 6.8298E-04 3.0746E-05 9.1324E-05                                 212633102  144
 0.0        0.0                 0          1         12          6212633102  145
 3.4000E+04 1.5819E-05 3.6000E+04 4.9680E-12 3.8000E+04 6.5496E-05212633102  146
 4.0000E+04 4.8828E-05 4.2500E+04 1.6762E-05 4.5000E+04 0.0000E+00212633102  147
 0.0        0.0                 0          1         12          6212633102  148
 6.9000E+04 1.6282E-05 7.2000E+04 2.4062E-09 7.6000E+04 2.6452E-08212633102  149
 8.0000E+04 1.7513E-08 8.4000E+04 2.4018E-04 8.8000E+04 0.0000E+00212633102  150
                                                                  212633  099999
                                                                  2126 0  0    0
                                                                     0 0  0    0
 2.20460E+4 4.55579E+1          0          0         34         102225 1451    1
 0.0        0.0                 0          0          0          62225 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022225 1451    3
 3.00000E+2 0.0                 1          0        233          62225 1451    4
 22-Ti- 46 FEI        EVAL-Jan02 K.I.Zolotarev                    2225 1451    5
                      DIST-Feb2004                                2225 1451    6
----IRDF-2002         MATERIAL 2225                               2225 1451    7
-----INCIDENT NEUTRON DATA                                        2225 1451    8
------ENDF-6 FORMAT                                               2225 1451    9
***************************************************************** 2225 1451   10
 22-TI- 46 FEI        EVAL-Jan02 K.I.Zolotarev                    2225 1451   11
                      DIST-Feb02                       20020203   2225 1451   12
----BROND-2           MATERIAL 2225                               2225 1451   13
-----INCIDENT NEUTRON DATA                                        2225 1451   14
------ENDF-6 FORMAT                                               2225 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    2225 1451   16
***************************************************************** 2225 1451   17
Author  of evaluation: K.I.Zolotarev                              2225 1451   18
***************************************************************** 2225 1451   19
MF=3                                                              2225 1451   20
MT= 16 -(n,2n) cross section                                      2225 1451   21
-------------------------------------                             2225 1451   22
    Excitation function for the  Ti-46(n,2n)Ti-45 reaction in the 2225 1451   23
energy region from threshold to 20 MeV was evaluated by  means of 2225 1451   24
statistical analysis  of experimental cross section data [1-18].  2225 1451   25
    All experimental data were renormalized to  the new standards 2225 1451   26
for monitor reactions cross sections and decay data. In the measu-2225 1451   27
rements [5,14-16] uncertainties were increased until the data had 2225 1451   28
become mutually consistent.                                       2225 1451   29
    The final procedure of evaluation the Ti-46(n,2n)Ti-45  reac- 2225 1451   30
tion excitation function  has been carried out  within the frame- 2225 1451   31
work of generalized least squares method. Statistical analysis of 2225 1451   32
input cross section data  was carried out by means of PADE-2 code 2225 1451   33
[19].  Rational function was used as the model function [20].     2225 1451   34
    The evaluated  Ti-46(n,2n)Ti-45  excitation function averaged 2225 1451   35
on U-235 thermal neutron fission spectrum [21] and Cf-252 sponta- 2225 1451   36
neous fission neutron spectrum [22] gives the following values :  2225 1451   37
  2225 1451   38
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  2225 1451   39
  2225 1451   40
 U-235 neutron fission    0.0044686                             2225 1451   41
  2225 1451   42
 CF-252 spont. fission    0.011982        0.093 +- 0.031 [23]   2225 1451   43
  2225 1451   44
                                                                  2225 1451   45
MT=103 -(n,p) cross section                                       2225 1451   46
-------------------------------------                             2225 1451   47
    Excitation function for the  Ti-46(n,p)Sc-46m+g  reaction in  2225 1451   48
the energy region from threshold to 20 MeV was evaluated by means 2225 1451   49
of statistical analysis of experimental cross section data [6,17, 2225 1451   50
24-38] and data from GNASH calculation [39].                      2225 1451   51
    Analyzed microscopic experimental data  were  renormalized to 2225 1451   52
the new recommended standards for monitor reaction cross sections 2225 1451   53
and decay data. All experiments performed with Ti-natural samples 2225 1451   54
were corrected for the contribution of the Ti-47(n,np+pn)Sc-46m+g 2225 1451   55
and  Ti-47(n,d)Sc-46m+g  reactions. Total cross section for these 2225 1451   56
reactions were taken from ref.[40].  Experimental data  from ref. 2225 1451   57
[6,27] were used partially. Data of Bormann et al. [6] were taken 2225 1451   58
only for 14.1 MeV point. In the work of Lukic and Carroll [27] it 2225 1451   59
were used data measured relative Fe56(n,p)Mn56 and Al27(n,a)Na24  2225 1451   60
monitor reactions. These data were renormalized to the cross sec- 2225 1451   61
sections obtained in the ref.[28]. Data of Smith and Meadows [28] 2225 1451   62
measured  with using  D(d,n)He3 neutron source  were renormalized 2225 1451   63
in the energy range  6.996-9.950 MeV to the preliminary evaluated 2225 1451   64
integral of cross section from new experimental data [34,37,38].  2225 1451   65
    Experimental cross section  data [8] , [41-46] were  rejected 2225 1451   66
due to their discrepancy  with the main bulk of experimental data 2225 1451   67
[6,17,24-38] and data from theoretical model calculation.         2225 1451   68
    Statistical analysis of input cross section data was carried  2225 1451   69
out by means of PADE-2 code [19].  Rational function was used as  2225 1451   70
the model function [20].                                          2225 1451   71
    U-235 thermal fission [21]  and  Cf-252  spontaneous fission  2225 1451   72
neutron spectra [22] averaged cross sections calculated from the  2225 1451   73
evaluated  Ti-46(n,p)Sc-46m+g  reaction excitation function  are  2225 1451   74
the following:                                                    2225 1451   75
  2225 1451   76
   TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)   2225 1451   77
  2225 1451   78
U-235 neutron fission      11.447        11.57 +- 0.37  [47]    2225 1451   79
                                         11.51 +- 0.40  [48]    2225 1451   80
                                         11.55 +- 0.20  [49]    2225 1451   81
  2225 1451   82
CF-252 spont. fission      13.818        14.20 +- 0.24  [50]    2225 1451   83
                                         14.07 +- 0.25  [51]    2225 1451   84
  2225 1451   85
                                                                  2225 1451   86
MF=33                                                             2225 1451   87
MT= 16 -(n,2n) cross section cov. matrix                          2225 1451   88
----------------------------------------                          2225 1451   89
    Uncertainties in the evaluated  excitation function  for the  2225 1451   90
reaction Ti-46(n,2n)Ti-45 are given in the form of relative cova- 2225 1451   91
riance matrix for the 17-neutron energy groups (LB=5). Covariance 2225 1451   92
matrix  of  uncertainties  was  calculated  simultaneously  with  2225 1451   93
recommended cross section data by means of PADE-2 code.           2225 1451   94
    Eigenvalues  of the  6-th digits  relative covariance matrix  2225 1451   95
given in the 33-file are the following:                           2225 1451   96
                                                                  2225 1451   97
    2.26418E-07    2.55017E-07    2.97541E-07    3.62667E-07      2225 1451   98
    4.74369E-07    6.90723E-07    1.00928E-06    1.38635E-06      2225 1451   99
    2.05902E-06    3.42154E-06    6.73918E-06    1.77794E-05      2225 1451  100
    1.16721E-04    5.82882E-03    7.49965E-03    2.28734E-02      2225 1451  101
    4.20028E-02                                                   2225 1451  102
                                                                  2225 1451  103
MT=103 -(n,p) cross section cov. matrix                           2225 1451  104
----------------------------------------                          2225 1451  105
    Uncertainties in the evaluated  excitation function  for the  2225 1451  106
reaction Ti-46(n,p)Sc-45m+g are given in the form of relative co- 2225 1451  107
variance matrix for the 31-neutron energy groups (LB=5).  Covari- 2225 1451  108
ance matrix of uncertainties  was calculated simultaneously  with 2225 1451  109
recommended cross section data by means of PADE-2 code.           2225 1451  110
    Eigenvalues  of the  6-th digits  relative covariance matrix  2225 1451  111
given in the 33-file are the following:                           2225 1451  112
                                                                  2225 1451  113
    3.10934E-07    3.16123E-07    3.24666E-07    3.37022E-07      2225 1451  114
    3.51765E-07    3.72727E-07    3.91781E-07    4.23365E-07      2225 1451  115
    4.47112E-07    4.91264E-07    5.29779E-07    6.15458E-07      2225 1451  116
    6.75168E-07    7.93660E-07    9.79888E-07    1.29384E-06      2225 1451  117
    1.98373E-06    3.65835E-06    2.36258E-04    5.76816E-04      2225 1451  118
    7.66259E-04    1.00346E-03    1.10942E-03    1.43365E-03      2225 1451  119
    2.89439E-03    3.32523E-03    4.20534E-03    7.47772E-03      2225 1451  120
    1.06722E-02    1.67016E-02    7.87709E-02                     2225 1451  121
                                                                  2225 1451  122
 References :                                                     2225 1451  123
 1. A.Poularikas, R.W.Fink  Physical Review, v.115, p.989, 1959   2225 1451  124
 2. R.J.Prestwood,B.P.Bayhurst  Phys. Rev, v.121, p.1438,Mar.1961 2225 1451  125
 3. L.A.Rayburn  Phys. Rev., v.122, p.168, 1961                   2225 1451  126
 3. M.Cevolani, S.Petralia Nuovo Cimento, v.26, p.1328, Dec. 1962 2225 1451  127
 5. J.E.Strain, W.J.Ross  Report ORNL-3672, January 1965          2225 1451  128
 6. M.Bormann et al. Nuclear Physics, v.63, p.438, March 1965     2225 1451  129
 7. J.Csikai  Progress Report EANDC-50S, v.2, p.102, July 1965    2225 1451  130
 8. H.L.Pai  Canadian J. of Physics, v.44, p.2337, 1966           2225 1451  131
 9. G.N.Maslov et al.  Yadernye Konstanty, No.9, p.50, 1972       2225 1451  132
10. J.Araminowicz, J.Dresler  Report INR-1464, p.14, May 1973     2225 1451  133
11. A.Paulsen et al.  Atomkernenergie , v.26, p.34, August 1975   2225 1451  134
12. S.M.Qaim, N.I.Molla  Proc of 9th Symposium on Fusion Technolo-2225 1451  135
    gy, Garmisch, Germany, 14-18 June 1976, p.589                 2225 1451  136
13. R.A.Sigg  J. Diss. Abst., v.B37, p.2237, November 1976        2225 1451  137
14. J.Csikai  Proc. of Int. Conf. on Nuclear Data for Science and 2225 1451  138
    Technology, Antwerp, 6-10 September 1982, p.414, Reidel Publ. 2225 1451  139
    Company, 1983                                                 2225 1451  140
15. N.T.Molla et al. Progress Report INDC(BAN)-002, p.1, Feb.1983 2225 1451  141
16. Zhou Muyao et al.  Chinese J. of Nucl. Phys., v.9, p.34, 1987 2225 1451  142
17. Y.Ikeda et al.  Report JAERI-1312, March 1988                 2225 1451  143
18. P.M.Dighe e.a. Indian J. of Pure and Applied Physics, v.29,   2225 1451  144
    p.665, October 1991                                           2225 1451  145
19. S.A.Badikov et.al.  Preprint FEI-1686, Obninsk, 1985          2225 1451  146
20. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2225 1451  147
    st's Meeting on Evaluation and Processing of Covariance Data, 2225 1451  148
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  2225 1451  149
21. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2225 1451  150
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              2225 1451  151
22. W.Mannhart   IAEA-TECDOC-410, p.158, 1987                     2225 1451  152
23. J.Csikai, Z.Dezso   Proc. of 4th All Union Conf. on Neutron   2225 1451  153
    Physics, Kiev, 18-22 April 1977, v.3, p.32                    2225 1451  154
24. H.Liskien, A.Paulsen  Nucl. Phys., v.63, p.393, March 1965    2225 1451  155
25. V.N.Levkovskij et al.  Yadernaja Fizika (Sov.), v.10, n.1,    2225 1451  156
    p.44, July 1969                                               2225 1451  157
26. S.K.Ghorai et al.  J. Nucl. Energ., v.25, p.319, August 1971  2225 1451  158
27. Y.Lukic, E.E.Carroll  Nucl. Sci. Eng., v.43, p.233, 1971      2225 1451  159
28. D.L.Smith, J.W.Meadows  Nucl. Sci. Eng., v.58, p.314, 1975    2225 1451  160
29. Lu Hamlin et al.  Chinese J. of Atomic Energy Sci. Technology,2225 1451  161
    v.9, no.2, p.113, May 1975                                    2225 1451  162
30. K.Kayashima et al. Prog. Report NEANDC(J)-61U, p.94, Sep.1979 2225 1451  163
31. M.Viennot et al.  Proc of Int. Conference on Nuclear Data for 2225 1451  164
    Science and Technology, Antwerp, 6-10 September 1982, p.406   2225 1451  165
32. N.I.Molla et al.  Progress Report INDC(BAN)-003, Sept. 1986   2225 1451  166
33. Lu Hanlin et al.  Report INDC(CPR)-16, IAEA, August 1989      2225 1451  167
34. N.I.Molla, S.M.Qaim, M.Uhl  Phys. Rev. C, v.42, n.4, p.1540,  2225 1451  168
    October 1990                                                  2225 1451  169
35. M.Viennot et al.  Nucl. Sci. Eng., v.108, p.289, July 1991    2225 1451  170
36. Yuan Junqian e.a.  High Energy Physics and Nucl.Phys.(China), 2225 1451  171
    v.16, n.1, p.57, January 1992                                 2225 1451  172
37. J.W.Meadows, D.L.Smith, L.R.Greenwood, R.C.Haight, Y.Ikeda,   2225 1451  173
    C.Konno  Annals of Nuclear Energy, v.23, p.877, July 1996     2225 1451  174
38. Lu Hanlin et al.  Report INDC(CPR)-045, IAEA, October 1998    2225 1451  175
39. P.G.Young, E.D.Arthur  A Preequilibrium Statistical Nuclear   2225 1451  176
    Model Code for Calculation of Cross Section and Emission      2225 1451  177
    Spectra. Report LA-6947, Los Alamos, 1977 ;                   2225 1451  178
    E.L.Trykiv, G.Ya.Tertychnyi  Private communication, IPPE,     2225 1451  179
    Obninsk, May 1999                                             2225 1451  180
40. K.I.Zolotrarev  RRDF-2002, MAT=2222, eval. January 2002       2225 1451  181
41. D.L.Allan  Nucl. Phys., v.24, p.274, April 1961               2225 1451  182
42. W.G.Cross, H.L.Pai Prog. Report EANDC(CAN)-16, p.1, Jan. 1963 2225 1451  183
43. S.M.Qaim, N.I.Molla  Nucl. Phys., v.A283, p.269, June 1977    2225 1451  184
44. I.Ribansky, S.Gmuca  J. Phys. G, v.9, p.1537, December 1983   2225 1451  185
45. R.Pepelnik et al.  Progress Report, NEANDC(E)-262U,(5), p.32, 2225 1451  186
    June 1985                                                     2225 1451  187
46. I.Kimura, K.Kobayashi  Nucl. Sci. Eng., v.106, p.332, 1990    2225 1451  188
47. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 2225 1451  189
    Washington D.C., 25-28 April 1989, v.2, p.923                 2225 1451  190
48. W.Mannhart  Proc. 5-th ASTM-EUR. Symp. on Reactor Dosimetry,  2225 1451  191
    Geesthacht, FRG, September 24-28, 1984, Vol.2, p.813, 1985    2225 1451  192
49. W.Mannhart  Progress Report INDC(Ger)-045, pp.40-43, 1999     2225 1451  193
50. W.Mannhart  Handbook on Nuclear Activation Data . IAEA Tech-  2225 1451  194
    nical Report series No.273, p.413, 1987                       2225 1451  195
51. W.Mannhart  Validation of Differential Cross Sections with    2225 1451  196
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2225 1451  197
    September 2002                                                2225 1451  198
***************************************************************** 2225 1451  199
 The Q values and threshold energies were updated prior to pro-   2225 1451  200
 cessing through the codes to comply with the values obtained     2225 1451  201
 using the NNDC calculation program which is based on the 1995    2225 1451  202
 Update to the Atomic mass Evaluation.                            2225 1451  203
                                                                  2225 1451  204
 File 2 added to the pointwise file containing only the effective 2225 1451  205
 scattering radius with no resonance parameters given.            2225 1451  206
 Taken from ENDF/B-VI                                             2225 1451  207
                                                                  2225 1451  208
 Psuedo Threshold of 0.0 added at 2.1E+6 ev to MF/MT=3/103        2225 1451  209
 in original evaluation                                           2225 1451  210
                                                                  2225 1451  211
***************************************************************** 2225 1451  212
 ***************** Program LINEAR (VERSION 2002-1) ***************2225 1451  213
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2225 1451  214
 Data Linearized to Within an Accuracy of .100000000 per-cent     2225 1451  215
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2225 1451  216
 Data Doppler Broadened to 300.000000 Kelvin                      2225 1451  217
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2225 1451  218
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2225 1451  219
 ***************** Program FIXUP (Version 2002-1) ****************2225 1451  220
 Corrected ZA/AWR in All Sections-----------------------------Yes 2225 1451  221
 Corrected Thresholds-----------------------------------------Yes 2225 1451  222
 Extended Cross Sections to 20 MeV----------------------------No  2225 1451  223
 Allow Cross Section Deletion---------------------------------No  2225 1451  224
 Allow Cross Section Reconstruction---------------------------No  2225 1451  225
 Make All Cross Sections Non-Negative-------------------------Yes 2225 1451  226
 Delete Energies Not in Ascending Order-----------------------Yes 2225 1451  227
 Deleted Duplicate Points-------------------------------------Yes 2225 1451  228
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2225 1451  229
 Check for Legal MF/MT Numbers--------------------------------Yes 2225 1451  230
 Allow Creation of Missing Sections---------------------------No  2225 1451  231
 Allow Insertion of Energy Points-----------------------------No  2225 1451  232
 Create Uniform Energy Grid-----------------------------------No  2225 1451  233
 Delete Section if Cross Section =0 at All Energies-----------Yes 2225 1451  234
 ***************** Program GROUPIE (VERSION 2002-1) **************2225 1451  235
 Unshielded Group Averages Using  640 Groups                      2225 1451  236
 Weighting Spectrum: Flat (Constant) Spectrum                     2225 1451  237
                                1        451        243          12225 1451  238
                                2        151          4          12225 1451  239
                                3         16         26          12225 1451  240
                                3        103         63          12225 1451  241
                               33         16         35          12225 1451  242
                               33        103         97          12225 1451  243
                                                                  2225 1  099999
                                                                  2225 0  0    0
 2.20460E+4 4.55578E+1          0          0          1          02225 2151    1
 2.204600+4 1.000000+0          0          0          1          02225 2151    2
 1.000000-5 1.000000+5          0          0          0          02225 2151    3
 0.000000+0 0.573300+0          0          0          0          02225 2151    4
                                                                  2225 2  099999
                                                                  2225 0  0    0
 2.20460E+4 4.55579E+1          0          0          0          02225 3 16    1
-1.31898E+7-1.31898E+7          0          0          1         672225 3 16    2
         67          1                                            2225 3 16    3
 13400000.0 5.44722E-6 13500000.0 .000269054 13600000.0 .0013538942225 3 16    4
 13700000.0 .003167185 13800000.0 .005539635 13900000.0 .0084628702225 3 16    5
 14000000.0 .011885800 14100000.0 .015756100 14200000.0 .0200212002225 3 16    6
 14300000.0 .024629400 14400000.0 .029530600 14500000.0 .0346768502225 3 16    7
 14600000.0 .040022950 14700000.0 .045526750 14800000.0 .0511660252225 3 16    8
 14900000.0 .056872075 15000000.0 .062608313 15100000.0 .0683747382225 3 16    9
 15200000.0 .074141163 15300000.0 .079907588 15400000.0 .0855952332225 3 16   10
 15500000.0 .091204100 15600000.0 .096812967 15700000.0 .1022853332225 3 16   11
 15800000.0 .107621200 15900000.0 .112957067 16000000.0 .1181235002225 3 16   12
 16100000.0 .123120500 16200000.0 .128117500 16300000.0 .1329310002225 3 16   13
 16400000.0 .137561000 16500000.0 .142191000 16600000.0 .1466356672225 3 16   14
 16700000.0 .150895000 16800000.0 .155154333 16900000.0 .1592341672225 3 16   15
 17000000.0 .163134500 17100000.0 .167034833 17200000.0 .1707660002225 3 16   16
 17300000.0 .174328000 17400000.0 .177890000 17500000.0 .1812951672225 3 16   17
 17600000.0 .184543500 17700000.0 .187791833 17800000.0 .1908743752225 3 16   18
 17900000.0 .193791125 18000000.0 .196707875 18100000.0 .1996246252225 3 16   19
 18200000.0 .202373250 18300000.0 .204953750 18400000.0 .2075342502225 3 16   20
 18500000.0 .210114750 18600000.0 .212532000 18700000.0 .2147860002225 3 16   21
 18800000.0 .217040000 18900000.0 .219294000 19000000.0 .2215480002225 3 16   22
 19100000.0 .223648400 19200000.0 .225595200 19300000.0 .2275420002225 3 16   23
 19400000.0 .229488800 19500000.0 .231435600 19600000.0 .2332651252225 3 16   24
 19700000.0 .234977375 19800000.0 .236689625 19900000.0 .2384018752225 3 16   25
 20000000.0 0.0                                                   2225 3 16   26
                                                                  2225 3  099999
 2.20460E+4 4.55579E+1          0          0          0          02225 3103    1
-1.58430E+6-1.58430E+6          0          0          1        1802225 3103    2
        180          1                                            2225 3103    3
 2100000.00 3.42206E-6 2200000.00 1.02662E-5 2300000.00 1.71103E-52225 3103    4
 2400000.00 2.39544E-5 2500000.00 3.98904E-5 2600000.00 9.93846E-52225 3103    5
 2700000.00 .000237889 2800000.00 .000478634 2900000.00 .0008521572225 3103    6
 3000000.00 .001398970 3100000.00 .002172540 3200000.00 .0032406352225 3103    7
 3300000.00 .004678875 3400000.00 .006545195 3500000.00 .0088332052225 3103    8
 3600000.00 .011449050 3700000.00 .014282900 3800000.00 .0173307502225 3103    9
 3900000.00 .020716350 4000000.00 .024597800 4100000.00 .0290779002225 3103   10
 4200000.00 .034170000 4300000.00 .039792900 4400000.00 .0457663252225 3103   11
 4500000.00 .051856975 4600000.00 .057775050 4700000.00 .0632341002225 3103   12
 4800000.00 .068060950 4900000.00 .072219050 5000000.00 .0757965502225 3103   13
 5100000.00 .079116450 5200000.00 .082497900 5300000.00 .0861876502225 3103   14
 5400000.00 .090482100 5500000.00 .095555300 5600000.00 .1014841502225 3103   15
 5700000.00 .108255000 5800000.00 .115777000 5900000.00 .1239030002225 3103   16
 6000000.00 .132481167 6100000.00 .141251500 6200000.00 .1500218332225 3103   17
 6300000.00 .158677500 6400000.00 .167038500 6500000.00 .1749920002225 3103   18
 6600000.00 .182459000 6700000.00 .189393500 6800000.00 .1957795002225 3103   19
 6900000.00 .201623000 7000000.00 .206947500 7100000.00 .2116860002225 3103   20
 7200000.00 .216090000 7300000.00 .220127250 7400000.00 .2237977502225 3103   21
 7500000.00 .227143500 7600000.00 .230164500 7700000.00 .2331855002225 3103   22
 7800000.00 .235943125 7900000.00 .238437375 8000000.00 .2409316252225 3103   23
 8100000.00 .243425875 8200000.00 .245762125 8300000.00 .2479403752225 3103   24
 8400000.00 .250118625 8500000.00 .252296875 8600000.00 .2544751252225 3103   25
 8700000.00 .256653375 8800000.00 .258831625 8900000.00 .2610098752225 3103   26
 9000000.00 .263188125 9100000.00 .265366375 9200000.00 .2675446252225 3103   27
 9300000.00 .269722875 9400000.00 .271901125 9500000.00 .2740793752225 3103   28
 9600000.00 .276257625 9700000.00 .278435875 9800000.00 .2804955832225 3103   29
 9900000.00 .282436750 10000000.0 .284377917 10100000.0 .2863190832225 3103   30
 10200000.0 .288260250 10300000.0 .290201417 10400000.0 .2919556252225 3103   31
 10500000.0 .293522875 10600000.0 .295090125 10700000.0 .2966573752225 3103   32
 10800000.0 .297992875 10900000.0 .299096625 11000000.0 .3002003752225 3103   33
 11100000.0 .301304125 11200000.0 .302152667 11300000.0 .3027460002225 3103   34
 11400000.0 .303339333 11500000.0 .303725000 11600000.0 .3039030002225 3103   35
 11700000.0 .303857833 11800000.0 .303589500 11900000.0 .3033211672225 3103   36
 12000000.0 .302775333 12100000.0 .301952000 12200000.0 .3011286672225 3103   37
 12300000.0 .300027833 12400000.0 .298649500 12500000.0 .2972711672225 3103   38
 12600000.0 .295628333 12700000.0 .293721000 12800000.0 .2918136672225 3103   39
 12900000.0 .289664667 13000000.0 .287274000 13100000.0 .2848833332225 3103   40
 13200000.0 .282253250 13300000.0 .279383750 13400000.0 .2765142502225 3103   41
 13500000.0 .273644750 13600000.0 .270544600 13700000.0 .2672138002225 3103   42
 13800000.0 .263883000 13900000.0 .260552200 14000000.0 .2572214002225 3103   43
 14100000.0 .253720375 14200000.0 .250049125 14300000.0 .2463778752225 3103   44
 14400000.0 .242706625 14500000.0 .239035375 14600000.0 .2353641252225 3103   45
 14700000.0 .231692875 14800000.0 .228021625 14900000.0 .2243471882225 3103   46
 15000000.0 .220669563 15100000.0 .216991938 15200000.0 .2133143132225 3103   47
 15300000.0 .209636688 15400000.0 .205959063 15500000.0 .2022814382225 3103   48
 15600000.0 .198603813 15700000.0 .195037600 15800000.0 .1915828002225 3103   49
 15900000.0 .188128000 16000000.0 .184673200 16100000.0 .1812184002225 3103   50
 16200000.0 .177889500 16300000.0 .174686500 16400000.0 .1714835002225 3103   51
 16500000.0 .168280500 16600000.0 .165077500 16700000.0 .1619997502225 3103   52
 16800000.0 .159047250 16900000.0 .156094750 17000000.0 .1531422502225 3103   53
 17100000.0 .150303750 17200000.0 .147579250 17300000.0 .1448547502225 3103   54
 17400000.0 .142130250 17500000.0 .139517250 17600000.0 .1370157502225 3103   55
 17700000.0 .134514250 17800000.0 .132012750 17900000.0 .1296180002225 3103   56
 18000000.0 .127330000 18100000.0 .125042000 18200000.0 .1227540002225 3103   57
 18300000.0 .120566000 18400000.0 .118478000 18500000.0 .1163900002225 3103   58
 18600000.0 .114302000 18700000.0 .112306625 18800000.0 .1104038752225 3103   59
 18900000.0 .108501125 19000000.0 .106598375 19100000.0 .1047807882225 3103   60
 19200000.0 .103048363 19300000.0 .101315938 19400000.0 .0995835132225 3103   61
 19500000.0 .097928538 19600000.0 .096351013 19700000.0 .0947734882225 3103   62
 19800000.0 .093195963 19900000.0 .091663500 20000000.0 0.0       2225 3103   63
                                                                  2225 3  099999
                                                                  2225 0  0    0
 2.20460E+4 4.55579E+1          0          0          0          1222533 16    1
 0.000000+0 0.000000+0          0         16          0          1222533 16    2
 0.000000+0 0.000000+0          1          5        190         19222533 16    3
 1.000000-5 1.340000+7 1.400000+7 1.425000+7 1.450000+7 1.475000+7222533 16    4
 1.500000+7 1.525000+7 1.550000+7 1.575000+7 1.600000+7 1.650000+7222533 16    5
 1.700000+7 1.750000+7 1.800000+7 1.850000+7 1.900000+7 1.950000+7222533 16    6
 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222533 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222533 16    9
 0.000000+0 2.781420-2 1.283920-2 7.150180-3 4.197760-3 2.624760-3222533 16   10
 1.798060-3 1.390020-3 1.219080-3 1.180400-3 1.246260-3 1.393920-3222533 16   11
 1.529020-3 1.618830-3 1.660180-3 1.659830-3 1.626720-3 1.569240-3222533 16   12
 8.069150-3 5.546650-3 3.876040-3 2.695150-3 1.848660-3 1.244700-3222533 16   13
 8.222770-4 5.378570-4 3.076620-4 2.302510-4 3.187630-4 5.002420-4222533 16   14
 7.302930-4 9.821299-4 1.239760-3 1.493850-3 4.441590-3 3.461700-3222533 16   15
 2.659900-3 2.009820-3 1.496660-3 1.103050-3 8.113270-4 5.333680-4222533 16   16
 3.719090-4 3.756580-4 4.829110-4 6.520230-4 8.556370-4 1.076080-3222533 16   17
 1.302130-3 2.992840-3 2.525270-3 2.115430-3 1.766930-3 1.480710-3222533 16   18
 1.252600-3 1.007340-3 8.189470-4 7.457220-4 7.499250-4 8.043140-4222533 16   19
 8.900250-4 9.942610-4 1.108480-3 2.356520-3 2.171160-3 1.996940-3222533 16   20
 1.836860-3 1.693860-3 1.511730-3 1.326660-3 1.194050-3 1.101810-3222533 16   21
 1.039690-3 9.996680-4 9.757380-4 9.634650-4 2.189000-3 2.170040-3222533 16   22
 2.129830-3 2.072140-3 1.961190-3 1.796150-3 1.623460-3 1.453990-3222533 16   23
 1.293310-3 1.143860-3 1.006340-3 8.805220-4 2.287180-3 2.348570-3222533 16   24
 2.367250-3 2.325030-3 2.189140-3 1.994320-3 1.770100-3 1.535250-3222533 16   25
 1.301110-3 1.074200-3 8.580140-4 2.496620-3 2.577930-3 2.597300-3222533 16   26
 2.495160-3 2.293670-3 2.036390-3 1.752220-3 1.459490-3 1.169360-3222533 16   27
 8.883550-4 2.712310-3 2.783360-3 2.716800-3 2.521360-3 2.250200-3222533 16   28
 1.939420-3 1.612380-3 1.283690-3 9.621380-4 2.917810-3 2.904460-3222533 16   29
 2.737660-3 2.476860-3 2.163820-3 1.826070-3 1.481200-3 1.140080-3222533 16   30
 2.958400-3 2.849680-3 2.639550-3 2.369860-3 2.069060-3 1.755710-3222533 16   31
 1.441570-3 2.814730-3 2.683000-3 2.492950-3 2.269720-3 2.030300-3222533 16   32
 1.785710-3 2.645740-3 2.555400-3 2.433170-3 2.292510-3 2.142650-3222533 16   33
 2.575470-3 2.565690-3 2.536570-3 2.494660-3 2.673410-3 2.760570-3222533 16   34
 2.831970-3 2.964830-3 3.149770-3 3.446400-3                      222533 16   35
                                                                  222533  099999
 2.20460E+4 4.55579E+1          0          0          0          1222533103    1
 0.000000+0 0.000000+0          0        103          0          1222533103    2
 0.000000+0 0.000000+0          1          5        561         33222533103    3
 1.000000-5 2.100000+6 3.500000+6 4.000000+6 4.500000+6 5.000000+6222533103    4
 5.500000+6 6.000000+6 6.500000+6 7.000000+6 7.500000+6 8.000000+6222533103    5
 8.500000+6 9.000000+6 9.500000+6 1.000000+7 1.050000+7 1.100000+7222533103    6
 1.150000+7 1.200000+7 1.250000+7 1.300000+7 1.350000+7 1.400000+7222533103    7
 1.450000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7 1.700000+7222533103    8
 1.800000+7 1.900000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0222533103    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222533103   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222533103   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222533103   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222533103   13
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 7.547140-2222533103   14
 7.738710-3 5.300980-3 3.343090-3 3.229410-3 3.191540-3 3.980150-3222533103   15
-1.086430-3-2.650150-3-9.973090-4 7.536140-4 1.330980-3 8.231030-4222533103   16
-2.400220-4-1.329500-3-2.073460-3-2.296170-3-2.007770-3-1.361480-3222533103   17
-5.881670-4 7.774100-5 4.595800-4 4.707900-4 1.159630-4-5.310000-4222533103   18
-1.356700-3-2.235630-3-3.049400-3-3.889490-3-4.085210-3-2.881160-3222533103   19
 8.776940-3 2.125590-3 1.611820-3 1.463940-3 1.611840-3 1.498400-3222533103   20
 8.439180-4 3.529330-4 1.464480-4 9.104700-5 8.565990-5 8.698920-5222533103   21
 8.266200-5 7.257120-5 6.017500-5 4.892090-5 4.093100-5 3.675780-5222533103   22
 3.569510-5 3.638050-5 3.743040-5 3.789660-5 3.746600-5 3.641250-5222533103   23
 3.542260-5 3.538540-5 3.721890-5 4.553930-5 6.925680-5 1.104860-4222533103   24
 2.651980-3 1.376600-3 1.269820-3 1.188260-3 1.107080-3 5.977230-4222533103   25
 1.916620-4 4.784520-5 3.918720-5 6.003220-5 6.884940-5 5.974800-5222533103   26
 4.003660-5 1.929470-5 4.792600-6-8.857040-8 4.183230-6 1.433420-5222533103   27
 2.587840-5 3.470020-5 3.813540-5 3.536510-5 2.720150-5 1.556630-5222533103   28
 2.911640-6-8.244020-6-1.641320-5-5.231780-6 4.002130-5 1.974690-3222533103   29
 1.294950-3 1.148980-3 9.448600-4 4.357460-4 1.605830-4 8.925170-5222533103   30
 8.489160-5 8.424620-5 7.318940-5 5.486660-5 3.568320-5 2.066400-5222533103   31
 1.231470-5 1.069510-5 1.404600-5 1.966510-5 2.484750-5 2.761730-5222533103   32
 2.707990-5 2.340320-5 1.752840-5 1.080900-5 4.690890-6 4.965480-7222533103   33
 5.774100-7 1.464440-5 4.788230-5 1.893610-3 1.330940-3 8.157900-4222533103   34
 5.722070-4 3.490700-4 1.849240-4 9.739180-5 6.438320-5 6.008410-5222533103   35
 6.643730-5 7.300830-5 7.479840-5 7.044050-5 6.093780-5 4.864880-5222533103   36
 3.639840-5 2.670740-5 2.127720-5 2.080510-5 2.508940-5 3.331480-5222533103   37
 4.436620-5 5.708370-5 7.042430-5 8.937890-5 1.111760-4 1.263500-4222533103   38
 2.282840-3 1.279210-3 2.857520-4 6.556030-5 1.348380-4 1.968960-4222533103   39
 1.935680-4 1.458640-4 8.401970-5 2.974710-5-5.509160-6-1.880930-5222533103   40
-1.345430-5 3.472290-6 2.362380-5 3.968860-5 4.694420-5 4.378170-5222533103   41
 3.132350-5 1.249240-5-8.982860-6-2.936480-5-4.539530-5-5.468300-5222533103   42
-3.563130-5 2.603940-5 2.847560-3 2.411660-3 1.176110-3 3.278340-4222533103   43
-1.829580-5-6.311860-5 1.867090-5 1.249600-4 2.059570-4 2.434140-4222533103   44
 2.376330-4 1.995920-4 1.452970-4 9.116720-5 5.040080-5 3.086220-5222533103   45
 3.473300-5 5.958600-5 1.001650-4 1.501230-4 2.033080-4 2.545010-4222533103   46
 3.170430-4 3.686510-4 3.737870-4 3.635790-3 2.830400-3 1.521650-3222533103   47
 5.839200-4 1.340470-4 3.008480-5 1.061840-4 2.360330-4 3.400020-4222533103   48
 3.792170-4 3.475140-4 2.621310-4 1.531760-4 5.276980-5-1.371600-5222533103   49
-3.243860-5-1.615290-6 7.111340-5 1.724880-4 2.872210-4 4.005680-4222533103   50
 5.355510-4 6.209800-4 5.540420-4 2.992230-3 2.210920-3 1.321870-3222533103   51
 6.648290-4 2.798550-4 1.044490-4 5.950710-5 7.769920-5 1.107890-4222533103   52
 1.301710-4 1.246390-4 9.638370-5 5.562990-5 1.508460-5-1.444240-5222533103   53
-2.648250-5-1.932520-5 4.843760-6 4.135800-5 8.442420-5 1.467160-4222533103   54
 2.047540-4 2.065660-4 2.102090-3 1.594860-3 1.020360-3 5.333650-4222533103   55
 1.840260-4-2.719890-5-1.218160-4-1.306990-4-8.748800-5-2.378860-5222533103   56
 3.485020-5 7.171340-5 7.966920-5 5.982700-5 1.883050-5-3.412800-5222533103   57
-8.970580-5-1.398910-4-1.786300-4-2.044440-4-1.784490-4-7.872330-5222533103   58
 1.445120-3 1.083580-3 6.775910-4 3.228050-4 6.477870-5-8.405100-5222533103   59
-1.334110-4-1.076300-4-3.862740-5 4.120460-5 1.054510-4 1.378040-4222533103   60
 1.330070-4 9.502850-5 3.371470-5-3.860100-5-1.097120-4-1.690850-4222533103   61
-2.150220-4-1.835830-4-2.528830-5 9.449480-4 7.149460-4 4.759940-4222533103   62
 2.760980-4 1.382640-4 6.658500-5 5.147420-5 7.484400-5 1.155630-4222533103   63
 1.546680-4 1.791070-4 1.831920-4 1.679270-4 1.389590-4 1.042630-4222533103   64
 7.221500-5 5.034500-5 5.195700-5 1.295790-4 3.101290-4 6.811540-4222533103   65
 6.084510-4 5.221670-4 4.374450-4 3.632780-4 3.038860-4 2.601880-4222533103   66
 2.310620-4 2.144760-4 2.083910-4 2.113000-4 2.224300-4 2.416450-4222533103   67
 2.692310-4 3.056580-4 3.514030-4 4.379840-4 5.881100-4 7.771760-4222533103   68
 6.991220-4 7.367750-4 7.216420-4 6.605220-4 5.672850-4 4.601860-4222533103   69
 3.585400-4 2.790880-4 2.332240-4 2.259000-4 2.562190-4 3.191390-4222533103   70
 4.074230-4 5.132960-4 6.295330-4 8.071950-4 1.037690-3 1.238670-3222533103   71
 8.790310-4 9.295870-4 8.911490-4 7.816890-4 6.311210-4 4.740970-4222533103   72
 3.424850-4 2.593850-4 2.363030-4 2.736960-4 3.638140-4 4.942810-4222533103   73
 6.512370-4 8.215070-4 1.072590-3 1.374030-3 1.596580-3 1.030230-3222533103   74
 1.017920-3 9.115610-4 7.451500-4 5.608290-4 3.988850-4 2.897880-4222533103   75
 2.500630-4 2.824190-4 3.789560-4 5.254750-4 7.054170-4 9.026670-4222533103   76
 1.194860-3 1.543810-3 1.794240-3 1.031340-3 9.444440-4 7.900760-4222533103   77
 6.093440-4 4.433830-4 3.246260-4 2.720760-4 2.908640-4 3.750690-4222533103   78
 5.118720-4 6.855040-4 8.801580-4 1.175590-3 1.539350-3 1.814440-3222533103   79
 8.888590-4 7.683740-4 6.179780-4 4.727510-4 3.619820-4 3.042870-4222533103   80
 3.066400-4 3.663150-4 4.741640-4 6.179180-4 7.847390-4 1.048310-3222533103   81
 1.391040-3 1.675830-3 6.951350-4 5.922860-4 4.861340-4 3.987540-4222533103   82
 3.458160-4 3.349860-4 3.668070-4 4.367340-4 5.373920-4 6.604250-4222533103   83
 8.666360-4 1.155910-3 1.425790-3 5.437350-4 4.853040-4 4.317030-4222533103   84
 3.935570-4 3.777810-4 3.872170-4 4.214350-4 4.778520-4 5.527710-4222533103   85
 6.898540-4 9.026440-4 1.128670-3 4.746400-4 4.584020-4 4.431900-4222533103   86
 4.334040-4 4.325120-4 4.425760-4 4.644360-4 4.980230-4 5.687730-4222533103   87
 6.952440-4 8.510190-4 4.782020-4 4.903100-4 4.974660-4 5.014420-4222533103   88
 5.045490-4 5.088950-4 5.162030-4 5.356930-4 5.801400-4 6.480210-4222533103   89
 5.318150-4 5.641130-4 5.877260-4 6.024600-4 6.093140-4 6.096570-4222533103   90
 6.009780-4 5.800660-4 5.550780-4 6.279110-4 6.821970-4 7.248890-4222533103   91
 7.532320-4 7.662530-4 7.557490-4 6.950360-4 5.859180-4 7.756650-4222533103   92
 8.574140-4 9.223740-4 9.650720-4 9.782880-4 9.082420-4 7.360870-4222533103   93
 9.863660-4 1.097040-3 1.182050-3 1.240980-3 1.193460-3 9.889720-4222533103   94
 1.260120-3 1.394240-3 1.515950-3 1.521600-3 1.321900-3 1.583350-3222533103   95
 1.778520-3 1.865200-3 1.710910-3 2.097680-3 2.348220-3 2.342350-3222533103   96
 2.885560-3 3.210870-3 4.018350-3                                 222533103   97
                                                                  222533  099999
                                                                  2225 0  0    0
                                                                     0 0  0    0
 2.20470E+4 4.65484E+1          0          0         34         102228 1451    1
 0.0        0.0                 0          0          0          62228 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022228 1451    3
 3.00000E+2 0.0                 1          0        163          72228 1451    4
 22-Ti- 47 FEI/ANL    EVAL-Oct95 K.I.Zolotarev, C.Philis et al.   2228 1451    5
                      DIST-Feb2004                                2228 1451    6
----IRDF-2002         MATERIAL 2228                               2228 1451    7
-----INCIDENT NEUTRON DATA                                        2228 1451    8
------ENDF-6 FORMAT                                               2228 1451    9
***************************************************************** 2228 1451   10
 22-TI-47  FEI        EVAL-Oct95 K.I.Zolotarev                    2228 1451   11
                      DIST-Feb02 Mod1                  20020203   2228 1451   12
----BROND-2           MATERIAL 2228         REVISION 1            2228 1451   13
-----INCIDENT NEUTRON DATA                                        2228 1451   14
------ENDF-6 FORMAT                                               2228 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    2228 1451   16
***************************************************************** 2228 1451   17
 22-TI- 47 ANL        EVAL-JAN77  C.PHILIS,O.BERSILLON,D.SMITH,ETC2228 1451   18
                      DIST-FEB91                       910201     2228 1451   19
----IRDF-90           MATERIAL 2228                               2228 1451   20
    ENDF/B-VI         MATERIAL 2228                               2228 1451   21
 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC             2228 1451   22
***************************************************************** 2228 1451   23
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2228 1451   24
DOSIMETRY                                                         2228 1451   25
***************************************************************** 2228 1451   26
********     Start of (N,NP) bibliographical component    ******* 2228 1451   27
***************************************************************** 2228 1451   28
Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko           2228 1451   29
                                                                  2228 1451   30
 For this special purpose library it was decided the reaction     2228 1451   31
 MF=3 MT=28+104 would use MF=10, MT=5 to present this data.       2228 1451   32
 This was done after processing through the codes. The            2228 1451   33
 co-variance file was converted from MF/MT=33/28 to MF/MT=40/5    2228 1451   34
******************************************************************2228 1451   35
MF=3                                                              2228 1451   36
MT= 28 -(n,np+pn+d) cross section data                            2228 1451   37
--------------------------------------                            2228 1451   38
    In this section is given the sum of cross section of the reac-2228 1451   39
tions Ti47(n,np)Sc46m+g , Ti47(n,pn)Sc46m+g and Ti47(n,d)Sc46m+g. 2228 1451   40
    Excitation function for the Ti47(n,x)Sc46m+g reaction  in the 2228 1451   41
energy region from threshold to 20 MeV was evaluated  by means of 2228 1451   42
statistical analysis of experimental cross section data [1-6] and 2228 1451   43
data from STAPRE [7] calculation.                                 2228 1451   44
    All experimental data were renormalized to  the new standards 2228 1451   45
for monitor reactions cross sections and decay data.              2228 1451   46
    The final procedure of evaluation Ti47(n,x)Sc46m+g excitation 2228 1451   47
function from threshold to 20 MeV has been carried out within the 2228 1451   48
framework of generalized least squares method.  Rational function 2228 1451   49
was used  as  model function [8].  Calculations  was performed by 2228 1451   50
means of  Pade-2 code [9].                                        2228 1451   51
    U-235 thermal fission [10]  and  Cf-252 spontaneous  fission  2228 1451   52
neutron spectra [11] averaged cross-sections calculated from the  2228 1451   53
evaluated Ti47(n,x)Sc46m+g excitation function are the following: 2228 1451   54
                                                                  2228 1451   55
         --------------------------------------------             2228 1451   56
              TYPE OF SPECTRUM     I <CS>, mb (calc.)             2228 1451   57
         --------------------------I-----------------             2228 1451   58
         U-235  neutron  fission   I    8.1158E-3                 2228 1451   59
         CF-252 spontan. fission   I    1.9201E-2                 2228 1451   60
                                                                  2228 1451   61
MF=33                                                             2228 1451   62
MT= 28 -(n,np+pn+d) cross section cov. matrix                     2228 1451   63
---------------------------------------------                     2228 1451   64
    Uncertainties in the evaluated  excitation function  for the  2228 1451   65
reaction  Ti-47(n,x)Sc-46m+g  are given in the form  of relative  2228 1451   66
covariance matrix for the 17-neutron energy groups (LB=5).  Cova- 2228 1451   67
riance matrix of uncertainties was calculated simultaneously with 2228 1451   68
recommended cross section data by means of PADE-2 code.           2228 1451   69
    Eigenvalues  of the  6-th digits  relative covariance matrix  2228 1451   70
given in the 33-file are the following:                           2228 1451   71
                                                                  2228 1451   72
    3.91044E-07    4.46920E-07    5.37497E-07    7.02044E-07      2228 1451   73
    9.85160E-07    1.54860E-06    2.86775E-06    6.97782E-06      2228 1451   74
    2.67223E-05    1.90995E-04    9.14779E-04    5.12707E-03      2228 1451   75
    8.27566E-03    1.15029E-02    1.68918E-02    5.65241E-02      2228 1451   76
    8.27240E-01                                                   2228 1451   77
                                                                  2228 1451   78
 References :                                                     2228 1451   79
 1. W.G.Cross, H.L.Pai Progress Rep. EANDC(CAN)-16, p.1, Jan.1963 2228 1451   80
 2. H.L.Pai  Canadian J. of Physics, v.44, p.2337, 1966           2228 1451   81
 3. I.Ribansky, S.Gmuca  J. Phys.G, v.9, p.1537, December 1983    2228 1451   82
 4. N.I.Molla et al.  Report INDC(BAN)-003, September 1986        2228 1451   83
 5. Y.Ikeda et al.  Report JAERI-1312, March 1988                 2228 1451   84
 6. Y.Uno et al.  Report JAERI-M-93-046, p.247-256, 1993          2228 1451   85
 7. M.Uhl, B.Strohmaier Computer Code STAPRE for Particle Induced 2228 1451   86
    Activation Cross Section and Related Quantities, Report       2228 1451   87
    IRK 76-01, Vienna, 1976                                       2228 1451   88
 8. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2228 1451   89
    st's Meeting on Evaluation and Processing of Covariance Data, 2228 1451   90
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  2228 1451   91
 9. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          2228 1451   92
10. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2228 1451   93
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              2228 1451   94
11. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        2228 1451   95
******************************************************************2228 1451   96
********      End of (N,NP) bibliographical component     ******* 2228 1451   97
***************************************************************** 2228 1451   98
***************************************************************** 2228 1451   99
********     Start of (N,P) bibliographical component     ******* 2228 1451  100
***************************************************************** 2228 1451  101
 **                                                               2228 1451  102
  DOCUMENTATION ANL/NDM-27 (N,P)                                  2228 1451  103
 **                                                               2228 1451  104
  COMMENTS- (N,P) EVAL IN ENERGY RANGES 1.10E+06 TO 1.0E+07 AND   2228 1451  105
  1.35E+07 TO 2.0E+07 BASED ON EXPERIMENTAL DATA.INTERPOLATION AND2228 1451  106
  EXTRAPOLATION TO OTHER ENERGIES BASED ON THEORETICAL CALCULATION2228 1451  107
  PERFORMED AT BRUYERES LE CHATEL USING CODE DEVELOPED BY JARRE.  2228 1451  108
  PSEUDO-THRESHOLD=0.5 MEV PER P.C. MACFARLANE TO MAGURNO 6/20/83 2228 1451  109
 **                                                               2228 1451  110
  REFERENCES                                                      2228 1451  111
   AL61 ALLAN D. NP24,274,61                                      2228 1451  112
   AR78 ARTHUR E. PC 1978                                         2228 1451  113
   AR75 ARMITAGE P.C. NNDC                                        2228 1451  114
   CR62 CROSS W.AND PAI H. EANDC(CAN)-16,2,62                     2228 1451  115
   FU79 C.Y.FU PRIVATE COMM 1979                                  2228 1451  116
   GH71 GHORAI S.AND CARROLL E. NSE 43,233,71                     2228 1451  117
   GO62 GONZALES ET.AL. PR126,271,62                              2228 1451  118
   HI   HILLMAN M. NP37,78,62                                     2228 1451  119
   LE69 LEVKOVSKII V. Y.F.10,44,69                                2228 1451  120
   PA66 PAI H.CJP 44 2337,66                                      2228 1451  121
   PO59 POULARIKIS A. AND FINK R. PR115,989,59                    2228 1451  122
   SM75 SMITH D.L.AND MEADOWS J. ANL/NDM10,75                     2228 1451  123
   TI68 TIKKU ET.AL. SYMP ON NUCL CROSS SECT AND TECH WASH.1968   2228 1451  124
******************************************************************2228 1451  125
********      End of (N,P) bibliographical component      ******* 2228 1451  126
***************************************************************** 2228 1451  127
 The Q values and threshold energies were updated prior to pro-   2228 1451  128
 cessing through the codes to comply with the values obtained     2228 1451  129
 using the NNDC calculation program which is based on the 1995    2228 1451  130
 Update to the Atomic mass Evaluation.                            2228 1451  131
                                                                  2228 1451  132
 File 2 added to the pointwise file containing only the effective 2228 1451  133
 scattering radius with no resonance parameters given.            2228 1451  134
 Taken from ENDF/B-VI                                             2228 1451  135
                                                                  2228 1451  136
 Threshold of 0.0 added at 1.0E-5 ev to MF/MT=3/103 after         2228 1451  137
 processing thro. the pre-procssing codes.                        2228 1451  138
                                                                  2228 1451  139
                                                                  2228 1451  140
***************************************************************** 2228 1451  141
 ***************** Program LINEAR (VERSION 2002-1) ***************2228 1451  142
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2228 1451  143
 Data Linearized to Within an Accuracy of .100000000 per-cent     2228 1451  144
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2228 1451  145
 Data Doppler Broadened to 300.000000 Kelvin                      2228 1451  146
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2228 1451  147
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2228 1451  148
 ***************** Program FIXUP (Version 2002-1) ****************2228 1451  149
 Corrected ZA/AWR in All Sections-----------------------------Yes 2228 1451  150
 Corrected Thresholds-----------------------------------------Yes 2228 1451  151
 Extended Cross Sections to 20 MeV----------------------------No  2228 1451  152
 Allow Cross Section Deletion---------------------------------No  2228 1451  153
 Allow Cross Section Reconstruction---------------------------No  2228 1451  154
 Make All Cross Sections Non-Negative-------------------------Yes 2228 1451  155
 Delete Energies Not in Ascending Order-----------------------Yes 2228 1451  156
 Deleted Duplicate Points-------------------------------------Yes 2228 1451  157
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2228 1451  158
 Check for Legal MF/MT Numbers--------------------------------Yes 2228 1451  159
 Allow Creation of Missing Sections---------------------------No  2228 1451  160
 Allow Insertion of Energy Points-----------------------------No  2228 1451  161
 Create Uniform Energy Grid-----------------------------------No  2228 1451  162
 Delete Section if Cross Section =0 at All Energies-----------Yes 2228 1451  163
***************************************************************** 2228 1451  164
 ***************** Program GROUPIE (VERSION 2002-1) **************2228 1451  165
 Unshielded Group Averages Using  640 Groups                      2228 1451  166
 Weighting Spectrum: Flat (Constant) Spectrum                     2228 1451  167
                                1        451        174          12228 1451  168
                                2        151          4          12228 1451  169
                                3        103         70          02228 1451  170
                                8          5          2          12228 1451  171
                               10          5         42          12228 1451  172
                               33        103        115          12228 1451  173
                               40          5         36          02228 1451  174
                                                                  2228 1  099999
                                                                  2228 0  0    0
 2.20470E+4 4.65480E+1          0          0          1          02228 2151    1
 2.204700+4 1.000000+0          0          0          1          02228 2151    2
 1.000000-5 1.000000+5          0          0          0          02228 2151    3
 3.500000+0 0.573300+0          0          0          0          02228 2151    4
                                                                  2228 2  099999
                                                                  2228 0  0    0
 2.20470E+4 4.65484E+1          0          0          0          02228 3103    1
 1.82300E+5 1.82300E+5          0          0          1        1992228 3103    2
        199          1                                            2228 3103    3
 690000.000 5.16780E-5 720000.000 .000310068 760000.000 .0006201362228 3103    4
 800000.000 .000805043 840000.000 .000864789 880000.000 .0009245352228 3103    5
 920000.000 .000984281 960000.000 .001044027 1000000.00 .0013463902228 3103    6
 1100000.00 .001891370 1200000.00 .002436350 1300000.00 .0029813302228 3103    7
 1400000.00 .003526310 1500000.00 .004697020 1600000.00 .0064934602228 3103    8
 1700000.00 .008289900 1800000.00 .010086340 1900000.00 .0118827802228 3103    9
 2000000.00 .013905700 2100000.00 .016155100 2200000.00 .0184045002228 3103   10
 2300000.00 .020653900 2400000.00 .022903300 2500000.00 .0250525002228 3103   11
 2600000.00 .027101500 2700000.00 .029097500 2800000.00 .0310405002228 3103   12
 2900000.00 .032983500 3000000.00 .034727500 3100000.00 .0362725002228 3103   13
 3200000.00 .037817500 3300000.00 .039362500 3400000.00 .0409075002228 3103   14
 3500000.00 .042653900 3600000.00 .044601700 3700000.00 .0465495002228 3103   15
 3800000.00 .048497300 3900000.00 .050445100 4000000.00 .0520001002228 3103   16
 4100000.00 .053162300 4200000.00 .054324500 4300000.00 .0554867002228 3103   17
 4400000.00 .056648900 4500000.00 .057830600 4600000.00 .0590318002228 3103   18
 4700000.00 .060233000 4800000.00 .061434200 4900000.00 .0626354002228 3103   19
 5000000.00 .064098300 5100000.00 .065822900 5200000.00 .0675475002228 3103   20
 5300000.00 .069272100 5400000.00 .070996700 5500000.00 .0723986002228 3103   21
 5600000.00 .073477800 5700000.00 .074557000 5800000.00 .0756362002228 3103   22
 5900000.00 .076715400 6000000.00 .078082700 6100000.00 .0797381002228 3103   23
 6200000.00 .081393500 6300000.00 .083048900 6400000.00 .0847043002228 3103   24
 6500000.00 .086108400 6600000.00 .087261200 6700000.00 .0884140002228 3103   25
 6800000.00 .089566800 6900000.00 .090719600 7000000.00 .0919561002228 3103   26
 7100000.00 .093276300 7200000.00 .094596500 7300000.00 .0959167002228 3103   27
 7400000.00 .097236900 7500000.00 .098933300 7600000.00 .1010059002228 3103   28
 7700000.00 .103078500 7800000.00 .105151100 7900000.00 .1072237002228 3103   29
 8000000.00 .109065000 8100000.00 .110675000 8200000.00 .1122850002228 3103   30
 8300000.00 .113895000 8400000.00 .115505000 8500000.00 .1168730002228 3103   31
 8600000.00 .117999000 8700000.00 .119125000 8800000.00 .1202510002228 3103   32
 8900000.00 .121377000 9000000.00 .122315000 9100000.00 .1230650002228 3103   33
 9200000.00 .123815000 9300000.00 .124565000 9400000.00 .1253150002228 3103   34
 9500000.00 .126237000 9600000.00 .127331000 9700000.00 .1284250002228 3103   35
 9800000.00 .129519000 9900000.00 .130613000 10000000.0 .1312550002228 3103   36
 10100000.0 .131445000 10200000.0 .131635000 10300000.0 .1318250002228 3103   37
 10400000.0 .132015000 10500000.0 .132205000 10600000.0 .1323950002228 3103   38
 10700000.0 .132585000 10800000.0 .132775000 10900000.0 .1329650002228 3103   39
 11000000.0 .132870000 11100000.0 .132490000 11200000.0 .1321100002228 3103   40
 11300000.0 .131730000 11400000.0 .131350000 11500000.0 .1309700002228 3103   41
 11600000.0 .130590000 11700000.0 .130210000 11800000.0 .1298300002228 3103   42
 11900000.0 .129450000 12000000.0 .128879750 12100000.0 .1281192502228 3103   43
 12200000.0 .127358750 12300000.0 .126598250 12400000.0 .1258377502228 3103   44
 12500000.0 .125077250 12600000.0 .124316750 12700000.0 .1235562502228 3103   45
 12800000.0 .122795750 12900000.0 .122035250 13000000.0 .1212747502228 3103   46
 13100000.0 .120514250 13200000.0 .119753750 13300000.0 .1189932502228 3103   47
 13400000.0 .118232750 13500000.0 .117472250 13600000.0 .1167117502228 3103   48
 13700000.0 .115951250 13800000.0 .115190750 13900000.0 .1144302502228 3103   49
 14000000.0 .113575000 14100000.0 .112625000 14200000.0 .1116750002228 3103   50
 14300000.0 .110725000 14400000.0 .109775000 14500000.0 .1087300002228 3103   51
 14600000.0 .107590000 14700000.0 .106450000 14800000.0 .1053100002228 3103   52
 14900000.0 .104170000 15000000.0 .103124400 15100000.0 .1021732002228 3103   53
 15200000.0 .101222000 15300000.0 .100270800 15400000.0 .0993196002228 3103   54
 15500000.0 .098273800 15600000.0 .097133400 15700000.0 .0959930002228 3103   55
 15800000.0 .094852600 15900000.0 .093712200 16000000.0 .0926786752228 3103   56
 16100000.0 .091752025 16200000.0 .090825375 16300000.0 .0898987252228 3103   57
 16400000.0 .088972075 16500000.0 .088045425 16600000.0 .0871187752228 3103   58
 16700000.0 .086192125 16800000.0 .085265475 16900000.0 .0843388252228 3103   59
 17000000.0 .083412175 17100000.0 .082485525 17200000.0 .0815588752228 3103   60
 17300000.0 .080632225 17400000.0 .079705575 17500000.0 .0787789252228 3103   61
 17600000.0 .077852275 17700000.0 .076925625 17800000.0 .0759989752228 3103   62
 17900000.0 .075072325 18000000.0 .074409400 18100000.0 .0740102002228 3103   63
 18200000.0 .073611000 18300000.0 .073211800 18400000.0 .0728126002228 3103   64
 18500000.0 .072413400 18600000.0 .072014200 18700000.0 .0716150002228 3103   65
 18800000.0 .071215800 18900000.0 .070816600 19000000.0 .0704174002228 3103   66
 19100000.0 .070018200 19200000.0 .069619000 19300000.0 .0692198002228 3103   67
 19400000.0 .068820600 19500000.0 .068411900 19600000.0 .0679937002228 3103   68
 19700000.0 .067575500 19800000.0 .067157300 19900000.0 .0667391002228 3103   69
 20000000.0 0.0                                                   2228 3103   70
                                                                  2228 3  099999
                                                                  2228 0  0    0
 2.20470E+4 4.65480E+1          0          0          1          12228 8  5    1
 2.104600+4 0.000000+0         10          0          0          02228 8  5    2
                                                                  2228 8  099999
                                                                  2228 0  0    0
 2.20470E+4 4.65484E+1          0          0          1          0222810  5    1
-8.23750E+6-8.23750E+6      21046          0          1        117222810  5    2
        117          1                                            222810  5    3
 8400000.00 1.03337E-8 8500000.00 3.81554E-8 8600000.00 6.62625E-8222810  5    4
 8700000.00 9.43696E-8 8800000.00 1.22477E-7 8900000.00 1.50584E-7222810  5    5
 9000000.00 1.78691E-7 9100000.00 2.06798E-7 9200000.00 2.34905E-7222810  5    6
 9300000.00 2.63012E-7 9400000.00 2.91119E-7 9500000.00 3.73532E-6222810  5    7
 9600000.00 8.18206E-6 9700000.00 9.01171E-6 9800000.00 8.63786E-6222810  5    8
 9900000.00 9.48327E-6 10000000.0 1.39527E-5 10100000.0 2.43832E-5222810  5    9
 10200000.0 4.30199E-5 10300000.0 7.19698E-5 10400000.0 .000113152222810  5   10
 10500000.0 .000168247 10600000.0 .000238639 10700000.0 .000325360222810  5   11
 10800000.0 .000429044 10900000.0 .000549884 11000000.0 .000687622222810  5   12
 11100000.0 .000841563 11200000.0 .001010656 11300000.0 .001193625222810  5   13
 11400000.0 .001389225 11500000.0 .001596590 11600000.0 .001815690222810  5   14
 11700000.0 .002047940 11800000.0 .002296875 11900000.0 .002568815222810  5   15
 12000000.0 .002873450 12100000.0 .003224210 12200000.0 .003638220222810  5   16
 12300000.0 .004135785 12400000.0 .004739380 12500000.0 .005472175222810  5   17
 12600000.0 .006356365 12700000.0 .007411525 12800000.0 .008653235222810  5   18
 12900000.0 .010092245 13000000.0 .011734200 13100000.0 .013579800222810  5   19
 13200000.0 .015625550 13300000.0 .017864600 13400000.0 .020287600222810  5   20
 13500000.0 .022883750 13600000.0 .025641250 13700000.0 .028548050222810  5   21
 13800000.0 .031592250 13900000.0 .034761950 14000000.0 .038046250222810  5   22
 14100000.0 .041434800 14200000.0 .044937275 14300000.0 .048504225222810  5   23
 14400000.0 .052142250 14500000.0 .055851350 14600000.0 .059625450222810  5   24
 14700000.0 .063464550 14800000.0 .067303650 14900000.0 .071198145222810  5   25
 15000000.0 .075148036 15100000.0 .079097927 15200000.0 .083047818222810  5   26
 15300000.0 .086997709 15400000.0 .090947600 15500000.0 .094897491222810  5   27
 15600000.0 .098847382 15700000.0 .102797273 15800000.0 .106747164222810  5   28
 15900000.0 .110697055 16000000.0 .114575600 16100000.0 .118382800222810  5   29
 16200000.0 .122190000 16300000.0 .125997200 16400000.0 .129804400222810  5   30
 16500000.0 .133516125 16600000.0 .137132375 16700000.0 .140748625222810  5   31
 16800000.0 .144364875 16900000.0 .147878500 17000000.0 .151289500222810  5   32
 17100000.0 .154700500 17200000.0 .158111500 17300000.0 .161411125222810  5   33
 17400000.0 .164599375 17500000.0 .167787625 17600000.0 .170975875222810  5   34
 17700000.0 .174035700 17800000.0 .176967100 17900000.0 .179898500222810  5   35
 18000000.0 .182829900 18100000.0 .185761300 18200000.0 .188553000222810  5   36
 18300000.0 .191205000 18400000.0 .193857000 18500000.0 .196509000222810  5   37
 18600000.0 .199161000 18700000.0 .201681100 18800000.0 .204069300222810  5   38
 18900000.0 .206457500 19000000.0 .208845700 19100000.0 .211233900222810  5   39
 19200000.0 .213490250 19300000.0 .215614750 19400000.0 .217739250222810  5   40
 19500000.0 .219863750 19600000.0 .221988250 19700000.0 .224112750222810  5   41
 19800000.0 .226149500 19900000.0 .228098500 20000000.0 0.0       222810  5   42
                                                                  222810  099999
                                                                  2228 0  0    0
 2.20470E+4 4.65484E+1          0          0          0          1222833103    1
 0.0000E+00 0.0000E+00          0        103          0          5222833103    2
 0.0000E+00 0.0000E+00          1          5        351         26222833103    3
 1.0000E-05 8.0000E+05 8.5000E+05 9.0000E+05 1.0000E+06 1.5000E+06222833103    4
 2.0000E+06 2.5000E+06 2.7000E+06 3.0000E+06 3.5000E+06 4.0000E+06222833103    5
 4.5000E+06 5.0000E+06 5.5000E+06 6.0000E+06 6.5000E+06 8.0000E+06222833103    6
 8.5000E+06 1.0000E+07 1.2000E+07 1.4000E+07 1.5500E+07 1.6000E+07222833103    7
 1.8000E+07 2.0000E+07 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00222833103    8
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00222833103    9
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00222833103   10
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00222833103   11
 0.0000E+00 0.0000E+00 0.0000E+00 2.5381E-02 7.9629E-04 7.9518E-04222833103   12
 7.6578E-04 8.8138E-04 5.1877E-04 8.0587E-04 7.7474E-04 6.1515E-04222833103   13
 6.1163E-04 5.2651E-04 5.3917E-04 5.1312E-04 5.3435E-04 3.3906E-04222833103   14
 3.4009E-04 2.0417E-04 2.6464E-04 3.9680E-04 3.9643E-04 3.9633E-04222833103   15
 3.9620E-04 3.9634E-04 3.9641E-04 2.1504E-02 7.9479E-04 7.6498E-04222833103   16
 8.8151E-04 5.1866E-04 8.0613E-04 7.7468E-04 6.1520E-04 6.1167E-04222833103   17
 5.2645E-04 5.3924E-04 5.1309E-04 5.3434E-04 3.3909E-04 3.4012E-04222833103   18
 2.0407E-04 2.6453E-04 3.9667E-04 3.9631E-04 3.9621E-04 3.9608E-04222833103   19
 3.9613E-04 3.9639E-04 8.9817E-03 7.6421E-04 8.8049E-04 5.1804E-04222833103   20
 8.0518E-04 7.7387E-04 6.1457E-04 6.1107E-04 5.2586E-04 5.3871E-04222833103   21
 5.1248E-04 5.3371E-04 3.3864E-04 3.3974E-04 2.0390E-04 2.6429E-04222833103   22
 3.9602E-04 3.9593E-04 3.9577E-04 3.9569E-04 3.9579E-04 3.9594E-04222833103   23
 1.0204E-03 8.4589E-04 5.3021E-04 8.0672E-04 7.7820E-04 6.1795E-04222833103   24
 6.1465E-04 5.2640E-04 5.3898E-04 5.1202E-04 5.3347E-04 3.3794E-04222833103   25
 3.3915E-04 2.0256E-04 2.6207E-04 3.9137E-04 3.9132E-04 3.9102E-04222833103   26
 3.9079E-04 3.9103E-04 3.9111E-04 9.9997E-04 5.8499E-04 9.1088E-04222833103   27
 8.7530E-04 6.9471E-04 6.9066E-04 5.9435E-04 6.0833E-04 5.7840E-04222833103   28
 6.0251E-04 3.8188E-04 3.8305E-04 2.2896E-04 2.9663E-04 4.4442E-04222833103   29
 4.4403E-04 4.4386E-04 4.4381E-04 4.4384E-04 4.4405E-04 1.9344E-03222833103   30
 1.0301E-03 1.2529E-03 1.2732E-03 1.2693E-03 1.1544E-03 1.1440E-03222833103   31
 1.0715E-03 1.1160E-03 7.2792E-04 7.3010E-04 4.3714E-04 4.9967E-04222833103   32
 6.3246E-04 6.3186E-04 6.3165E-04 6.3160E-04 6.3159E-04 6.3202E-04222833103   33
 4.5091E-03 2.1313E-03 1.9340E-03 1.9475E-03 1.4592E-03 1.5061E-03222833103   34
 1.4020E-03 1.4605E-03 1.0395E-03 1.0427E-03 7.1384E-04 7.8497E-04222833103   35
 9.3160E-04 9.3092E-04 9.3053E-04 9.3029E-04 9.3053E-04 9.3082E-04222833103   36
 2.9794E-03 1.8212E-03 1.8725E-03 1.4470E-03 1.4896E-03 1.3848E-03222833103   37
 1.4426E-03 9.9556E-04 9.9869E-04 6.7811E-04 7.5004E-04 8.9890E-04222833103   38
 8.9831E-04 8.9791E-04 8.9761E-04 8.9794E-04 8.9812E-04 2.5437E-03222833103   39
 1.8898E-03 1.4992E-03 1.4553E-03 1.3861E-03 1.4439E-03 9.9382E-04222833103   40
 9.9676E-04 6.6725E-04 7.3710E-04 8.8198E-04 8.8127E-04 8.8093E-04222833103   41
 8.8078E-04 8.8075E-04 8.8132E-04 2.4114E-03 1.2836E-03 1.5091E-03222833103   42
 1.3287E-03 1.3838E-03 9.7183E-04 9.7488E-04 6.5752E-04 7.2830E-04222833103   43
 8.7513E-04 8.7452E-04 8.7421E-04 8.7389E-04 8.7414E-04 8.7436E-04222833103   44
 3.2041E-03 1.3121E-03 1.9672E-03 2.0492E-03 1.1751E-03 1.1786E-03222833103   45
 7.5781E-04 8.0402E-04 8.9428E-04 8.9351E-04 8.9318E-04 8.9301E-04222833103   46
 8.9312E-04 8.9355E-04 5.1052E-03 3.0666E-03 3.1940E-03 1.1620E-03222833103   47
 1.1656E-03 7.8194E-04 8.8221E-04 1.0931E-03 1.0923E-03 1.0919E-03222833103   48
 1.0917E-03 1.0917E-03 1.0924E-03 6.7878E-03 4.1885E-03 1.1457E-03222833103   49
 1.1492E-03 8.2269E-04 9.5199E-04 1.2277E-03 1.2267E-03 1.2262E-03222833103   50
 1.2261E-03 1.2261E-03 1.2269E-03 6.7235E-03 1.1932E-03 1.1969E-03222833103   51
 8.5687E-04 9.9170E-04 1.2788E-03 1.2778E-03 1.2772E-03 1.2770E-03222833103   52
 1.2772E-03 1.2778E-03 9.4153E-03 4.2649E-03-2.3971E-04 1.4751E-04222833103   53
 1.0208E-03 1.0199E-03 1.0195E-03 1.0193E-03 1.0193E-03 1.0199E-03222833103   54
 8.5135E-03-2.4014E-04 1.4815E-04 1.0240E-03 1.0230E-03 1.0226E-03222833103   55
 1.0225E-03 1.0225E-03 1.0231E-03 7.9729E-03 5.9034E-03 1.1173E-03222833103   56
 1.1162E-03 1.1162E-03 1.1158E-03 1.1160E-03 1.1165E-03 1.2694E-02222833103   57
 1.5499E-03 1.5489E-03 1.5481E-03 1.5480E-03 1.5483E-03 1.5490E-03222833103   58
 1.2700E-02 2.4994E-03 2.4987E-03 2.4986E-03 2.4985E-03 2.4998E-03222833103   59
 1.2795E-02 2.4964E-03 2.4962E-03 2.4965E-03 2.4977E-03 1.2827E-02222833103   60
 9.5528E-03 2.4955E-03 2.4969E-03 1.3978E-02 2.4952E-03 2.4964E-03222833103   61
 1.2852E-02 2.4966E-03 1.2789E-02 0.0000E+00 0.0000E+00 0.0000E+00222833103   62
 0.0000E+00 0.0000E+00         26          4        104         52222833103   63
 1.0000E-05 0.0000E+00 8.0000E+05-1.0000E+00 8.5000E+05-1.0000E+00222833103   64
 9.0000E+05-1.0000E+00 1.0000E+06-1.0000E+00 1.5000E+06-1.0000E+00222833103   65
 2.0000E+06-1.0000E+00 2.5000E+06-1.0000E+00 2.7000E+06-1.0000E+00222833103   66
 3.0000E+06-1.0000E+00 3.5000E+06-1.0000E+00 4.0000E+06-1.0000E+00222833103   67
 4.5000E+06-1.0000E+00 5.0000E+06-1.0000E+00 5.5000E+06-1.0000E+00222833103   68
 6.0000E+06-1.0000E+00 6.5000E+06-5.6000E-01 8.0000E+06-1.0000E+00222833103   69
 8.5000E+06-3.5000E-01 1.0000E+07-2.4000E-01 1.2000E+07-2.7000E-01222833103   70
 1.4000E+07-2.6000E-01 1.5500E+07-1.0000E+00 1.6000E+07-2.9000E-01222833103   71
 1.8000E+07-2.8000E-01 2.0000E+07 0.0000E+00 1.0000E-05 0.0000E+00222833103   72
 8.0000E+05 1.5931E-01 8.5000E+05 1.4664E-01 9.0000E+05 9.4772E-02222833103   73
 1.0000E+06 3.1943E-02 1.5000E+06 3.1622E-02 2.0000E+06 4.3982E-02222833103   74
 2.5000E+06 6.7150E-02 2.7000E+06 5.4584E-02 3.0000E+06 5.0435E-02222833103   75
 3.5000E+06 4.9106E-02 4.0000E+06 5.6605E-02 4.5000E+06 7.1451E-02222833103   76
 5.0000E+06 8.2388E-02 5.5000E+06 8.1997E-02 6.0000E+06 9.7032E-02222833103   77
 6.5000E+06 9.2268E-02 8.0000E+06 8.9291E-02 8.5000E+06 1.1267E-01222833103   78
 1.0000E+07 1.1269E-01 1.2000E+07 1.1312E-01 1.4000E+07 1.1326E-01222833103   79
 1.5500E+07 1.1823E-01 1.6000E+07 1.1337E-01 1.8000E+07 1.1309E-01222833103   80
 2.0000E+07 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00222833103   81
 0.0000E+00 0.0000E+00          0          1         88         44222833103   82
 1.0000E-05 0.0000E+00 8.0000E+05 2.2843E-02 8.5000E+05 1.9354E-02222833103   83
 9.0000E+05 8.0835E-03 1.0000E+06 9.1833E-04 1.5000E+06 8.9998E-04222833103   84
 2.0000E+06 1.7410E-03 2.5000E+06 4.0582E-03 2.7000E+06 2.6815E-03222833103   85
 3.0000E+06 2.2893E-03 3.5000E+06 2.1702E-03 4.0000E+06 2.8837E-03222833103   86
 4.5000E+06 4.5947E-03 5.0000E+06 6.1090E-03 5.5000E+06 6.0512E-03222833103   87
 6.0000E+06 8.4737E-03 6.5000E+06 4.2908E-03 7.0000E+06 4.2908E-03222833103   88
 7.5000E+06 4.2908E-03 8.0000E+06 7.1756E-03 8.5000E+06 3.9985E-03222833103   89
 9.0000E+06 3.9985E-03 9.5000E+06 3.9985E-03 1.0000E+07 2.7432E-03222833103   90
 1.0500E+07 2.7432E-03 1.1000E+07 2.7432E-03 1.1500E+07 2.7432E-03222833103   91
 1.2000E+07 3.1093E-03 1.2500E+07 3.1093E-03 1.3000E+07 3.1093E-03222833103   92
 1.3500E+07 3.1093E-03 1.4000E+07 3.0015E-03 1.4500E+07 3.0015E-03222833103   93
 1.5000E+07 3.0015E-03 1.5500E+07 1.2580E-02 1.6000E+07 3.3545E-03222833103   94
 1.6500E+07 3.3545E-03 1.7000E+07 3.3545E-03 1.7500E+07 3.3545E-03222833103   95
 1.8000E+07 3.2228E-03 1.8500E+07 3.2228E-03 1.9000E+07 3.2228E-03222833103   96
 1.9500E+07 3.2228E-03 2.0000E+07 0.0000E+00 0.0000E+00 0.0000E+00222833103   97
 0.0000E+00 0.0000E+00          0          8         88         44222833103   98
 1.0000E-05 0.0000E+00 8.0000E+05 1.7840E-09 8.5000E+05 1.7944E-09222833103   99
 9.0000E+05 9.4782E-10 1.0000E+06 6.1588E-10 1.5000E+06 6.9313E-09222833103  100
 2.0000E+06 6.6180E-08 2.5000E+06 3.0335E-07 2.7000E+06 2.7625E-07222833103  101
 3.0000E+06 3.4819E-07 3.5000E+06 5.0856E-07 4.0000E+06 9.3419E-07222833103  102
 4.5000E+06 1.8450E-06 5.0000E+06 3.1013E-06 5.5000E+06 3.6005E-06222833103  103
 6.0000E+06 5.7907E-06 6.5000E+06 3.5738E-06 7.0000E+06 4.1828E-06222833103  104
 7.5000E+06 4.9454E-06 8.0000E+06 9.7757E-06 8.5000E+06 6.0984E-06222833103  105
 9.0000E+06 6.5926E-06 9.5000E+06 7.2632E-06 1.0000E+07 5.3544E-06222833103  106
 1.0500E+07 5.4347E-06 1.1000E+07 5.3985E-06 1.1500E+07 5.2463E-06222833103  107
 1.2000E+07 5.6908E-06 1.2500E+07 5.3562E-06 1.3000E+07 5.0318E-06222833103  108
 1.3500E+07 4.7183E-06 1.4000E+07 4.2268E-06 1.4500E+07 3.8407E-06222833103  109
 1.5000E+07 3.4731E-06 1.5500E+07 1.3094E-05 1.6000E+07 3.1245E-06222833103  110
 1.6500E+07 2.8157E-06 1.7000E+07 2.5230E-06 1.7500E+07 2.2418E-06222833103  111
 1.8000E+07 1.9701E-06 1.8500E+07 1.8648E-06 1.9000E+07 1.7624E-06222833103  112
 1.9500E+07 1.6595E-06 2.0000E+07 0.0000E+00 0.0000E+00 0.0000E+00222833103  113
 0.0000E+00 0.0000E+00          0          1          4          2222833103  114
 6.9000E+05 2.2843E-02 8.0000E+05 0.0                             222833103  115
                                                                  222833  099999
                                                                  2228 0  0    0
 2.20470E+4 4.65484E+1          0          0          1          0222840  5    1
-8.23715E+6-8.23715E+6          0          1          0          1222840  5    2
 1.000000+1 1.000000+0          0          5          0          1222840  5    3
 0.000000+0 0.000000+0          1          5        190         19222840  5    4
 1.000000-5 8.400000+6 1.200000+7 1.250000+7 1.300000+7 1.350000+7222840  5    5
 1.400000+7 1.450000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7222840  5    6
 1.700000+7 1.750000+7 1.800000+7 1.850000+7 1.900000+7 1.950000+7222840  5    7
 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222840  5    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222840  5    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222840  5   10
 0.000000+0 8.224320-1 3.047800-2-5.099880-3 2.660400-2 2.567630-2222840  5   11
 8.789060-3-2.089150-4 4.143110-4 5.627230-3 1.120560-2 1.502500-2222840  5   12
 1.653970-2 1.606880-2 1.428180-2 1.189650-2 9.535380-3 7.674830-3222840  5   13
 2.317220-2 1.579900-2 4.911180-3 9.215290-4 7.415560-4 1.566370-3222840  5   14
 2.456920-3 3.187640-3 3.730820-3 4.106900-3 4.345820-3 4.476950-3222840  5   15
 4.526420-3 4.516220-3 4.464290-3 4.384770-3 2.410370-2 1.179110-2222840  5   16
 2.085650-3-4.356060-5 1.197690-3 2.968140-3 4.280220-3 4.991600-3222840  5   17
 5.234730-3 5.189020-3 5.005500-3 4.790790-3 4.611590-3 4.504530-3222840  5   18
 4.485670-3 1.255610-2 7.443600-3 3.314840-3 1.501210-3 1.219560-3222840  5   19
 1.623630-3 2.199950-3 2.702100-3 3.042030-3 3.212750-3 3.242780-3222840  5   20
 3.171400-3 3.036720-3 2.870740-3 7.555650-3 4.699770-3 2.094550-3222840  5   21
 5.902510-4 3.201110-5 5.900340-5 3.656710-4 7.479170-4 1.087880-3222840  5   22
 1.328070-3 1.448730-3 1.451680-3 1.349620-3 3.780760-3 2.278690-3222840  5   23
 1.087240-3 3.782550-4 7.219620-5 3.330810-5 1.404120-4 3.044130-4222840  5   24
 4.669730-4 5.938050-4 6.675780-4 6.820470-4 2.094230-3 1.740670-3222840  5   25
 1.376410-3 1.067600-3 8.374700-4 6.850910-4 5.990970-4 5.649730-4222840  5   26
 5.687140-4 5.983170-4 6.442110-4 2.137400-3 2.230550-3 2.111580-3222840  5   27
 1.877100-3 1.606180-3 1.352240-3 1.146690-3 1.004800-3 9.311090-4222840  5   28
 9.235670-4 2.710740-3 2.837360-3 2.718770-3 2.461500-3 2.152640-3222840  5   29
 1.853540-3 1.602850-3 1.421840-3 1.319530-3 3.190670-3 3.236060-3222840  5   30
 3.076280-3 2.802720-3 2.488110-3 2.183810-3 1.922800-3 1.723960-3222840  5   31
 3.447240-3 3.420070-3 3.236110-3 2.964070-3 2.657910-3 2.356140-3222840  5   32
 2.084160-3 3.528090-3 3.454820-3 3.259670-3 2.991250-3 2.688170-3222840  5   33
 2.378610-3 3.491600-3 3.386500-3 3.181570-3 2.911070-3 2.602730-3222840  5   34
 3.371280-3 3.242790-3 3.031150-3 2.760710-3 3.195830-3 3.061290-3222840  5   35
 2.860660-3 3.016960-3 2.911930-3 2.923980-3                      222840  5   36
                                                                  222840  099999
                                                                  2228 0  0    0
                                                                     0 0  0    0
 2.20480E+4 4.75360E+1          0          0         34         102231 1451    1
 0.0        0.0                 0          0          0          62231 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022231 1451    3
 3.00000E+2 0.0                 1          0        242          72231 1451    4
 22-Ti- 48 FEI        EVAL-Feb02 K.I.Zolotarev                    2231 1451    5
                      DIST-Feb2004                                2231 1451    6
----IRDF-2002         MATERIAL 2231                               2231 1451    7
-----INCIDENT NEUTRON DATA                                        2231 1451    8
------ENDF-6 FORMAT                                               2231 1451    9
***************************************************************** 2231 1451   10
**********************  SPECIAL PURPOSE FILE   *****************  2231 1451   11
DOSIMETRY                                                         2231 1451   12
                                                                  2231 1451   13
 For this special purpose library it was decided the reaction     2231 1451   14
 MF=3 MT=28+104 would use MF=10, MT=5 to present this data.       2231 1451   15
 This was done after processing through the codes. The            2231 1451   16
 co-variance file was converted from MF/MT=33/28 to MF/MT=40/5    2231 1451   17
***************************************************************** 2231 1451   18
 22-TI-48  FEI        EVAL-Feb02 K.I.Zolotarev                    2231 1451   19
                      DIST-Feb02                       20020214   2231 1451   20
----BROND-2           MATERIAL 2231                               2231 1451   21
-----INCIDENT NEUTRON DATA                                        2231 1451   22
------ENDF-6 FORMAT                                               2231 1451   23
------Russian Reactor Dosimetry File RRDF-2002                    2231 1451   24
***************************************************************** 2231 1451   25
Author  of evaluation: K.I.Zolotarev                              2231 1451   26
***************************************************************** 2231 1451   27
MF= 3                                                             2231 1451   28
MT= 28 -(n,np+pn+d) cross section data                            2231 1451   29
--------------------------------------                            2231 1451   30
    In this section is given the sum of cross sections of the re- 2231 1451   31
actions Ti-48(n,np)Sc-47 , Ti-48(n,pn)Sc-47 and Ti-48(n,d)Sc-47.  2231 1451   32
    Excitation function for the  Ti-48(n,x)Sc-47  reaction in the 2231 1451   33
energy region from threshold to 20 MeV was evaluated  by means of 2231 1451   34
statistical analysis  of  experimental cross section data [1-12]  2231 1451   35
and data from STAPRE [13] calculation.                            2231 1451   36
    Analised  experimental  data were corrected  to the new stan- 2231 1451   37
dards for monitor reactions cross sections and decay data.        2231 1451   38
    The final procedure of evaluation Ti-48(n,x)Sc-47  excitation 2231 1451   39
function from threshold to 20 MeV has been carried out within the 2231 1451   40
framework of generalized least squares method.  Rational function 2231 1451   41
was used  as model function [14].  Calculations  was performed by 2231 1451   42
means of Pade-2 code [15].                                        2231 1451   43
     U-235 thermal fission [16] and  Cf-252 spontanious  fission  2231 1451   44
neutron spectra [17] averaged cross-sections calculated from the  2231 1451   45
evaluated Ti-48(n,x)Sc-47 excitation function are the following:  2231 1451   46
                                                                  2231 1451   47
         --------------------------------------------             2231 1451   48
              TYPE OF SPECTRUM     I <CS>, mb (calc.)             2231 1451   49
         --------------------------I-----------------             2231 1451   50
         U-235  neutron  fission   I    1.6558E-3                 2231 1451   51
         CF-252 spontan. fission   I    4.2891E-3                 2231 1451   52
                                                                  2231 1451   53
MT=103 -(n,p) cross section                                       2231 1451   54
-------------------------------------                             2231 1451   55
    Excitation function for the  Ti-48(n,p)Sc-48  reaction in the 2231 1451   56
energy region from threshold to 20 MeV was evaluated by means of  2231 1451   57
of statistical analysis of experimental cross section data [1-2], 2231 1451   58
[4], [6-11], [18-41] and data from STAPRE [13] calculation.       2231 1451   59
    The energy dependence of cross-section from 4.7 MeV to thres- 2231 1451   60
hold was extrapolated  with  L=0  penetrability function  for the 2231 1451   61
the outgoing  p + Sc48  channal [42].                             2231 1451   62
    Analised microscopic experimental data  were  renormalized to 2231 1451   63
the new recommended standards for monitor reaction cross sections 2231 1451   64
and decay data. All experiments performed with Ti-natural samples 2231 1451   65
were  corrected for  the contribution of the  Ti-49(n,np+pn)Sc-48 2231 1451   66
and Ti-49(n,d)Sc-48 reactions. Total cross section for these reac-2231 1451   67
tions were taken from ref. [43]. Experimental data from ref. [24] 2231 1451   68
were used partially. It was taken into account only data measured 2231 1451   69
relative  Fe-56(n,p)Mn-56  monitor reaction.  Data of Firkin  [6] 2231 1451   70
obtained in the experiment with neutrons from  D(d,n)He3 reaction 2231 1451   71
were renormalized  to the results  of his measurements  with 14.1 2231 1451   72
MeV neutrons from T(d,n)He4 reaction. Cross section data of Smith 2231 1451   73
and Meadows [26]  measured in the energy range  5.964 - 9.952 MeV 2231 1451   74
with  using  D(d,n)He3  neutron source  were renormalized  to the 2231 1451   75
value  30.7 mb at 10 MeV [38].  The correction  factors  for  the 2231 1451   76
experimental data  [6] and [26]  were Fc=0.91853 and Fc=1.11111 , 2231 1451   77
respectively                                                      2231 1451   78
    Experimental cross section data [44-51] were rejected  due to 2231 1451   79
their discrepancy with the main bulk  of experimental data [1-2], 2231 1451   80
[4], [6-11], [18-41] and data from theoretical model calculatiod. 2231 1451   81
    Statistical analysis of input cross section data was carried  2231 1451   82
out by means of PADE-2 code [15].  Rational function was used as  2231 1451   83
the model function [14].                                          2231 1451   84
     U-235 thermal fission [16] and  Cf-252 spontanious  fission  2231 1451   85
neutron spectra [17] averaged cross-sections calculated from the  2231 1451   86
evaluated Ti-48(n,p)Sc-48 excitation function are the following:  2231 1451   87
                                                                  2231 1451   88
  2231 1451   89
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  2231 1451   90
  2231 1451   91
 U-235 neutron fission     0.30430        0.305 +- 0.020  [52]  2231 1451   92
                                          0.302 +- 0.010  [53]  2231 1451   93
                                          0.3007+- 0.0054 [54]  2231 1451   94
  2231 1451   95
 Cf-252 spont. fission     0.42629        0.4275+- 0.0078 [55]  2231 1451   96
                                          0.4247+- 0.0080 [56]  2231 1451   97
  2231 1451   98
                                                                  2231 1451   99
MF=33                                                             2231 1451  100
MT= 28 -(n,np+pn+d) cross section cov. matrix                     2231 1451  101
---------------------------------------------                     2231 1451  102
    Uncertainties in the evaluated  excitation function  for  the 2231 1451  103
reaction  Ti-48(n,x)Sc-47 are given in the form of relative cova- 2231 1451  104
riance matrix for the 15-neutron energy groups (LB=5). Covariance 2231 1451  105
matrix  of  uncertainties  was  calculated  simultaneously  with  2231 1451  106
recommended cross section data by means of PADE-2 code.           2231 1451  107
    Eigenvalues  of the  6-th digits  relative covariance matrix  2231 1451  108
given in the 33-file are the following:                           2231 1451  109
                                                                  2231 1451  110
    3.25031E-07    3.96552E-07    7.16579E-07    1.55391E-06      2231 1451  111
    4.04176E-06    1.39260E-05    8.49003E-05    2.17726E-03      2231 1451  112
    8.18710E-03    1.48647E-02    2.37004E-02    3.37652E-02      2231 1451  113
    4.90298E-02    9.66009E-02    5.46438E-01                     2231 1451  114
                                                                  2231 1451  115
MT=103 -(n,p) cross section cov. matrix                           2231 1451  116
---------------------------------------------                     2231 1451  117
    Uncertainties in the evaluated  excitation function  for  the 2231 1451  118
reaction  Ti-48(n,p)Sc-48 are given in the form of relative cova- 2231 1451  119
riance matrix for the 26-neutron energy groups (LB=5). Covariance 2231 1451  120
matrix  of  uncertainties  was  calculated  simultaneously  with  2231 1451  121
recommended cross section data by means of PADE-2 code.           2231 1451  122
    Eigenvalues  of the  6-th digits  relative covariance matrix  2231 1451  123
given in the 33-file are the following:                           2231 1451  124
                                                                  2231 1451  125
    5.39341E-09    5.73858E-09    5.82529E-09    6.42044E-09      2231 1451  126
    6.80480E-09    7.28300E-09    7.51108E-09    8.50118E-09      2231 1451  127
    9.53827E-09    1.09813E-08    1.24867E-08    1.39806E-08      2231 1451  128
    1.87772E-08    2.72244E-08    4.05820E-08    6.49966E-08      2231 1451  129
    1.23779E-07    3.87183E-07    6.43873E-06    1.17950E-03      2231 1451  130
    6.38433E-03    8.03793E-03    1.04937E-02    1.43313E-02      2231 1451  131
    2.41167E-02    3.79706E-02                                    2231 1451  132
                                                                  2231 1451  133
 References :                                                     2231 1451  134
 1. W.G.Cross, H.L.Pai Prog. Report EANDC(CAN)-16, p.1, Jan. 1963 2231 1451  135
 2. H.L.Pai  Canadian J. of Physics, v.44, p.2337, 1966           2231 1451  136
 3. S.M.Grimes et al.  Nucl. Sci. Eng., v.62, p.187, Feb. 1977    2231 1451  137
 4. S.M.Qaim, N.I.Molla  Nucl. Phys., v.A283, p.269, June 1977    2231 1451  138
 5. M.Viennot et al.  Progress Report MOH-5, p.10, 1982           2231 1451  139
 6. S.Firkin  Report AERE-M-3350, Harwell, September 1983         2231 1451  140
 7. I.Ribansky, S.Gmuca  J. Phys.G, v.9, p.1537, December 1983    2231 1451  141
 8. N.I.Molla et al.  Report INDC(BAN)-003, September 1986        2231 1451  142
 9. Y.Ikeda et al.  Report JAERI-1312, March 1988                 2231 1451  143
10. W.V.Hecker et al.  Nucl. Inst. Meth., Sec.B, v.40/41, p.478,  2231 1451  144
    April 1989                                                    2231 1451  145
11. M.Viennot et al.  Nucl. Sci. Eng., v.108, p.289, July 1991    2231 1451  146
12. Y.Uno et al.  Report JAERI-M-93-046, p.247-256, 1993          2231 1451  147
13. M.Uhl, B.Strohmaier Computer Code STAPRE for Particle Induced 2231 1451  148
    Activation Cross Section and Related Quantities, Report       2231 1451  149
    IRK 76-01, Vienna, 1976                                       2231 1451  150
14. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2231 1451  151
    st's Meeting on Evaluation and Processing of Covariance Data, 2231 1451  152
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  2231 1451  153
15. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          2231 1451  154
16. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2231 1451  155
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              2231 1451  156
17. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        2231 1451  157
18. A.Poularikas, R.W.Fink  Physical Review, v.115, p.989, 1959   2231 1451  158
19. F.Gabbard, B.D.Kern  Physical Review, v.128, p.1276, 1962     2231 1451  159
20. M.Hillman  Nucl. Phys., v.37, p.78, 1962                      2231 1451  160
21. M.Bormann et al.  Nucl. Phys., v.63, p.438, March 1965        2231 1451  161
22. V.N.Levkovskij et al.  Yadernaja Fizika (Sov.), v.10, n.1,    2231 1451  162
    p.44, July 1969                                               2231 1451  163
23. S.K.Ghorai et al.  J. Nucl. Energy, v.25, p.319, August 1971  2231 1451  164
24. Y.Lukic, E.E.Carroll  Nucl. Sci. Eng., v.43, p.233, 1971      2231 1451  165
25. J.Prasad, D.C.Sarcar  Nuovo Cimento, v.A3, p.467, June 1971   2231 1451  166
26. D.L.Smith,J.W.Meadows Nucl. Sci. Eng., v.58, p.314, Nov. 1975 2231 1451  167
27. W.Mannhart, H.Vonach   Zeitsch. fur Physik, Sect.A, v.272,    2231 1451  168
    p.279, March 1975                                             2231 1451  169
28. K.Kayashima e.a.  Prog. Report NEANDC(J)-61U, p.94, Sep. 1979 2231 1451  170
29. M.Viennot e.a. Proc. of Int. Conf.on Nuclear Data for Science 2231 1451  171
    and Technology, Antwerpen, Belgium, 6-10 Sep. 1982, p.406     2231 1451  172
30. L.R.Greenwood  Report DOE-ER-0046-21, p.15, May 1985          2231 1451  173
31. R.Pepelnik et al. Progress Report NEANDC(E)-262U, (5), p.32,  2231 1451  174
    June 1985                                                     2231 1451  175
32. J.P.Gupta et al.  Pramana, v.24, p.637, 1985                  2231 1451  176
33. Hoang Dac Luc et al.  Progress Report INDC(VN)-5, Sep. 1986   2231 1451  177
34. K.Kobayashi, I.Kimura  Proc. of an Intern. Conf. on Nuclear   2231 1451  178
    Data for Science and Technology, 30 May - 3 June 1988, Mito,  2231 1451  179
    Japan, Saikon Publishing Co., LTD, pp.261-265, 1989           2231 1451  180
35. Lu Han-Lin et al. Report INDC(CPR)-16, August 1989            2231 1451  181
36. Y.Ikeda et al.  Report JAERI-M-91-032, p.281, March 1991      2231 1451  182
37. M.Viennot et al.  Nucl. Sci. Eng., v.108, p.289, July 1991    2231 1451  183
38. S.M.Qaim et al. Proc. of Int. Conference on Nuclear Data for  2231 1451  184
    Science and Technology, Julich, FRG, 13-17 May 1991. Springer 2231 1451  185
    Verlag, Berlin - Heidelberg, 1992, p.297-300                  2231 1451  186
39. I.Garlea et al.  J. Rev. Roum. Phys., v.37, n.1, p.19, 1992   2231 1451  187
40. Yuan Junqian et al.  High Energy Physics and Nuclear Physics  2231 1451  188
    (China), v.16, n.1, p.57, January 1992                        2231 1451  189
41. A.Grallert et al.  Progress Report,INDC(NDS)-286, p.131, 1993 2231 1451  190
42. S.A.Badikov, A.B.Pashchenko Voprosy Atomnoy Nauki i Tekhniki  2231 1451  191
    Ser. Jadernye Konstanty, 2(53), p.70, 1987                    2231 1451  192
43. K.Zolotarev RRDF-2002, MAT=2243, eval. February 2002          2231 1451  193
44. E.B.Paul, R.L.Clarke  Canadian J. Phys., v.31, p.267, 1953    2231 1451  194
45. D.L.Allan  Nucl. Phys., v.24, p.274, April 1961               2231 1451  195
46. J.E.Strain, W.J.Ross  Report ORNL-3672, January 1965          2231 1451  196
47. H.K.Vonach et al. Proc. of 2-nd Conference on Nuclear Cross-  2231 1451  197
    Sections and Technology, Washington D.C., 4-7 March 1968,     2231 1451  198
    v.2, p.885                                                    2231 1451  199
48. D.Crumpton  J. Inorg. Nucl. Chem., v.31, p.3727, Dec. 1969    2231 1451  200
49. V.K.Tikku et al.  Proc. of Nucl. Phys. and Solid State Phys.  2231 1451  201
    Symp., Chandigarh, v.2, p.115, December 1972                  2231 1451  202
50. R.Spangler et al.  J. Trans. Amer. Nucl. Soc., v.22, p.818,   2231 1451  203
    November 1975                                                 2231 1451  204
51. K.T.Osman, F.I.Habbani  Report, INDC(SUD)-001, October 1996   2231 1451  205
52. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 2231 1451  206
    Washington D.C., 25-28 April 1989, v.2, p.923                 2231 1451  207
53. W.Mannhart  Proc. 5-th ASTM-EUR. Symp. on Reactor Dosimetry,  2231 1451  208
    Geesthacht, FRG, September 24-28, 1984, Vol.2, p.813, 1985    2231 1451  209
54. W.Mannhart  Progress Report INDC(Ger)-045, pp.40-43, 1999     2231 1451  210
55. W.Mannhart  Handbook on Nuclear Activation Cross Sections ,   2231 1451  211
    IAEA Tech. Report Ser. No.273, p.413, 1987                    2231 1451  212
56. W.Mannhart  Validation of Differential Cross Sections with    2231 1451  213
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2231 1451  214
    September 2002                                                2231 1451  215
***************************************************************** 2231 1451  216
 File 2 added to the pointwise file containing only the effective 2231 1451  217
 scattering radius with no resonance parameters given.            2231 1451  218
 Taken from ENDF/B-VI                                             2231 1451  219
***************************************************************** 2231 1451  220
                                                                  2231 1451  221
 ***************** Program LINEAR (VERSION 2002-1) ***************2231 1451  222
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2231 1451  223
 Data Linearized to Within an Accuracy of .100000000 per-cent     2231 1451  224
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2231 1451  225
 Data Doppler Broadened to 300.000000 Kelvin                      2231 1451  226
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2231 1451  227
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2231 1451  228
 ***************** Program FIXUP (Version 2002-1) ****************2231 1451  229
 Corrected ZA/AWR in All Sections-----------------------------Yes 2231 1451  230
 Corrected Thresholds-----------------------------------------Yes 2231 1451  231
 Extended Cross Sections to 20 MeV----------------------------No  2231 1451  232
 Allow Cross Section Deletion---------------------------------No  2231 1451  233
 Allow Cross Section Reconstruction---------------------------No  2231 1451  234
 Make All Cross Sections Non-Negative-------------------------Yes 2231 1451  235
 Delete Energies Not in Ascending Order-----------------------Yes 2231 1451  236
 Deleted Duplicate Points-------------------------------------Yes 2231 1451  237
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2231 1451  238
 Check for Legal MF/MT Numbers--------------------------------Yes 2231 1451  239
 Allow Creation of Missing Sections---------------------------No  2231 1451  240
 Allow Insertion of Energy Points-----------------------------No  2231 1451  241
 Create Uniform Energy Grid-----------------------------------No  2231 1451  242
 Delete Section if Cross Section =0 at All Energies-----------Yes 2231 1451  243
 ***************** Program GROUPIE (VERSION 2002-1) **************2231 1451  244
 Unshielded Group Averages Using  640 Groups                      2231 1451  245
 Weighting Spectrum: Flat (Constant) Spectrum                     2231 1451  246
                                1        451        253          12231 1451  247
                                2        151          4          12231 1451  248
                                3        103         60          12231 1451  249
                                8          5          2          12231 1451  250
                               10          5         39          12231 1451  251
                               33        103         71          12231 1451  252
                               40          5         30          12231 1451  253
                                                                  2231 1  099999
                                                                  2231 0  0    0
 2.20480E+4 4.75360E+1          0          0          1          02231 2151    1
 2.204800+4 1.000000+0          0          0          1          02231 2151    2
 1.000000-5 1.000000-5          0          0          0          02231 2151    3
 0.000000+0 0.573300+0          0          0          0          02231 2151    4
                                                                  2231 2  099999
                                                                  2231 0  0    0
 2.20480E+4 4.75360E+1          0          0          0          02231 3103    1
-3.21180E+6-3.21180E+6          0          0          1        1692231 3103    2
        169          1                                            2231 3103    3
 3200000.00 4.44705E-9 3300000.00 1.46148E-7 3400000.00 3.52717E-72231 3103    4
 3500000.00 5.59287E-7 3600000.00 7.65856E-7 3700000.00 9.72426E-72231 3103    5
 3800000.00 1.17900E-6 3900000.00 1.75487E-6 4000000.00 2.60258E-62231 3103    6
 4100000.00 3.40719E-6 4200000.00 4.52734E-6 4300000.00 6.44311E-62231 3103    7
 4400000.00 9.78106E-6 4500000.00 1.53460E-5 4600000.00 2.41598E-52231 3103    8
 4700000.00 3.75024E-5 4800000.00 5.69529E-5 4900000.00 8.44353E-52231 3103    9
 5000000.00 .000122266 5100000.00 .000173193 5200000.00 .0002404202231 3103   10
 5300000.00 .000327615 5400000.00 .000438894 5500000.00 .0005787552231 3103   11
 5600000.00 .000751970 5700000.00 .000963413 5800000.00 .0012178252231 3103   12
 5900000.00 .001519525 6000000.00 .001872085 6100000.00 .0022779952231 3103   13
 6200000.00 .002738340 6300000.00 .003252590 6400000.00 .0038184952231 3103   14
 6500000.00 .004432120 6600000.00 .005088075 6700000.00 .0057798702231 3103   15
 6800000.00 .006500350 6900000.00 .007244910 7000000.00 .0080010502231 3103   16
 7100000.00 .008760743 7200000.00 .009523988 7300000.00 .0102872332231 3103   17
 7400000.00 .011050478 7500000.00 .011802500 7600000.00 .0125433002231 3103   18
 7700000.00 .013284100 7800000.00 .014013106 7900000.00 .0147303172231 3103   19
 8000000.00 .015447528 8100000.00 .016164739 8200000.00 .0168819502231 3103   20
 8300000.00 .017599161 8400000.00 .018316372 8500000.00 .0190335832231 3103   21
 8600000.00 .019750794 8700000.00 .020481567 8800000.00 .0212259002231 3103   22
 8900000.00 .021970233 9000000.00 .022732733 9100000.00 .0235134002231 3103   23
 9200000.00 .024294067 9300000.00 .025097267 9400000.00 .0259230002231 3103   24
 9500000.00 .026748733 9600000.00 .027599500 9700000.00 .0284753002231 3103   25
 9800000.00 .029351100 9900000.00 .030252433 10000000.0 .0311793002231 3103   26
 10100000.0 .032106167 10200000.0 .033060613 10300000.0 .0340426382231 3103   27
 10400000.0 .035024663 10500000.0 .036006688 10600000.0 .0370165502231 3103   28
 10700000.0 .038054250 10800000.0 .039091950 10900000.0 .0401296502231 3103   29
 11000000.0 .041167350 11100000.0 .042205050 11200000.0 .0432453922231 3103   30
 11300000.0 .044288375 11400000.0 .045331358 11500000.0 .0463743422231 3103   31
 11600000.0 .047417325 11700000.0 .048460308 11800000.0 .0494691382231 3103   32
 11900000.0 .050443813 12000000.0 .051418488 12100000.0 .0523931632231 3103   33
 12200000.0 .053319817 12300000.0 .054198450 12400000.0 .0550770832231 3103   34
 12500000.0 .055898950 12600000.0 .056664050 12700000.0 .0574291502231 3103   35
 12800000.0 .058125350 12900000.0 .058752650 13000000.0 .0593799502231 3103   36
 13100000.0 .059929217 13200000.0 .060400450 13300000.0 .0608716832231 3103   37
 13400000.0 .061259683 13500000.0 .061564450 13600000.0 .0618692172231 3103   38
 13700000.0 .062089767 13800000.0 .062226100 13900000.0 .0623624332231 3103   39
 14000000.0 .062443900 14100000.0 .062418567 14200000.0 .0623413002231 3103   40
 14300000.0 .062264033 14400000.0 .062115133 14500000.0 .0618946002231 3103   41
 14600000.0 .061674067 14700000.0 .061391650 14800000.0 .0610473502231 3103   42
 14900000.0 .060703050 15000000.0 .060300825 15100000.0 .0598406752231 3103   43
 15200000.0 .059380525 15300000.0 .058920375 15400000.0 .0584077502231 3103   44
 15500000.0 .057842650 15600000.0 .057277550 15700000.0 .0567124502231 3103   45
 15800000.0 .056147350 15900000.0 .055545431 16000000.0 .0549066942231 3103   46
 16100000.0 .054267956 16200000.0 .053629219 16300000.0 .0529904812231 3103   47
 16400000.0 .052351744 16500000.0 .051713006 16600000.0 .0510742692231 3103   48
 16700000.0 .050433667 16800000.0 .049791200 16900000.0 .0491487332231 3103   49
 17000000.0 .048506267 17100000.0 .047863800 17200000.0 .0472213332231 3103   50
 17300000.0 .046578867 17400000.0 .045936400 17500000.0 .0452939332231 3103   51
 17600000.0 .044674017 17700000.0 .044076650 17800000.0 .0434792832231 3103   52
 17900000.0 .042881917 18000000.0 .042284550 18100000.0 .0416871832231 3103   53
 18200000.0 .041113110 18300000.0 .040562330 18400000.0 .0400115502231 3103   54
 18500000.0 .039460770 18600000.0 .038909990 18700000.0 .0383818002231 3103   55
 18800000.0 .037876200 18900000.0 .037370600 19000000.0 .0368650002231 3103   56
 19100000.0 .036359400 19200000.0 .035876120 19300000.0 .0354151602231 3103   57
 19400000.0 .034954200 19500000.0 .034493240 19600000.0 .0340322802231 3103   58
 19700000.0 .033588467 19800000.0 .033161800 19900000.0 .0327351332231 3103   59
 20000000.0 0.0                                                   2231 3103   60
                                                                  2231 3  099999
                                                                  2231 0  0    0
 2.20480E+4 4.75360E+1          0          0          1          12231 8  5    1
 2.104700+4 0.000000+0         10          0          0          02231 8  5    2
                                                                  2231 8  099999
                                                                  2231 0  0    0
 2.20480E+4 4.75360E+1          0          0          1          0223110  5    1
-9.22000E+6-9.22000E+6      21047          0          1        107223110  5    2
        107          1                                            223110  5    3
 9400000.00 2.09726E-7 9500000.00 7.70813E-7 9600000.00 1.33742E-6223110  5    4
 9700000.00 1.90403E-6 9800000.00 2.47063E-6 9900000.00 3.03724E-6223110  5    5
 10000000.0 3.60385E-6 10100000.0 4.17046E-6 10200000.0 5.32343E-6223110  5    6
 10300000.0 6.96840E-6 10400000.0 8.47552E-6 10500000.0 9.97182E-6223110  5    7
 10600000.0 1.16052E-5 10700000.0 1.35478E-5 10800000.0 1.59992E-5223110  5    8
 10900000.0 1.91905E-5 11000000.0 2.33890E-5 11100000.0 2.89037E-5223110  5    9
 11200000.0 3.60910E-5 11300000.0 4.53630E-5 11400000.0 5.71957E-5223110  5   10
 11500000.0 7.21354E-5 11600000.0 9.08205E-5 11700000.0 .000113983223110  5   11
 11800000.0 .000142472 11900000.0 .000177270 12000000.0 .000219511223110  5   12
 12100000.0 .000270512 12200000.0 .000331792 12300000.0 .000405106223110  5   13
 12400000.0 .000492478 12500000.0 .000596228 12600000.0 .000719007223110  5   14
 12700000.0 .000863820 12800000.0 .001034037 12900000.0 .001233390223110  5   15
 13000000.0 .001465935 13100000.0 .001735970 13200000.0 .002047895223110  5   16
 13300000.0 .002406025 13400000.0 .002814295 13500000.0 .003275920223110  5   17
 13600000.0 .003793045 13700000.0 .004366360 13800000.0 .004994865223110  5   18
 13900000.0 .005675790 14000000.0 .006404750 14100000.0 .007176215223110  5   19
 14200000.0 .007984180 14300000.0 .008822960 14400000.0 .009687995223110  5   20
 14500000.0 .010576400 14600000.0 .011487400 14700000.0 .012422300223110  5   21
 14800000.0 .013384250 14900000.0 .014377950 15000000.0 .015409200223110  5   22
 15100000.0 .016484400 15200000.0 .017610150 15300000.0 .018793050223110  5   23
 15400000.0 .020039300 15500000.0 .021354500 15600000.0 .022743650223110  5   24
 15700000.0 .024211050 15800000.0 .025760250 15900000.0 .027393950223110  5   25
 16000000.0 .029113900 16100000.0 .030921100 16200000.0 .032815650223110  5   26
 16300000.0 .034796700 16400000.0 .036862600 16500000.0 .039030075223110  5   27
 16600000.0 .041257225 16700000.0 .043556600 16800000.0 .045928200223110  5   28
 16900000.0 .048360800 17000000.0 .050854400 17100000.0 .053404250223110  5   29
 17200000.0 .056010350 17300000.0 .058616450 17400000.0 .061256300223110  5   30
 17500000.0 .063929900 17600000.0 .066603500 17700000.0 .069277100223110  5   31
 17800000.0 .071950700 17900000.0 .074624300 18000000.0 .077297900223110  5   32
 18100000.0 .079971500 18200000.0 .082581663 18300000.0 .085128388223110  5   33
 18400000.0 .087675113 18500000.0 .090221838 18600000.0 .092692467223110  5   34
 18700000.0 .095087000 18800000.0 .097481533 18900000.0 .099789075223110  5   35
 19000000.0 .102009625 19100000.0 .104230175 19200000.0 .106450725223110  5   36
 19300000.0 .108572375 19400000.0 .110595125 19500000.0 .112617875223110  5   37
 19600000.0 .114640625 19700000.0 .116584333 19800000.0 .118449000223110  5   38
 19900000.0 .120313667 20000000.0 0.0                             223110  5   39
                                                                  223110  099999
                                                                  2231 0  0    0
 2.20480E+4 4.75360E+1          0          0          0          1223133103    1
 0.000000+0 0.000000+0          0        103          0          1223133103    2
 0.000000+0 0.000000+0          1          5        406         28223133103    3
 1.000000-5 3.200000+6 6.000000+6 6.500000+6 7.000000+6 7.500000+6223133103    4
 8.000000+6 8.500000+6 9.000000+6 9.500000+6 1.000000+7 1.050000+7223133103    5
 1.100000+7 1.150000+7 1.200000+7 1.250000+7 1.300000+7 1.350000+7223133103    6
 1.400000+7 1.450000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7223133103    7
 1.700000+7 1.800000+7 1.900000+7 2.000000+7 0.000000+0 0.000000+0223133103    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223133103    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223133103   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223133103   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223133103   12
 0.000000+0 1.244150-2 7.346840-3 3.817820-3 2.023600-3 1.670350-3223133103   13
 1.914370-3 2.193410-3 2.302740-3 2.218330-3 1.979000-3 1.639120-3223133103   14
 1.253720-3 8.737600-4 5.426420-4 2.916640-4 1.355170-4 7.050570-5223133103   15
 7.734160-5 1.278750-4 1.929260-4 2.482490-4 2.773030-4 2.712070-4223133103   16
 1.881820-4-3.611490-5-3.653190-4 7.757040-3 6.098810-3 4.154940-3223133103   17
 2.757920-3 2.029510-3 1.740490-3 1.661580-3 1.649290-3 1.626740-3223133103   18
 1.556430-3 1.424190-3 1.231820-3 9.938690-4 7.346730-4 4.837150-4223133103   19
 2.692840-4 1.123370-4 2.294990-5 4.162250-7 3.615880-5 1.176120-4223133103   20
 2.315270-4 4.363480-4 7.328280-4 1.020310-3 6.503610-3 5.489650-3223133103   21
 3.976130-3 2.699250-3 1.867760-3 1.414650-3 1.213220-3 1.152120-3223133103   22
 1.147310-3 1.138840-3 1.087580-3 9.745160-4 8.006670-4 5.850100-4223133103   23
 3.585880-4 1.556880-4 5.163970-6-7.495940-5-7.848490-5-8.736890-6223133103   24
 1.250630-4 4.204940-4 9.271180-4 1.503660-3 5.552780-3 4.728610-3223133103   25
 3.677500-3 2.763700-3 2.078490-3 1.597730-3 1.269150-3 1.042580-3223133103   26
 8.773390-4 7.431170-4 6.198910-4 4.976790-4 3.756340-4 2.597860-4223133103   27
 1.595420-4 8.401720-5 3.941690-5 2.808660-5 4.893890-5 9.857880-5223133103   28
 2.175880-4 4.321980-4 6.863320-4 4.790110-3 4.371670-3 3.743620-3223133103   29
 3.070070-3 2.427020-3 1.846360-3 1.342280-3 9.227950-4 5.930010-4223133103   30
 3.544680-4 2.030560-4 1.273520-4 1.091970-4 1.266340-4 1.581090-4223133103   31
 1.860910-4 1.988820-4 1.905280-4 1.595630-4 7.340970-5-9.489670-5223133103   32
-3.035830-4 4.559690-3 4.328510-3 3.834850-3 3.204670-3 2.525770-3223133103   33
 1.860850-3 1.258050-3 7.551470-4 3.784270-4 1.388780-4 2.896740-5223133103   34
 2.339780-5 8.492700-5 1.733170-4 2.536830-4 3.013780-4 3.028680-4223133103   35
 2.538460-4 8.842740-5-2.600790-4-7.124240-4 4.443610-3 4.193460-3223133103   36
 3.704470-3 3.080450-3 2.402690-3 1.737410-3 1.139940-3 6.539380-4223133103   37
 3.068680-4 1.051810-4 3.310610-5 5.730040-5 1.360700-4 2.293020-4223133103   38
 3.054380-4 3.441220-4 3.353790-4 2.263220-4-6.184520-5-4.772290-4223133103   39
 4.184480-3 3.901610-3 3.433910-3 2.855910-3 2.231760-3 1.619200-3223133103   40
 1.069660-3 6.241580-4 3.072850-4 1.229730-4 5.521990-5 7.418210-5223133103   41
 1.449290-4 2.352440-4 3.202190-4 3.834970-4 4.158710-4 3.503750-4223133103   42
 1.706540-4 3.841480-3 3.579830-3 3.168340-3 2.655440-3 2.090130-3223133103   43
 1.523280-3 1.004800-3 5.770040-4 2.671880-4 8.324800-5 1.472830-5223133103   44
 3.861770-5 1.268670-4 2.526630-4 3.940650-4 5.981290-4 8.250830-4223133103   45
 9.753670-4 3.533590-3 3.316190-3 2.953300-3 2.478450-3 1.935820-3223133103   46
 1.378990-3 8.644510-4 4.414440-4 1.425100-4-2.100990-5-5.701670-5223133103   47
 1.375670-5 1.651580-4 3.714370-4 7.336580-4 1.246250-3 1.732250-3223133103   48
 3.289420-3 3.089100-3 2.730660-3 2.247570-3 1.691990-3 1.128910-3223133103   49
 6.243380-4 2.317070-4-1.757530-5-1.160950-4-7.567700-5 8.046170-5223133103   50
 3.251350-4 8.001730-4 1.534130-3 2.293640-3 3.042310-3 2.810680-3223133103   51
 2.415160-3 1.901810-3 1.337270-3 7.964780-4 3.467360-4 3.457190-5223133103   52
-1.195210-4-1.182760-4 1.987030-5 2.689400-4 7.909510-4 1.642760-3223133103   53
 2.565630-3 2.702120-3 2.413220-3 1.980270-3 1.464370-3 9.402680-4223133103   54
 4.799640-4 1.379780-4-5.622000-5-9.732580-5 2.238020-6 2.202720-4223133103   55
 7.149690-4 1.561400-3 2.510920-3 2.239130-3 1.916880-3 1.495720-3223133103   56
 1.041080-3 6.199920-4 2.868080-4 7.473390-5-4.977680-6 4.173930-5223133103   57
 1.985470-4 5.968160-4 1.317270-3 2.154950-3 1.722740-3 1.430710-3223133103   58
 1.089500-3 7.526010-4 4.664730-4 2.625740-4 1.553380-4 1.449180-4223133103   59
 2.220540-4 4.739210-4 9.741100-4 1.586440-3 1.284100-3 1.083510-3223133103   60
 8.630930-4 6.555010-4 4.857210-4 3.683870-4 3.084850-4 3.039140-4223133103   61
 3.897200-4 6.216970-4 9.436640-4 1.029260-3 9.394040-4 8.298590-4223133103   62
 7.159590-4 6.098560-4 5.194640-4 4.487370-4 3.839040-4 3.563470-4223133103   63
 3.847270-4 9.747120-4 9.683430-4 9.248700-4 8.519660-4 7.582400-4223133103   64
 6.516400-4 4.833150-4 2.585650-4 5.063660-5 1.056860-3 1.089950-3223133103   65
 1.069780-3 1.003410-3 9.001680-4 6.972650-4 3.769060-4 3.602680-5223133103   66
 1.198100-3 1.245680-3 1.236370-3 1.178080-3 1.018650-3 7.236530-4223133103   67
 3.779790-4 1.370840-3 1.444020-3 1.469220-3 1.429200-3 1.281260-3223133103   68
 1.063020-3 1.619290-3 1.760150-3 1.905790-3 2.014100-3 2.044310-3223133103   69
 2.041250-3 2.425520-3 2.879870-3 3.259940-3 3.234920-3 4.327790-3223133103   70
 5.371820-3 6.404900-3 8.492620-3 1.170350-2                      223133103   71
                                                                  223133  099999
                                                                  2231 0  0    0
 2.20480E+4 4.75360E+1          0          0          1          0223140  5    1
-9.22000E+6-9.22000E+6          0          1          0          1223140  5    2
 1.000000+1 1.000000+0          0          5          0          1223140  5    3
 0.000000+0 0.000000+0          1          5        153         17223140  5    4
 1.000000-5 9.400000+6 1.300000+7 1.350000+7 1.400000+7 1.450000+7223140  5    5
 1.500000+7 1.550000+7 1.600000+7 1.650000+7 1.700000+7 1.750000+7223140  5    6
 1.800000+7 1.850000+7 1.900000+7 1.950000+7 2.000000+7 0.000000+0223140  5    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223140  5    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223140  5    9
 0.000000+0 0.000000+0 0.000000+0 4.707110-1 1.759780-1 1.697230-2223140  5   10
-8.146730-3 1.038100-2-5.224470-3-2.034860-2-1.446150-2-9.242090-4223140  5   11
 6.358550-3 3.918520-3-4.555240-3-1.358030-2-1.920200-2-1.987550-2223140  5   12
 1.052700-1 2.855580-2-1.423330-3 4.824040-3 5.676170-3-7.073830-4223140  5   13
-3.600630-3-2.063640-3 5.308030-4 1.841570-3 1.461860-3 1.058170-4223140  5   14
-1.304640-3-2.135350-3 2.285560-2 7.762240-3 1.086850-3 2.996610-3223140  5   15
 4.013350-3 2.410030-3 5.183160-4-1.889870-4 3.334230-4 1.449850-3223140  5   16
 2.490700-3 3.052080-3 3.021780-3 1.008370-2 4.078560-3-7.285120-4223140  5   17
-1.046370-3 3.213810-4 1.205820-3 1.175750-3 5.878370-4-9.490980-5223140  5   18
-5.712350-4-7.367790-4-6.212280-4 8.396540-3 7.438880-3 3.738740-3223140  5   19
 1.061670-3 2.405110-4 6.122910-4 1.371180-3 2.005320-3 2.316480-3223140  5   20
 2.311780-3 2.087370-3 1.621120-2 1.515040-2 8.632830-3 3.121490-3223140  5   21
 1.138420-3 2.178660-3 4.619640-3 6.965430-3 8.348450-3 8.521370-3223140  5   22
 1.895660-2 1.478520-2 8.727250-3 4.770970-3 3.793980-3 4.917860-3223140  5   23
 6.814000-3 8.444710-3 9.280860-3 1.554920-2 1.270370-2 8.999380-3223140  5   24
 6.138550-3 4.681970-3 4.463460-3 5.026080-3 5.915220-3 1.336970-2223140  5   25
 1.145390-2 8.468040-3 5.709430-3 3.904690-3 3.230420-3 3.514540-3223140  5   26
 1.161810-2 1.015980-2 8.083180-3 6.198510-3 4.939490-3 4.404970-3223140  5   27
 1.095260-2 1.089590-2 1.022320-2 9.212560-3 8.099470-3 1.315310-2223140  5   28
 1.425810-2 1.409830-2 1.289180-2 1.700900-2 1.794020-2 1.714270-2223140  5   29
 1.989720-2 1.988000-2 2.083550-2                                 223140  5   30
                                                                  223140  099999
                                                                  2231 0  0    0
                                                                     0 0  0    0
 2.20490E+4 4.85274E+1          0          0         34         202234 1451    1
 0.0        0.0                 0          0          0          62234 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022234 1451    3
 3.00000E+2 0.0                 1          0        116          52234 1451    4
 22-Ti- 49 FEI        EVAL-Feb02 K.I.Zolotarev                    2234 1451    5
                      DIST-Feb2004                                2234 1451    6
----IRDF-2002         MATERIAL 2234                               2234 1451    7
-----INCIDENT NEUTRON DATA                                        2234 1451    8
------ENDF-6 FORMAT                                               2234 1451    9
***************************************************************** 2234 1451   10
**********************  SPECIAL PURPOSE FILE   *****************  2234 1451   11
DOSIMETRY                                                         2234 1451   12
                                                                  2234 1451   13
 For this special purpose library it was decided the reaction     2234 1451   14
 MF=3 MT=28+104 would use MF=10, MT=5 to present this data.       2234 1451   15
 This was done after processing through the codes. The            2234 1451   16
 co-variance file was converted from MF/MT=33/28 to MF/MT=40/5    2234 1451   17
***************************************************************** 2234 1451   18
 22-TI-49  FEI        EVAL-Feb02 K.I.Zolotarev                    2234 1451   19
                      DIST-Feb02                                  2234 1451   20
----BROND-2           MATERIAL 2234                               2234 1451   21
-----INCIDENT NEUTRON DATA                                        2234 1451   22
------ENDF-6 FORMAT                                               2234 1451   23
------Russian Reactor Dosimetry File RRDF-2002                    2234 1451   24
***************************************************************** 2234 1451   25
Author  of evaluation: K.I.Zolotarev                              2234 1451   26
***************************************************************** 2234 1451   27
MF= 3                                                             2234 1451   28
MT= 28 -(n,np+pn+d) cross section data                            2234 1451   29
--------------------------------------                            2234 1451   30
    In this section is given the sum of cross section of the reac-2234 1451   31
tions Ti-49(n,np)Sc-48 , Ti-49(n,pn)Sc-48 and Ti-49(n,d)Sc-48.    2234 1451   32
    Excitation function for the  Ti-49(n,x)Sc-48  reaction in the 2234 1451   33
energy region from threshold to 20 MeV was evaluated  by means of 2234 1451   34
statistical analysis of experimental cross section data [1-5] and 2234 1451   35
data from STAPRE [6] calculation.                                 2234 1451   36
    Analysed experimental data were renormalized to the new stan- 2234 1451   37
dards for monitor reactions cross sections  and decay data.  Data 2234 1451   38
of Pai [2]  measured in the energy  region 16-19.5 MeV with using 2234 1451   39
Van de Graaff accelerator  were  renormalized  to the results  of 2234 1451   40
the theoretical model calculation.                                2234 1451   41
    The final procedure of evaluation Ti-49(n,x)Sc-48  excitation 2234 1451   42
function from threshold to 20 MeV has been carried out within the 2234 1451   43
framework of generalized least squares method.  Rational function 2234 1451   44
was used  as  model function [7].  Calculations  was performed by 2234 1451   45
means of  Pade-2 code [8].                                        2234 1451   46
    U-235 thermal fission [9]  and   Cf-252 spontaneous  fission  2234 1451   47
neutron spectra [10] averaged cross-sections calculated from the  2234 1451   48
evaluated Ti-49(n,x)Sc-48  excitation function are the following: 2234 1451   49
                                                                  2234 1451   50
         --------------------------------------------             2234 1451   51
              TYPE OF SPECTRUM     I <CS>, mb (calc.)             2234 1451   52
         --------------------------I-----------------             2234 1451   53
         U-235  neutron  fission   I    1.0041E-3                 2234 1451   54
         CF-252 spontan. fission   I    2.6070E-3                 2234 1451   55
                                                                  2234 1451   56
MF=33                                                             2234 1451   57
MT= 28 -(n,np+pn+d) cross section cov. matrix                     2234 1451   58
---------------------------------------------                     2234 1451   59
    Uncertainties in the evaluated  excitation function  for  the 2234 1451   60
reaction  Ti-49(n,x)Sc-48 are given in the form of relative cova- 2234 1451   61
riance matrix for the 14-neutron energy groups (LB=5). Covariance 2234 1451   62
matrix  of  uncertainties  was  calculated  simultaneously  with  2234 1451   63
recommended cross section data by means of PADE-2 code.           2234 1451   64
    Eigenvalues  of the  6-th digits  relative covariance matrix  2234 1451   65
given in the 33-file are the following:                           2234 1451   66
                                                                  2234 1451   67
    2.34704E-08    3.44912E-08    5.30971E-08    9.47934E-08      2234 1451   68
    1.99158E-07    5.01449E-07    1.49592E-06    5.55617E-06      2234 1451   69
    1.56887E-04    2.23251E-03    8.77261E-03    1.50447E-02      2234 1451   70
    3.12585E-02    8.36148E-02                                    2234 1451   71
                                                                  2234 1451   72
 References :                                                     2234 1451   73
 1. W.G.Cross, H.L.Pai  Progress Report, EANDC(CAN)-16, p.1,      2234 1451   74
    January 1963                                                  2234 1451   75
 2. H.L.Pai  Canadian J. of Physics, v.44, p.2337, 1966           2234 1451   76
 3. S.M.Qaim   Nucl. Phys., v.A382, n.2, p.255, July 1982         2234 1451   77
 4. I.Ribansky, S.Gmuca  J. Phys.G, v.9, p.1537, December 1983    2234 1451   78
 5. Y.Ikeda et al.  Report JAERI-1312, March 1988                 2234 1451   79
 6. M.Uhl, B.Strohmaier Computer Code STAPRE for Particle Induced 2234 1451   80
    Activation Cross Section and Related Quantities, Report       2234 1451   81
    IRK 76-01, Vienna, 1976                                       2234 1451   82
 7. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2234 1451   83
    st's Meeting on Evaluation and Processing of Covariance Data, 2234 1451   84
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  2234 1451   85
 8. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          2234 1451   86
 9. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2234 1451   87
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              2234 1451   88
10. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        2234 1451   89
***************************************************************** 2234 1451   90
 File 2 added to the pointwise file containing only the effective 2234 1451   91
 scattering radius with no resonance parameters given.            2234 1451   92
 Taken from JENDL-3.2                                             2234 1451   93
***************************************************************** 2234 1451   94
                                                                  2234 1451   95
 ***************** Program LINEAR (VERSION 2002-1) ***************2234 1451   96
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2234 1451   97
 Data Linearized to Within an Accuracy of .100000000 per-cent     2234 1451   98
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2234 1451   99
 Data Doppler Broadened to 300.000000 Kelvin                      2234 1451  100
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2234 1451  101
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2234 1451  102
 ***************** Program FIXUP (Version 2002-1) ****************2234 1451  103
 Corrected ZA/AWR in All Sections-----------------------------Yes 2234 1451  104
 Corrected Thresholds-----------------------------------------Yes 2234 1451  105
 Extended Cross Sections to 20 MeV----------------------------No  2234 1451  106
 Allow Cross Section Deletion---------------------------------No  2234 1451  107
 Allow Cross Section Reconstruction---------------------------No  2234 1451  108
 Make All Cross Sections Non-Negative-------------------------Yes 2234 1451  109
 Delete Energies Not in Ascending Order-----------------------Yes 2234 1451  110
 Deleted Duplicate Points-------------------------------------Yes 2234 1451  111
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2234 1451  112
 Check for Legal MF/MT Numbers--------------------------------Yes 2234 1451  113
 Allow Creation of Missing Sections---------------------------No  2234 1451  114
 Allow Insertion of Energy Points-----------------------------No  2234 1451  115
 Create Uniform Energy Grid-----------------------------------No  2234 1451  116
 Delete Section if Cross Section =0 at All Energies-----------Yes 2234 1451  117
 ***************** Program GROUPIE (VERSION 2002-1) **************2234 1451  118
 Unshielded Group Averages Using  640 Groups                      2234 1451  119
 Weighting Spectrum: Flat (Constant) Spectrum                     2234 1451  120
                                1        451        125          12234 1451  121
                                2        151          4          12234 1451  122
                                8          5          2          12234 1451  123
                               10          5         39          12234 1451  124
                               40          5         27          12234 1451  125
                                                                  2234 1  099999
                                                                  2234 0  0    0
 2.20490E+4 4.85274E+1          0          0          1          02234 2151    1
 2.20490+ 4 1.00000+ 0          0          0          1          02234 2151    2
 1.00000- 5 1.00000+ 5          0          0          0          02234 2151    3
 3.50000+ 0 4.50000- 1          0          0          0          02234 2151    4
                                                                  2234 2  099999
                                                                  2234 0  0    0
 2.20490E+4 4.85274E+1          0          0          1          12234 8  5    1
 2.104800+4 0.000000+0         10          0          0          02234 8  5    2
                                                                  2234 8  099999
                                                                  2234 0  0    0
 2.20490E+4 4.85274E+1          0          0          1          0223410  5    1
-9.12956E+6-9.12956E+6      21048          0          1        108223410  5    2
        108          1                                            223410  5    3
 9300000.00 1.10601E-9 9400000.00 4.31560E-9 9500000.00 7.57585E-9223410  5    4
 9600000.00 1.08361E-8 9700000.00 1.40964E-8 9800000.00 1.73566E-8223410  5    5
 9900000.00 2.06169E-8 10000000.0 4.97413E-8 10100000.0 1.04730E-7223410  5    6
 10200000.0 1.59719E-7 10300000.0 2.14707E-7 10400000.0 2.69696E-7223410  5    7
 10500000.0 7.67187E-7 10600000.0 1.70718E-6 10700000.0 2.64718E-6223410  5    8
 10800000.0 3.58717E-6 10900000.0 4.52716E-6 11000000.0 6.74413E-6223410  5    9
 11100000.0 1.09550E-5 11200000.0 1.67516E-5 11300000.0 2.44527E-5223410  5   10
 11400000.0 3.44093E-5 11500000.0 4.70069E-5 11600000.0 6.26681E-5223410  5   11
 11700000.0 8.18556E-5 11800000.0 .000105075 11900000.0 .000132876223410  5   12
 12000000.0 .000165858 12100000.0 .000204674 12200000.0 .000250028223410  5   13
 12300000.0 .000302684 12400000.0 .000363468 12500000.0 .000433267223410  5   14
 12600000.0 .000513036 12700000.0 .000603801 12800000.0 .000706656223410  5   15
 12900000.0 .000822770 13000000.0 .000953387 13100000.0 .001099825223410  5   16
 13200000.0 .001263485 13300000.0 .001445825 13400000.0 .001648390223410  5   17
 13500000.0 .001872795 13600000.0 .002120700 13700000.0 .002393845223410  5   18
 13800000.0 .002694020 13900000.0 .003023020 14000000.0 .003382710223410  5   19
 14100000.0 .003774980 14200000.0 .004201675 14300000.0 .004664635223410  5   20
 14400000.0 .005165665 14500000.0 .005706495 14600000.0 .006288770223410  5   21
 14700000.0 .006914025 14800000.0 .007583640 14900000.0 .008298825223410  5   22
 15000000.0 .009060585 15100000.0 .009869710 15200000.0 .010726650223410  5   23
 15300000.0 .011631650 15400000.0 .012584700 15500000.0 .013585300223410  5   24
 15600000.0 .014632650 15700000.0 .015725600 15800000.0 .016862750223410  5   25
 15900000.0 .018042250 16000000.0 .019270825 16100000.0 .020527875223410  5   26
 16200000.0 .021818075 16300000.0 .023141425 16400000.0 .024496200223410  5   27
 16500000.0 .025882400 16600000.0 .027268600 16700000.0 .028676978223410  5   28
 16800000.0 .030107533 16900000.0 .031538089 17000000.0 .032968644223410  5   29
 17100000.0 .034399200 17200000.0 .035829756 17300000.0 .037260311223410  5   30
 17400000.0 .038690867 17500000.0 .040121422 17600000.0 .041516575223410  5   31
 17700000.0 .042876325 17800000.0 .044236075 17900000.0 .045595825223410  5   32
 18000000.0 .046914233 18100000.0 .048191300 18200000.0 .049468367223410  5   33
 18300000.0 .050704483 18400000.0 .051899650 18500000.0 .053094817223410  5   34
 18600000.0 .054247567 18700000.0 .055357900 18800000.0 .056468233223410  5   35
 18900000.0 .057530588 19000000.0 .058544963 19100000.0 .059559338223410  5   36
 19200000.0 .060573713 19300000.0 .061538125 19400000.0 .062452575223410  5   37
 19500000.0 .063367025 19600000.0 .064281475 19700000.0 .065157833223410  5   38
 19800000.0 .065996100 19900000.0 .066834367 20000000.0 0.0       223410  5   39
                                                                  223410  099999
                                                                  2234 0  0    0
 2.20490E+4 4.85274E+1          0          0          1          0223440  5    1
-9.12956E+6-9.12956E+6          0          1          0          1223440  5    2
 1.000000+1 1.000000+0          0          5          0          1223440  5    3
 0.000000+0 0.000000+0          1          5        136         16223440  5    4
 1.000000-5 9.300000+6 1.350000+7 1.400000+7 1.450000+7 1.500000+7223440  5    5
 1.550000+7 1.600000+7 1.650000+7 1.700000+7 1.750000+7 1.800000+7223440  5    6
 1.850000+7 1.900000+7 1.950000+7 2.000000+7 0.000000+0 0.000000+0223440  5    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223440  5    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223440  5    9
 0.000000+0 2.340470-2 1.573760-2 1.165090-2 8.156660-3 5.541340-3223440  5   10
 3.969430-3 3.457650-3 3.824990-3 4.757050-3 5.897230-3 6.966960-3223440  5   11
 7.813930-3 8.420550-3 8.858660-3 1.315090-2 1.087230-2 8.474760-3223440  5   12
 6.164580-3 4.207140-3 2.837340-3 2.197190-3 2.273200-3 2.909620-3223440  5   13
 3.862550-3 4.881200-3 5.757010-3 6.348110-3 9.682370-3 8.120140-3223440  5   14
 6.337310-3 4.558730-3 3.043450-3 2.025410-3 1.624510-3 1.820480-3223440  5   15
 2.467110-3 3.358720-3 4.283100-3 5.063930-3 7.358580-3 6.232520-3223440  5   16
 4.886070-3 3.524410-3 2.383810-3 1.652690-3 1.421190-3 1.664730-3223440  5   17
 2.277620-3 3.115020-3 4.034000-3 5.813390-3 5.091770-3 4.162120-3223440  5   18
 3.178860-3 2.326160-3 1.761320-3 1.580970-3 1.811250-3 2.427040-3223440  5   19
 3.374180-3 5.065940-3 4.757790-3 4.186930-3 3.465820-3 2.759470-3223440  5   20
 2.250120-3 2.087010-3 2.377510-3 3.180650-3 5.131690-3 5.149110-3223440  5   21
 4.804660-3 4.208600-3 3.567080-3 3.106570-3 3.039490-3 3.527780-3223440  5   22
 5.806850-3 6.020090-3 5.794240-3 5.284890-3 4.721960-3 4.359860-3223440  5   23
 4.419540-3 6.857770-3 7.193930-3 7.072420-3 6.651570-3 6.153380-3223440  5   24
 5.798070-3 8.165580-3 8.611450-3 8.566600-3 8.159510-3 7.554320-3223440  5   25
 9.678720-3 1.017690-2 1.011670-2 9.575680-3 1.129210-2 1.182470-2223440  5   26
 1.177030-2 1.316420-2 1.408870-2 1.651520-2                      223440  5   27
                                                                  223440  099999
                                                                  2234 0  0    0
                                                                     0 0  0    0
 2.30510E+4 5.05063E+1          0          0         34         102328 1451    1
 0.0        0.0                 0          0          0          62328 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022328 1451    3
 3.00000E+2 0.0                 1          0        185          42328 1451    4
 23-V - 51 FEI        EVAL-Dec01 K.I.Zolotarev                    2328 1451    5
                      DIST-Feb2004                                2328 1451    6
----IRDF-2002         MATERIAL 2328                               2328 1451    7
-----INCIDENT NEUTRON DATA                                        2328 1451    8
------ENDF-6 FORMAT                                               2328 1451    9
***************************************************************** 2328 1451   10
 23-V-51   FEI        EVAL-Dec01 K.I.Zolotarev                    2328 1451   11
                      DIST-Jan02                       20020118   2328 1451   12
----BROND-2           MATERIAL 2328                               2328 1451   13
-----INCIDENT NEUTRON DATA                                        2328 1451   14
------ENDF-6 FORMAT                                               2328 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    2328 1451   16
***************************************************************** 2328 1451   17
Author  of evaluation: K.I.Zolotarev                              2328 1451   18
***************************************************************** 2328 1451   19
MF=3                                                              2328 1451   20
MT=107 -(n,a) cross section                                       2328 1451   21
-------------------------------------                             2328 1451   22
    Excitation function for the  V-51(n,a)Sc-48  reaction in the  2328 1451   23
energy region from threshold to 20 MeV was evaluated by means of  2328 1451   24
statistical analysis of  experimental cross section  data [1-21]  2328 1451   25
and data from GNASH calculation [45].                             2328 1451   26
    All analysed microscopic experimental data [1-38] and integ-  2328 1451   27
ral experimental data [39-44] were renormalized to the new recom- 2328 1451   28
mended standards for monitor reactions cross sections and decay   2328 1451   29
data.                                                             2328 1451   30
    Experimental cross section data from ref. [22-38] were rejec- 2328 1451   31
ted due to their big discrepancy with the main bulk of experimen- 2328 1451   32
al data [1-21], data from theoretical model calculation and data  2328 1451   33
from (n,a) cross section systematics.                             2328 1451   34
    Statistical analysis of input cross section data was carried  2328 1451   35
out by means of PADE-2 code [46].  Rational function was used as  2328 1451   36
the model function [47].                                          2328 1451   37
    The evaluated   V-51(n,a)Sc-48   excitation function averaged 2328 1451   38
on  U-235  neutron fission spectrum [48]  and  Cf-252 spontaneous 2328 1451   39
fission neutron spectrum [49] gives the next values :             2328 1451   40
  2328 1451   41
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  2328 1451   42
  2328 1451   43
 U-235 neutron fission    0.024414       0.0235 +-0.0015  [40]  2328 1451   44
                                         0.0215 +-0.0013  [41]  2328 1451   45
                                         0.02438+-0.00056 [42]  2328 1451   46
  2328 1451   47
 CF-252 spont. fission    0.038514       0.03904+-0.00086 [43]  2328 1451   48
  2328 1451   49
                                                                  2328 1451   50
MF=33                                                             2328 1451   51
MT=107 -(n,a) cross section cov. matrix                           2328 1451   52
---------------------------------------                           2328 1451   53
    Uncertainties in the evaluated  excitation function  for the  2328 1451   54
reaction V-51(n,a)Sc-48 are given in the form of relative covari- 2328 1451   55
ance matrix for the  26-neutron energy groups (LB=5).  Covariance 2328 1451   56
matrix of uncertainties was calculated simultaneously with recom- 2328 1451   57
mended cross section data by means of PADE-2 code.                2328 1451   58
    Eigenvalues  of the  6-th digits  relative covariance matrix  2328 1451   59
given in the 33-file are the following:                           2328 1451   60
                                                                  2328 1451   61
    4.46067E-09    4.97872E-09    5.09809E-09    5.50951E-09      2328 1451   62
    6.22582E-09    6.26808E-09    6.80068E-09    7.58613E-09      2328 1451   63
    9.63723E-09    1.29149E-08    1.82432E-08    2.72742E-08      2328 1451   64
    4.31460E-08    7.37989E-08    1.54144E-07    3.75108E-07      2328 1451   65
    2.13791E-06    1.13740E-04    6.78127E-04    9.37900E-04      2328 1451   66
    1.40076E-03    2.54577E-03    4.01102E-03    5.22789E-03      2328 1451   67
    1.00172E-02    1.34609E-02                                    2328 1451   68
                                                                  2328 1451   69
References :                                                      2328 1451   70
 1. H.Vonach, H.Muenzer  Oesterr. Akad. Wiss., Math + Naturw.     2328 1451   71
    Anzeiger, v.95, p.199, November 1958                          2328 1451   72
 2. H.K.Vonach et al.  Proc. 2nd Conf. on Nuclear Cross-Sections  2328 1451   73
    and Technology, Washington D.C., 4-7 March 1968, v.2, p.885   2328 1451   74
 3. V.N.Levkovskiy et al. Yadernaja Fizika (Sov.), v.10, n.1,     2328 1451   75
    p.44, July 1968                                               2328 1451   76
 4. J.C.Robertson,B.Audric,P.Kolkowski  J. of Nucl. Energy, v.27, 2328 1451   77
    p.531, August 1973                                            2328 1451   78
 5. A.Paulsen et al.  Atomkernenergie, v.22, p.291, Sep. 1974     2328 1451   79
 6. W.Mannhart, H.Vonach  Zeitschrift fuer Physik, Section A,     2328 1451   80
    v.272, p.279, March 1975                                      2328 1451   81
 7. S.M.Qaim, N.I.Molla  Proc. of 9th Symposium on Fusion Techno- 2328 1451   82
    logy, Garmisch, 14-18 June 1976, FRG, Pergamon Press, p.589   2328 1451   83
 8. O.Schwerer et al.  Oesterr. Akad. Wiss., Math + Naturw.       2328 1451   84
    Anzeiger, v.113, p.153, June 1976                             2328 1451   85
 9. E.Zupranska et al.  Progress Report INR-1821/I/PL/A, 1980     2328 1451   86
    E.Zupranska et al.  Acta. Phys. Pol., v.B11, p.853, Nov. 1980 2328 1451   87
10. I.Kanno, J.W.Meadows, D.L.Smith  Annals of Nuclear Energy,    2328 1451   88
    v.11, p.623, December 1984                                    2328 1451   89
11. J.W.Meadows, D.L.Smith et al. Annals of Nuclear Energy, v.14, 2328 1451   90
    p.489, September 1987                                         2328 1451   91
12. Y.Ikeda et al.  Report JAERI-1312, March 1988                 2328 1451   92
13. K.Kobayashi, I.Kimura  Proc. of an Intern. Conf. on Nuclear   2328 1451   93
    Data for Science and Technology, 30 May - 3 June 1988, Mito,  2328 1451   94
    Japan, Saikon Publishing Co., LTD, pp.261-265, 1989  ;        2328 1451   95
14. Lu Hanlin et al.  Report INDC(CPR)-16, August 1989            2328 1451   96
15. I.Kimura, K.Kobayashi  Nucl. Sci. Eng., v.106, p.332, 1990    2328 1451   97
16. N.I.Molla et al. Proc. of International Conference on Nuclear 2328 1451   98
    Data for Science and Technology, Gatlinburg, Tennessee, USA,  2328 1451   99
    9-13 May 1994, v.2, pp.938-940                                2328 1451  100
17. A.A.Filatenkov et al.  VANT, Ser.: Yadernye Konstanty, v.2,   2328 1451  101
    p.8, Moscow, 1996                                             2328 1451  102
18. D.Subasi et al.  Nucl. Sci. Eng., to be published in 1997     2328 1451  103
19. A.D.Majdeddin  "Measurement and analysis of excitation func-  2328 1451  104
    tions for fast  neutron induced reactions from threshold to   2328 1451  105
    20 MeV".  PHD dissertation, Inst. of Experimental Physics ,   2328 1451  106
    Kossuth University, Hungary, June 1998                        2328 1451  107
20. A.A.Filatenkov et al.  Report RI-252, St.Petersburg, May 1999 2328 1451  108
21. P.Reimer et al. Progress Report On Nuclear Data Research in   2328 1451  109
    the FRG, INDC(Ger)-047, July 2001                             2328 1451  110
22. I.Kumabe  J. Phys. Soc. Jap., v.13, p.325, 1958               2328 1451  111
23. E.B.Paul, R.L.Clarke  Canadian J. of Phys., v.31, p.267, 1953 2328 1451  112
24. A.Poularikas, R.W.Fink   Progress Report A-ARK-60, p.3, 1960  2328 1451  113
25. F.Gabbard et al.  Bull. Amer. Phys. Soc., v.5, p.42(C8), 1960 2328 1451  114
26. M.Bormann et al.  Phys. Rev., v.22, p.602, October 1961       2328 1451  115
27. M.Hillman  Nucl. Phys., v.37, p.78, 1962                      2328 1451  116
28. E.T.Bramlitt, R.W.Fink  Phys. Rev., v.131, p.2649, Sep. 1963  2328 1451  117
29. J.E.Strain, W.J.Ross  Report ORNL-3672, January 1965          2328 1451  118
30. D.Crumpton  J. Inorg. Nucl. Chem., v.31, p.3727, Dec. 1969    2328 1451  119
31. R.Spangler et al.  Transactions of the American Nuclear       2328 1451  120
    Society, v.22, p.818, November 1975                           2328 1451  121
32. U.Garuska et al. Progress Report INDC(POL)-9, p.16, Sep. 1978 2328 1451  122
33. W.H.Warren, W.L.Alford Annals of Nucl. Energy, v.9,p.369,1982 2328 1451  123
34. G.Helfer et al.  Czechoslovak Journal of Physics, Part B,     2328 1451  124
    v.34, p.30, 1984                                              2328 1451  125
35. R.Pepelnik et al.  Int. Conf. on Nuclear Data for Basic and   2328 1451  126
    Applied Science, Santa Fe, N.M., 13-17 May 1985, v.1, p.211   2328 1451  127
36. N.I.Molla et al.  Progress Report INDC(BAN)-003 , Sep. 1986   2328 1451  128
37. Y.Ikeda et al. Progress Report INDC(JPN)-162/U,p.24,Aug. 1992 2328 1451  129
38. J.Cezar Suita et al.  Nucl. Sci. Eng., v.126, p.101, 1997     2328 1451  130
39. F.Nasyrov,B.D.Sciborskij  Atomnaya Energija (Sov.), v.25, n.5,2328 1451  131
    p.437, November 1968                                          2328 1451  132
40. I.Kimura, K.Kobayashi, T.Shibata  Nucl. Sci. Technology., v.8,2328 1451  133
    p.59, February 1971                                           2328 1451  134
41. K.Kobayashi, I.Kimura et al.  Nucl. Sci. Technology., v.13,   2328 1451  135
    p.531, October 1976                                           2328 1451  136
42. W.Mannhart   Progress Report INDC(Ger)-045, pp.40-43, 1999    2328 1451  137
43. W.Mannhart   Proc. of 5-th ASTM-EURATOM Symposium on Reactor  2328 1451  138
    Dosimetry. Geesthacht, Sep.24-28, 1984, Vol.2, p.813, 1985    2328 1451  139
44. J.Csikai, Z.Dezso   Proc. of 4th All Union Conf. on Neutron   2328 1451  140
    Physics, Kiev, 18-22 April 1977, v.3, p.32                    2328 1451  141
45. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear    2328 1451  142
    Model Code for Calculation of Cross Section and Emission      2328 1451  143
    Spectra. Report LA-6947, Los Alamos, 1977  ;                  2328 1451  144
    E.L.Trykiv, G.Ya.Tertychnyi  Private communication, IPPE,     2328 1451  145
    Obninsk, May 1999                                             2328 1451  146
46. S.A.Badikov et.al.  Preprint FEI-1686, Obninsk, 1985          2328 1451  147
47. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2328 1451  148
    st's Meeting on Evaluation and Processing of Covariance Data, 2328 1451  149
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  2328 1451  150
48. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2328 1451  151
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              2328 1451  152
49. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        2328 1451  153
***************************************************************** 2328 1451  154
 The Q values and threshold energies were updated prior to pro-   2328 1451  155
 cessing through the codes to comply with the values obtained     2328 1451  156
 using the NNDC calculation program which is based on the 1995    2328 1451  157
 Update to the Atomic mass Evaluation.                            2328 1451  158
                                                                  2328 1451  159
 File 2 added to the pointwise file containing only the effective 2328 1451  160
 scattering radius with no resonance parameters given.            2328 1451  161
 Taken from ENDF/B-VI                                             2328 1451  162
***************************************************************** 2328 1451  163
                                                                  2328 1451  164
 ***************** Program LINEAR (VERSION 2002-1) ***************2328 1451  165
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2328 1451  166
 Data Linearized to Within an Accuracy of .100000000 per-cent     2328 1451  167
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2328 1451  168
 Data Doppler Broadened to 300.000000 Kelvin                      2328 1451  169
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2328 1451  170
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2328 1451  171
 ***************** Program FIXUP (Version 2002-1) ****************2328 1451  172
 Corrected ZA/AWR in All Sections-----------------------------Yes 2328 1451  173
 Corrected Thresholds-----------------------------------------Yes 2328 1451  174
 Extended Cross Sections to 20 MeV----------------------------No  2328 1451  175
 Allow Cross Section Deletion---------------------------------No  2328 1451  176
 Allow Cross Section Reconstruction---------------------------No  2328 1451  177
 Make All Cross Sections Non-Negative-------------------------Yes 2328 1451  178
 Delete Energies Not in Ascending Order-----------------------Yes 2328 1451  179
 Deleted Duplicate Points-------------------------------------Yes 2328 1451  180
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2328 1451  181
 Check for Legal MF/MT Numbers--------------------------------Yes 2328 1451  182
 Allow Creation of Missing Sections---------------------------No  2328 1451  183
 Allow Insertion of Energy Points-----------------------------No  2328 1451  184
 Create Uniform Energy Grid-----------------------------------No  2328 1451  185
 Delete Section if Cross Section =0 at All Energies-----------Yes 2328 1451  186
 ***************** Program GROUPIE (VERSION 2002-1) **************2328 1451  187
 Unshielded Group Averages Using  640 Groups                      2328 1451  188
 Weighting Spectrum: Flat (Constant) Spectrum                     2328 1451  189
                                1        451        193          12328 1451  190
                                2        151          4          12328 1451  191
                                3        107         64          12328 1451  192
                               33        107         71          12328 1451  193
                                                                  2328 1  099999
                                                                  2328 0  0    0
 2.30510E+4 5.05063E+1          0          0          1          02328 2151    1
 2.30510+ 4 1.00000+ 0          0          0          1          02328 2151    2
 1.00000- 5 9.80000+ 5          0          0          0          02328 2151    3
 0.00000+ 0 5.44480- 1          0          0          0          02328 2151    4
                                                                  2328 2  099999
                                                                  2328 0  0    0
 2.30510E+4 5.05063E+1          0          0          0          02328 3107    1
-2.05800E+6-2.05800E+6          0          0          1        1812328 3107    2
        181          1                                            2328 3107    3
 2000000.00 1.8941E-13 2100000.00 1.23745E-9 2200000.00 3.65187E-92328 3107    4
 2300000.00 6.06629E-9 2400000.00 8.48070E-9 2500000.00 1.08951E-82328 3107    5
 2600000.00 1.33095E-8 2700000.00 1.57240E-8 2800000.00 1.81384E-82328 3107    6
 2900000.00 2.05528E-8 3000000.00 2.17904E-8 3100000.00 2.18512E-82328 3107    7
 3200000.00 2.27955E-8 3300000.00 2.90406E-8 3400000.00 3.61691E-82328 3107    8
 3500000.00 4.62735E-8 3600000.00 5.93538E-8 3700000.00 7.29986E-82328 3107    9
 3800000.00 9.00308E-8 3900000.00 1.07628E-7 4000000.00 1.27030E-72328 3107   10
 4100000.00 1.48239E-7 4200000.00 1.70077E-7 4300000.00 1.95692E-72328 3107   11
 4400000.00 2.21935E-7 4500000.00 2.54196E-7 4600000.00 2.92475E-72328 3107   12
 4700000.00 3.34447E-7 4800000.00 3.98587E-7 4900000.00 4.66421E-72328 3107   13
 5000000.00 5.51411E-7 5100000.00 6.72556E-7 5200000.00 8.29793E-72328 3107   14
 5300000.00 1.03209E-6 5400000.00 1.29020E-6 5500000.00 1.61995E-62328 3107   15
 5600000.00 2.05269E-6 5700000.00 2.65886E-6 5800000.00 3.58291E-62328 3107   16
 5900000.00 5.05849E-6 6000000.00 7.35895E-6 6100000.00 1.07116E-52328 3107   17
 6200000.00 1.52802E-5 6300000.00 2.12329E-5 6400000.00 2.88160E-52328 3107   18
 6500000.00 3.83819E-5 6600000.00 5.03943E-5 6700000.00 6.54289E-52328 3107   19
 6800000.00 8.41770E-5 6900000.00 .000107451 7000000.00 .0001361842328 3107   20
 7100000.00 .000171432 7200000.00 .000214354 7300000.00 .0002661842328 3107   21
 7400000.00 .000328186 7500000.00 .000401585 7600000.00 .0004874772328 3107   22
 7700000.00 .000586733 7800000.00 .000699892 7900000.00 .0008270702328 3107   23
 8000000.00 .000967893 8100000.00 .001121482 8200000.00 .0012870882328 3107   24
 8300000.00 .001461652 8400000.00 .001644565 8500000.00 .0018322112328 3107   25
 8600000.00 .002024416 8700000.00 .002217381 8800000.00 .0024103462328 3107   26
 8900000.00 .002603311 9000000.00 .002796276 9100000.00 .0029885792328 3107   27
 9200000.00 .003176905 9300000.00 .003364567 9400000.00 .0035522292328 3107   28
 9500000.00 .003739891 9600000.00 .003927553 9700000.00 .0041152152328 3107   29
 9800000.00 .004302877 9900000.00 .004490539 10000000.0 .0046821802328 3107   30
 10100000.0 .004877800 10200000.0 .005073420 10300000.0 .0052744232328 3107   31
 10400000.0 .005480810 10500000.0 .005687197 10600000.0 .0059001172328 3107   32
 10700000.0 .006119570 10800000.0 .006339023 10900000.0 .0065655302328 3107   33
 11000000.0 .006799090 11100000.0 .007032650 11200000.0 .0072732432328 3107   34
 11300000.0 .007520870 11400000.0 .007768497 11500000.0 .0080236842328 3107   35
 11600000.0 .008286431 11700000.0 .008549179 11800000.0 .0088119262328 3107   36
 11900000.0 .009082530 12000000.0 .009360990 12100000.0 .0096394502328 3107   37
 12200000.0 .009917910 12300000.0 .010196370 12400000.0 .0104803252328 3107   38
 12500000.0 .010769775 12600000.0 .011059225 12700000.0 .0113486752328 3107   39
 12800000.0 .011638125 12900000.0 .011927575 13000000.0 .0122170252328 3107   40
 13100000.0 .012506475 13200000.0 .012795925 13300000.0 .0130853752328 3107   41
 13400000.0 .013374825 13500000.0 .013664275 13600000.0 .0139537252328 3107   42
 13700000.0 .014243175 13800000.0 .014524710 13900000.0 .0147983302328 3107   43
 14000000.0 .015071950 14100000.0 .015345570 14200000.0 .0156191902328 3107   44
 14300000.0 .015882675 14400000.0 .016136025 14500000.0 .0163893752328 3107   45
 14600000.0 .016642725 14700000.0 .016883825 14800000.0 .0171126752328 3107   46
 14900000.0 .017341525 15000000.0 .017570375 15100000.0 .0177839752328 3107   47
 15200000.0 .017982325 15300000.0 .018180675 15400000.0 .0183790252328 3107   48
 15500000.0 .018561667 15600000.0 .018728600 15700000.0 .0188955332328 3107   49
 15800000.0 .019047283 15900000.0 .019183850 16000000.0 .0193204172328 3107   50
 16100000.0 .019440483 16200000.0 .019544050 16300000.0 .0196476172328 3107   51
 16400000.0 .019733583 16500000.0 .019801950 16600000.0 .0198703172328 3107   52
 16700000.0 .019920333 16800000.0 .019952000 16900000.0 .0199836672328 3107   53
 17000000.0 .020002900 17100000.0 .019997250 17200000.0 .0199791502328 3107   54
 17300000.0 .019961050 17400000.0 .019924583 17500000.0 .0198697502328 3107   55
 17600000.0 .019814917 17700000.0 .019742550 17800000.0 .0196526502328 3107   56
 17900000.0 .019562750 18000000.0 .019456550 18100000.0 .0193340502328 3107   57
 18200000.0 .019211550 18300000.0 .019072275 18400000.0 .0189162252328 3107   58
 18500000.0 .018760175 18600000.0 .018604125 18700000.0 .0184321882328 3107   59
 18800000.0 .018244363 18900000.0 .018056538 19000000.0 .0178687132328 3107   60
 19100000.0 .017667850 19200000.0 .017453950 19300000.0 .0172400502328 3107   61
 19400000.0 .017026150 19500000.0 .016812250 19600000.0 .0165901382328 3107   62
 19700000.0 .016359813 19800000.0 .016129488 19900000.0 .0158991632328 3107   63
 20000000.0 0.0                                                   2328 3107   64
                                                                  2328 3  099999
                                                                  2328 0  0    0
 2.30510E+4 5.05063E+1          0          0          0          1232833107    1
 0.000000+0 0.000000+0          0        107          0          1232833107    2
 0.000000+0 0.000000+0          1          5        406         28232833107    3
 1.000000-5 2.000000+6 8.000000+6 8.400000+6 8.700000+6 9.000000+6232833107    4
 9.500000+6 1.000000+7 1.050000+7 1.100000+7 1.150000+7 1.200000+7232833107    5
 1.250000+7 1.300000+7 1.350000+7 1.400000+7 1.450000+7 1.500000+7232833107    6
 1.550000+7 1.600000+7 1.650000+7 1.700000+7 1.750000+7 1.800000+7232833107    7
 1.850000+7 1.900000+7 1.950000+7 2.000000+7 0.000000+0 0.000000+0232833107    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0232833107    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0232833107   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0232833107   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0232833107   12
 0.000000+0 6.409350-3 3.702780-3 2.209040-3 1.369340-3 8.918800-4232833107   13
 8.003970-4 8.169160-4 7.473430-4 5.866800-4 3.888360-4 2.073490-4232833107   14
 7.510980-5 1.598180-6-2.190230-5-1.394860-5 5.409240-6 2.066510-5232833107   15
 2.397450-5 1.522380-5-1.221820-8-1.386740-5-1.964710-5-1.453750-5232833107   16
-7.426460-7 1.490920-5 2.259660-5 3.533640-3 2.721880-3 1.873850-3232833107   17
 9.033920-4 2.002510-4-4.511890-5-4.519550-5 3.326440-5 9.822120-5232833107   18
 1.156290-4 8.888230-5 4.058370-5-2.615250-6-2.090600-5-7.174720-6232833107   19
 3.241110-5 8.182950-5 1.212640-4 1.338890-4 1.117260-4 5.896180-5232833107   20
-8.043630-6-6.393620-5-7.953580-5-2.720720-5 2.644550-3 2.251630-3232833107   21
 1.492470-3 6.422470-4 9.351260-5-1.598030-4-2.144940-4-1.676780-4232833107   22
-9.073660-5-2.572730-5 1.052820-5 1.916870-5 1.098420-5-1.171280-6232833107   23
-7.662610-6-4.699890-6 5.742270-6 1.784780-5 2.499430-5 2.270910-5232833107   24
 1.078710-5-6.112150-6-1.926930-5-1.772970-5 2.304190-3 1.965740-3232833107   25
 1.277390-3 6.122250-4 1.405760-4-1.157460-4-1.994410-4-1.732450-4232833107   26
-9.826500-5-2.250730-5 2.462440-5 3.284700-5 7.600960-6-3.572180-5232833107   27
-7.831570-5-1.038630-4-1.029510-4-7.528640-5-2.953690-5 1.902460-5232833107   28
 5.216820-5 5.264690-5 7.166370-6 2.238470-3 2.038110-3 1.502260-3232833107   29
 9.134390-4 4.326360-4 1.190360-4-3.307590-5-6.563490-5-3.419560-5232833107   30
 9.842040-6 3.107050-5 1.522200-5-3.221090-5-9.198690-5-1.397690-4232833107   31
-1.550570-4-1.284310-4-6.535050-5 1.421750-5 7.994730-5 9.754510-5232833107   32
 3.514570-5 2.460990-3 2.328050-3 1.869570-3 1.307140-3 7.891170-4232833107   33
 3.931920-4 1.413020-4 1.669140-5-1.855550-5-7.470460-6 1.409750-5232833107   34
 2.418390-5 1.614900-5-4.410620-6-2.528220-5-3.424260-5-2.458510-5232833107   35
 1.594710-6 3.318330-5 5.235960-5 3.840850-5 2.626390-3 2.461640-3232833107   36
 2.007150-3 1.432960-3 8.739120-4 4.203870-4 1.171690-4-3.187220-5232833107   37
-5.377050-5 6.628290-6 9.978150-5 1.825280-4 2.255580-4 2.171680-4232833107   38
 1.629420-4 8.216970-5 1.748080-6-5.049080-5-5.165130-5 1.281430-5232833107   39
 2.588360-3 2.326970-3 1.818850-3 1.216390-3 6.537300-4 2.270770-4232833107   40
-1.614330-5-7.743920-5 2.088440-6 1.574000-4 3.175160-4 4.222880-4232833107   41
 4.355210-4 3.520330-4 1.976880-4 2.239200-5-1.115150-4-1.424160-4232833107   42
-1.996670-5 2.254280-3 1.879440-3 1.339290-3 7.778230-4 3.154790-4232833107   43
 2.737830-5-6.557210-5 7.354640-6 1.811410-4 3.751200-4 5.142460-4232833107   44
 5.475840-4 4.604080-4 2.775360-4 5.721090-5-1.221850-4-1.787450-4232833107   45
-4.157720-5 1.655150-3 1.246880-3 7.787640-4 3.656390-4 8.818820-5232833107   46
-2.033960-5 2.532950-5 1.731710-4 3.514140-4 4.887460-4 5.329630-4232833107   47
 4.643000-4 3.005900-4 9.316360-5-8.481210-5-1.539790-4-4.322840-5232833107   48
 9.979500-4 6.779530-4 3.736110-4 1.516640-4 4.613630-5 5.514980-5232833107   49
 1.468580-4 2.713890-4 3.757350-4 4.181980-4 3.794610-4 2.677670-4232833107   50
 1.171590-4-2.033930-5-8.602870-5-2.551960-5 5.174630-4 3.454470-4232833107   51
 2.033880-4 1.170720-4 9.297450-5 1.198800-4 1.743340-4 2.283430-4232833107   52
 2.573910-4 2.471310-4 1.971890-4 1.213170-4 4.406540-5-4.780210-6232833107   53
 3.934470-6 2.935610-4 2.326390-4 1.760670-4 1.331670-4 1.080550-4232833107   54
 9.974160-5 1.033330-4 1.118310-4 1.181840-4 1.170650-4 1.060490-4232833107   55
 8.591960-5 6.017890-5 3.400260-5 2.346650-4 2.112160-4 1.696470-4232833107   56
 1.206830-4 7.576690-5 4.437710-5 3.183570-5 3.806620-5 5.754900-5232833107   57
 8.052540-5 9.505690-5 8.939060-5 5.388830-5 2.174930-4 1.971300-4232833107   58
 1.582960-4 1.124850-4 7.147940-5 4.440740-5 3.552820-5 4.323420-5232833107   59
 6.047870-5 7.643890-5 7.888610-5 5.647360-5 2.120480-4 2.129620-4232833107   60
 2.006700-4 1.778160-4 1.483680-4 1.168520-4 8.758620-5 6.397400-5232833107   61
 4.807710-5 4.049150-5 4.054580-5 2.707820-4 3.156970-4 3.338090-4232833107   62
 3.171470-4 2.661770-4 1.903260-4 1.063600-4 3.512920-5-2.393020-6232833107   63
 1.149190-5 4.248520-4 4.961890-4 5.070980-4 4.505250-4 3.375260-4232833107   64
 1.953650-4 6.192050-5-2.193140-5-1.942250-5 6.197670-4 6.691760-4232833107   65
 6.282040-4 5.043390-4 3.275690-4 1.439350-4 5.926440-6-3.705100-5232833107   66
 7.612450-4 7.584940-4 6.595730-4 4.869100-4 2.815200-4 9.398340-5232833107   67
-2.521280-5 8.108710-4 7.715490-4 6.460520-4 4.571060-4 2.389510-4232833107   68
 3.009620-5 8.139380-4 7.703780-4 6.367250-4 4.204600-4 1.378650-4232833107   69
 8.239680-4 7.757420-4 6.043510-4 3.003020-4 8.270000-4 7.491350-4232833107   70
 5.126110-4 8.137850-4 7.643050-4 1.041490-3                      232833107   71
                                                                  232833  099999
                                                                  2328 0  0    0
                                                                     0 0  0    0
 2.40520E+4 5.14943E+1          0          0         34         102431 1451    1
 0.0        0.0                 0          0          0          62431 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022431 1451    3
 3.00000E+2 0.0                 1          0         38          42431 1451    4
 24-Cr- 52 IRK-VIENNA EVAL-APR90                                  2431 1451    5
                      DIST-Feb2004                                2431 1451    6
----IRDF-2002         MATERIAL 2431                               2431 1451    7
-----INCIDENT NEUTRON DATA                                        2431 1451    8
------ENDF-6 FORMAT                                               2431 1451    9
 *****************************************************************2431 1451   10
                      DIST-JUN90                       910201     2431 1451   11
    IRK-EVAL.NLIB 25  2431                                        2431 1451   12
 *****************************************************************2431 1451   13
  The Q values and threshold energies were updated prior to pro-  2431 1451   14
  cessing through the codes to comply with the values obtained    2431 1451   15
  using the NNDC calculation program which is based on the 1995   2431 1451   16
  Update to the Atomic mass Evaluation.                           2431 1451   17
 ***************** Program LINEAR (VERSION 2002-1) ***************2431 1451   18
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2431 1451   19
 Data Linearized to Within an Accuracy of .100000000 per-cent     2431 1451   20
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2431 1451   21
 Data Doppler Broadened to 300.000000 Kelvin                      2431 1451   22
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2431 1451   23
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2431 1451   24
 ***************** Program FIXUP (Version 2002-1) ****************2431 1451   25
 Corrected ZA/AWR in All Sections-----------------------------Yes 2431 1451   26
 Corrected Thresholds-----------------------------------------Yes 2431 1451   27
 Extended Cross Sections to 20 MeV----------------------------No  2431 1451   28
 Allow Cross Section Deletion---------------------------------No  2431 1451   29
 Allow Cross Section Reconstruction---------------------------No  2431 1451   30
 Make All Cross Sections Non-Negative-------------------------Yes 2431 1451   31
 Delete Energies Not in Ascending Order-----------------------Yes 2431 1451   32
 Deleted Duplicate Points-------------------------------------Yes 2431 1451   33
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2431 1451   34
 Check for Legal MF/MT Numbers--------------------------------Yes 2431 1451   35
 Allow Creation of Missing Sections---------------------------No  2431 1451   36
 Allow Insertion of Energy Points-----------------------------No  2431 1451   37
 Create Uniform Energy Grid-----------------------------------No  2431 1451   38
 Delete Section if Cross Section =0 at All Energies-----------Yes 2431 1451   39
 ***************** Program GROUPIE (VERSION 2002-1) **************2431 1451   40
 Unshielded Group Averages Using  640 Groups                      2431 1451   41
 Weighting Spectrum: Flat (Constant) Spectrum                     2431 1451   42
                                1        451         46          12431 1451   43
                                2        151          4          12431 1451   44
                                3         16         30          12431 1451   45
                               33         16         26          12431 1451   46
                                                                  2431 1  099999
                                                                  2431 0  0    0
 2.40520E+4 5.14943E+1          0          0          1          02431 2151    1
 2.40520E+4 1.00000E+0          0          0          1          02431 2151    2
 1.00000E+0 2.00000E+7          0          0          0          02431 2151    3
 0.0        5.44480E-1          0          0          0          02431 2151    4
                                                                  2431 2  099999
                                                                  2431 0  0    0
 2.40520E+4 5.14943E+1          0          0          0          02431 3 16    1
-1.20394E+7-1.20394E+7          0          0          1         792431 3 16    2
         79          1                                            2431 3 16    3
 12200000.0 .000136222 12300000.0 .002913303 12400000.0 .0090350002431 3 16    4
 12500000.0 .018505000 12600000.0 .029945000 12700000.0 .0421942862431 3 16    5
 12800000.0 .054457131 12900000.0 .070114000 13000000.0 .0871593332431 3 16    6
 13100000.0 .104204667 13200000.0 .121073583 13300000.0 .1368840002431 3 16    7
 13400000.0 .152518000 13500000.0 .168152000 13600000.0 .1837860002431 3 16    8
 13700000.0 .200229500 13800000.0 .221530000 13900000.0 .2436400002431 3 16    9
 14000000.0 .265750000 14100000.0 .287860000 14200000.0 .3092252502431 3 16   10
 14300000.0 .326122000 14400000.0 .342274000 14500000.0 .3584260002431 3 16   11
 14600000.0 .374578000 14700000.0 .390333833 14800000.0 .4037126672431 3 16   12
 14900000.0 .416695333 15000000.0 .429678000 15100000.0 .4426606672431 3 16   13
 15200000.0 .455643333 15300000.0 .468626000 15400000.0 .4816086672431 3 16   14
 15500000.0 .491881500 15600000.0 .499444500 15700000.0 .5070075002431 3 16   15
 15800000.0 .514570500 15900000.0 .522133500 16000000.0 .5296965002431 3 16   16
 16100000.0 .537259500 16200000.0 .544822500 16300000.0 .5523855002431 3 16   17
 16400000.0 .559948500 16500000.0 .566084500 16600000.0 .5707935002431 3 16   18
 16700000.0 .575502500 16800000.0 .580211500 16900000.0 .5849205002431 3 16   19
 17000000.0 .589629500 17100000.0 .594338500 17200000.0 .5990475002431 3 16   20
 17300000.0 .603756500 17400000.0 .608465500 17500000.0 .6119980002431 3 16   21
 17600000.0 .614354000 17700000.0 .616710000 17800000.0 .6190660002431 3 16   22
 17900000.0 .621422000 18000000.0 .623778000 18100000.0 .6261340002431 3 16   23
 18200000.0 .628490000 18300000.0 .630846000 18400000.0 .6332020002431 3 16   24
 18500000.0 .635069000 18600000.0 .636447000 18700000.0 .6378250002431 3 16   25
 18800000.0 .639203000 18900000.0 .640581000 19000000.0 .6419590002431 3 16   26
 19100000.0 .643337000 19200000.0 .644715000 19300000.0 .6460930002431 3 16   27
 19400000.0 .647471000 19500000.0 .648849000 19600000.0 .6502270002431 3 16   28
 19700000.0 .651605000 19800000.0 .652983000 19900000.0 .6543610002431 3 16   29
 20000000.0 0.0                                                   2431 3 16   30
                                                                  2431 3  099999
                                                                  2431 0  0    0
 2.40520E+4 5.14943E+1          0          0          0          1243133 16    1
 0.000000+0 0.000000+0          0         16          0          1243133 16    2
 0.000000+0 0.000000+0          1          5        136         16243133 16    3
 1.000000-5 1.220000+7 1.245000+7 1.255000+7 1.265000+7 1.275000+7243133 16    4
 1.300000+7 1.350000+7 1.400000+7 1.450000+7 1.500000+7 1.600000+7243133 16    5
 1.700000+7 1.800000+7 1.900000+7 2.000000+7 0.000000+0 0.000000+0243133 16    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0243133 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0243133 16    8
 0.000000+0 4.031000-2 3.015000-2 2.011000-2 4.441000-3 1.005000-2243133 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0243133 16   10
 0.000000+0 0.000000+0 0.000000+0 2.256000-2 1.504000-2 3.322000-3243133 16   11
 7.519000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0243133 16   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.003000-2 2.216000-3243133 16   13
 5.015000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0243133 16   14
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.088000-3 1.107000-3243133 16   15
 7.104000-4 1.385000-4 3.054000-4 1.269000-4 1.050000-3 6.131000-4243133 16   16
 5.750000-4 5.345000-4 5.072000-4 2.506000-3 0.000000+0 0.000000+0243133 16   17
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0243133 16   18
 0.000000+0 1.823000-3 2.416000-4 5.329000-4 2.213000-4 1.832000-3243133 16   19
 1.070000-3 1.003000-3 9.325000-4 8.849000-4 4.904000-4 3.163000-4243133 16   20
 3.318000-4 3.571000-4 2.085000-4 1.956000-4 1.818000-4 1.725000-4243133 16   21
 7.342000-4 2.818000-4 7.875000-4 4.599000-4 4.313000-4 4.009000-4243133 16   22
 3.805000-4 4.986000-4 3.270000-4 1.910000-4 1.791000-4 1.665000-4243133 16   23
 1.580000-4 3.980000-3 1.581000-3 1.482000-3 1.378000-3 1.308000-3243133 16   24
 1.358000-3 8.658000-4 8.048000-4 7.637000-4 1.194000-3 7.548000-4243133 16   25
 7.163000-4 1.032000-3 6.658000-4 9.292000-4                      243133 16   26
                                                                  243133  099999
                                                                  2431 0  0    0
                                                                     0 0  0    0
 2.50550E+4 5.44661E+1          0          0         34         102525 1451    1
 0.0        0.0                 0          0          0          62525 1451    2
 1.00000E+0 2.00000E+7          0          5         10       20022525 1451    3
 3.00000E+2 0.0                 1          0        157          42525 1451    4
 25-Mn- 55 JAERI,ORNL EVAL-MAR88 K.SHIBATA                        2525 1451    5
                      DIST-Feb2004                                2525 1451    6
----IRDF-2002         MATERIAL 2525                               2525 1451    7
-----INCIDENT NEUTRON DATA                                        2525 1451    8
------ENDF-6 FORMAT                                               2525 1451    9
******************************************************************2525 1451   10
 25-MN- 55 JAERI,ORNL EVAL-MAR88 K.SHIBATA                        2525 1451   11
                      DIST-SEP 1 REV2-SEP98            20010926   2525 1451   12
----ENDF/B-VI         MATERIAL 2525         REVISION 2            2525 1451   13
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2525 1451   14
DOSIMETRY                                                         2525 1451   15
******************************************************************2525 1451   16
                                                                  2525 1451   17
 **************************************************************** 2525 1451   18
                                                                  2525 1451   19
 ENDF/B-VI MOD 3 Revision, June 2000, S.C. Frankle, R.C. Reedy,   2525 1451   20
                 P.G. Young (LANL)                                2525 1451   21
                                                                  2525 1451   22
 The secondary gamma-ray spectrum for radiative capture (MF 12,   2525 1451   23
 MT 102) has been updated for new experimental data at incident   2525 1451   24
 neutron energies up to 100 keV.                                  2525 1451   25
 The previous (MOD 2) pure continuum at thermal neutron energy    2525 1451   26
 is replaced by 321 discrete photons.                             2525 1451   27
 The Q-value for radiative capture was also updated in File 3.    2525 1451   28
 Details of these changes are described in Frankel et al. [Fr01]. 2525 1451   29
                                                                  2525 1451   30
REFERENCES                                                        2525 1451   31
                                                                  2525 1451   32
[Fr01]  S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos      2525 1451   33
   National Laboratory Report, LA-13812 (2001).                   2525 1451   34
                                                                  2525 1451   35
 **************************************************************** 2525 1451   36
                                                                  2525 1451   37
 ENDF/B-VI MOD 2 Revision, October 1997, V. McLane (NNDC)         2525 1451   38
                                                                  2525 1451   39
 1. Corrected residual nucleus and AWR in File 6, MT=22,107.      2525 1451   40
 2. Updated file 1 comments and and corrected references.         2525 1451   41
                                                                  2525 1451   42
 **************************************************************** 2525 1451   43
                                                                  2525 1451   44
 ENDF/B-VI MOD 1 Evaluation, March 1988, K. Shibata (ORNL,JAERI)  2525 1451   45
                                                                  2525 1451   46
 File 1  General Information ------------------------------------ 2525 1451   47
   MT=451   Descriptive data and dictionary                       2525 1451   48
                                                                  2525 1451   49
 File 2  Resonance Parameters ----------------------------------- 2525 1451   50
   MT=151   Resolved resonance parameters for MLBW formula.       2525 1451   51
     The parameters of the lowest four resonances were taken      2525 1451   52
     from the work of Macklin [1].  Others were taken from the    2525 1451   53
     compilation of mughabghab et al.[2] except that the          2525 1451   54
     parameters of two negative resonances were adjusted so as    2525 1451   55
     to fit to experimental thermal cross sections.               2525 1451   56
     Resonance region : 1.0E-5 eV to 100 keV.                     2525 1451   57
                                                                  2525 1451   58
     Scattering radius: 5.15 fm                                   2525 1451   59
                                                                  2525 1451   60
     Calculated 2200-m/s cross sections and res. integrals        2525 1451   61
                  2200-M/S         RES. INTEG.                    2525 1451   62
      Elastic      2.167 b            -                           2525 1451   63
      Capture     13.413 b          11.73  b                      2525 1451   64
      Total       15.579 b            -                           2525 1451   65
                                                                  2525 1451   66
 File 3  Neutron Cross Sections --------------------------------- 2525 1451   67
   MT=1 Total                                                     2525 1451   68
      Below 100 keV   : no background                             2525 1451   69
      Above 100 keV   : based on the experimental data [3,4,5].   2525 1451   70
   MT=2 Elastic scattering                                        2525 1451   71
      (total) - (nonelastic cross section).                       2525 1451   72
                                                                  2525 1451   73
   MT=102  Radiative capture cross section                        2525 1451   74
      Below 100 keV: Resonance parameters given (no background).  2525 1451   75
      Above 100 keV: Based on the experimental data [11-15]       2525 1451   76
        (taken from JENDL-2 [20]).                                2525 1451   77
                                                                  2525 1451   78
                                                                  2525 1451   79
 File 33.  Covariance data                                        2525 1451   80
   MT=102                                                         2525 1451   81
      Estimated from experimental data and calculation.           2525 1451   82
                                                                  2525 1451   83
 ---------------------------------------------------------------- 2525 1451   84
 REFERENCES                                                       2525 1451   85
                                                                  2525 1451   86
 [1] R.L. Macklin, Nucl.Sci.Eng. 89, 362 (1985).                  2525 1451   87
 [2] S. F. Mughabghab, M. Divadeenam, and N.E. Holden, Neutron    2525 1451   88
     Cross Sections, Vol. 1, Part A (Academic Press, 1981).       2525 1451   89
 [3] S. Cierjacks, P. Forti, D. Kopsch et al., "High Resolution   2525 1451   90
     Total Cross Sections for Na, Cl, K, V, Mn and Co between 0.5 2525 1451   91
     and 30 MeV", report KFK-1000 (1968).                         2525 1451   92
 [4] W.F.E. Pineo, M. Divadeenam, E.G. Bilpuch et al., Ann.Phys.  2525 1451   93
     84, 165 (1974).                                              2525 1451   94
 [5] J.B. Garg, J. Rainwater, and W.W. Havens Jr., Nucl.Sci.Eng.  2525 1451   95
     65, 76 (1978).                                               2525 1451   96
 [6] C.Y. Fu, "A Consistent Nuclear Model for Compound and Pre-   2525 1451   97
     compound Reactions with Conservation of Angular Momentum,"   2525 1451   98
     Oak Ridge National Laboratory report ORNL/TM-7042 (1980).    2525 1451   99
 [7] C.Y. Fu, private communication (1985).                       2525 1451  100
 [8] Zhou Enchen, Huo Junde, Zhou Chunmei et al., Nucl.Data       2525 1451  101
     Sheets 44, 463 (1985).                                       2525 1451  102
 [9] F.G. Perey, Phys.Rev. 131, 745 (1963).                       2525 1451  103
[10] J.R. Huizenga,  and G.J. Igo, Nucl.Phys. 29, 462 (1962).     2525 1451  104
[11] J.B. Garg, R.L. Macklin, and J. Halperin, Phys.Rev. C18,     2525 1451  105
     2079 (1978).                                                 2525 1451  106
[12] A.G. Dovbenko, V.E. Kolesov, V.P. Koroleva et al., At.En. 26,2525 1451  107
     67 (1969).                                                   2525 1451  108
[13] H.O. Menlove, K.L. Coop, H.A. Grench et al. Phys.Rev. 163,   2525 1451  109
     1299 (1967).                                                 2525 1451  110
[14] O. Schwerer, M. Winkler-Rohatsch, H. Warhanek et al., Nucl.  2525 1451  111
     Phys. A264, 105 (1976).                                      2525 1451  112
[15] M. Budnar, F. Cvelbar, E. Hodgson et al., "Prompt Gamma-ray  2525 1451  113
     Spectra and Integarted Cross Sections for the Radiative      2525 1451  114
     Capture of 14 MeV Neutrons for 28 Natural Targets ...,"      2525 1451  115
     report INDC(YUG)-6 (1979).                                   2525 1451  116
[16] L. Colli, I. Iori, S. Micheletti et al., Nuovo.cim. 21, 966  2525 1451  117
     (1962).                                                      2525 1451  118
[17] S. Sudar and Csikai, Nucl.Phys. A319, 157 (1979).            2525 1451  119
[18] M. Diksic, P. Strohal, and I. Slaus, J.Inorg.Nucl.Chem. 36,  2525 1451  120
     477 (1974).                                                  2525 1451  121
[19] C.H. Wu, R. Woelfle, and S.M. Qaim, Nucl.Phys. A329, 63      2525 1451  122
     (1979).                                                      2525 1451  123
[20] T. Nakagawa, "Summary of JENDL-2 General Purpose File,"      2525 1451  124
     report JAERI-M 84-103 (1984).                                2525 1451  125
                                                                  2525 1451  126
******************************************************************2525 1451  127
                                                                  2525 1451  128
                                                                  2525 1451  129
                                                                  2525 1451  130
                                                                  2525 1451  131
******************************************************************2525 1451  132
 ************************ C O N T E N T S *********************** 2525 1451  133
 ***************** Program LINEAR (VERSION 2002-1) ***************2525 1451  134
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2525 1451  135
 Data Linearized to Within an Accuracy of .100000000 per-cent     2525 1451  136
 ***************** Program RECENT (VERSION 2002-1) ***************2525 1451  137
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2525 1451  138
 Data Linearized to within an Accuracy of .100000000 per-cent     2525 1451  139
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2525 1451  140
 Data Doppler Broadened to 300.000000 Kelvin                      2525 1451  141
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2525 1451  142
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2525 1451  143
 ***************** Program FIXUP (Version 2002-1) ****************2525 1451  144
 Corrected ZA/AWR in All Sections-----------------------------Yes 2525 1451  145
 Corrected Thresholds-----------------------------------------Yes 2525 1451  146
 Extended Cross Sections to 20 MeV----------------------------No  2525 1451  147
 Allow Cross Section Deletion---------------------------------No  2525 1451  148
 Allow Cross Section Reconstruction---------------------------No  2525 1451  149
 Make All Cross Sections Non-Negative-------------------------Yes 2525 1451  150
 Delete Energies Not in Ascending Order-----------------------Yes 2525 1451  151
 Deleted Duplicate Points-------------------------------------Yes 2525 1451  152
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2525 1451  153
 Check for Legal MF/MT Numbers--------------------------------Yes 2525 1451  154
 Allow Creation of Missing Sections---------------------------No  2525 1451  155
 Allow Insertion of Energy Points-----------------------------No  2525 1451  156
 Create Uniform Energy Grid-----------------------------------No  2525 1451  157
 Delete Section if Cross Section =0 at All Energies-----------Yes 2525 1451  158
 ***************** Program GROUPIE (VERSION 2002-1) **************2525 1451  159
 Unshielded Group Averages Using  640 Groups                      2525 1451  160
 Weighting Spectrum: Flat (Constant) Spectrum                     2525 1451  161
                                1        451        165          32525 1451  162
                                2        151          4          12525 1451  163
                                3        102        217          32525 1451  164
                               33        102         17          12525 1451  165
                                                                  2525 1  099999
                                                                  2525 0  0    0
 2.50550E+4 5.44661E+1          0          0          1          02525 2151    1
 2.50550E+4 1.00000E+0          0          0          1          02525 2151    2
 1.00000E-5 1.00000E+5          0          0          0          02525 2151    3
 2.50000E+0 5.15000E-1          0          0          0          02525 2151    4
                                                                  2525 2  099999
                                                                  2525 0  0    0
 2.50550E+4 5.44661E+1          0          0          0          02525 3102    1
 7.27050E+6 7.27050E+6          0          0          1        6412525 3102    2
        641          1                                            2525 3102    3
 .000100000 210.836355 .000105000 205.919990 .000110000 201.2493862525 3102    4
 .000115000 196.945550 .000120000 191.914305 .000127500 186.3322702525 3102    5
 .000135000 181.232244 .000142500 176.545422 .000150000 171.4729812525 3102    6
 .000160000 166.188822 .000170000 161.380891 .000180000 156.9675742525 3102    7
 .000190000 152.861356 .000200000 149.112342 .000210000 145.5851502525 3102    8
 .000220000 142.308952 .000230000 139.265033 .000240000 135.6921232525 3102    9
 .000255000 131.765845 .000270000 128.736134 .000280000 125.3635062525 3102   10
 .000300000 121.250491 .000320000 117.526305 .000340000 114.1155532525 3102   11
 .000360000 110.974047 .000380000 108.106258 .000400000 105.1164352525 3102   12
 .000425000 102.056964 .000450000 99.2616168 .000475000 96.69878032525 3102   13
 .000500000 94.2886053 .000525000 92.0858615 .000550000 90.00503242525 3102   14
 .000575000 88.0698021 .000600000 86.0862994 .000630000 84.04577582525 3102   15
 .000660000 82.1786685 .000690000 80.3875951 .000720000 78.48183612525 3102   16
 .000760000 76.4384216 .000800000 74.5411534 .000840000 72.80240492525 3102   17
 .000880000 71.1498209 .000920000 69.6348527 .000960000 68.18401602525 3102   18
 .001000000 66.6802433 .001050000 65.1103649 .001100000 63.63859712525 3102   19
 .001150000 62.2824700 .001200000 60.6827442 .001275000 58.92456722525 3102   20
 .001350000 57.3171279 .001425000 55.8169724 .001500000 54.22319982525 3102   21
 .001600000 52.5567297 .001700000 51.0354372 .001800000 49.62844332525 3102   22
 .001900000 48.3430548 .002000000 47.1512904 .002100000 46.03299822525 3102   23
 .002200000 45.0088670 .002300000 44.0295564 .002400000 42.91218462525 3102   24
 .002550000 41.6705962 .002700000 40.6994470 .002800000 39.64420442525 3102   25
 .003000000 38.3451997 .003200000 37.1630951 .003400000 36.08207962525 3102   26
 .003600000 35.0960903 .003800000 34.1857100 .004000000 33.23684052525 3102   27
 .004250000 32.2734093 .004500000 31.3941221 .004750000 30.57240332525 3102   28
 .005000000 29.8184172 .005250000 29.1195793 .005500000 28.45904112525 3102   29
 .005750000 27.8537655 .006000000 27.2181353 .006300000 26.58283802525 3102   30
 .006600000 25.9816432 .006900000 25.4240492 .007200000 24.81770612525 3102   31
 .007600000 24.1692362 .008000000 23.5761125 .008400000 23.01947612525 3102   32
 .008800000 22.5015420 .009200000 22.0202748 .009600000 21.56235132525 3102   33
 .010000000 21.0882598 .010500000 20.5870570 .011000000 20.12861052525 3102   34
 .011500000 19.6912520 .012000000 19.1899854 .012750000 18.63505402525 3102   35
 .013500000 18.1210420 .014250000 17.6495482 .015000000 17.14682352525 3102   36
 .016000001 16.6192227 .017000001 16.1355174 .017999999 15.69395772525 3102   37
 .018999999 15.2880961 .020000000 14.9073261 .021000000 14.55883792525 3102   38
 .022000000 14.2305260 .023000000 13.9246739 .024000000 13.56547322525 3102   39
 .025500000 13.1784088 .027000001 12.8717830 .028000001 12.53936132525 3102   40
 .029999999 12.1291901 .032000002 11.7547360 .034000002 11.41274262525 3102   41
 .035999998 11.1005590 .037999999 10.8126558 .039999999 10.51231402525 3102   42
 .042500000 10.2075815 .045000002 9.92927915 .047499999 9.670116892525 3102   43
 .050000001 9.43185152 .052499998 9.21135883 .055000000 9.002585112525 3102   44
 .057500001 8.81134205 .059999999 8.61018310 .063000001 8.408838552525 3102   45
 .066000000 8.21903201 .068999998 8.04215889 .071999997 7.850354602525 3102   46
 .075999998 7.64490573 .079999998 7.45726121 .083999999 7.280971782525 3102   47
 .088000000 7.11715255 .092000000 6.96557614 .096000001 6.820888452525 3102   48
 .100000001 6.67151668 .104999997 6.51337408 .109999999 6.368653332525 3102   49
 .115000002 6.23031740 .119999997 6.07166588 .127499998 5.896271252525 3102   50
 .135000005 5.73360932 .142499998 5.58432775 .150000006 5.425221582525 3102   51
 .159999996 5.25797835 .170000002 5.10499237 .180000007 4.965220922525 3102   52
 .189999998 4.83697678 .200000003 4.71666452 .209999993 4.606885102525 3102   53
 .219999999 4.50328170 .230000004 4.40673826 .239999995 4.295008192525 3102   54
 .254999995 4.16988289 .270000011 4.07410511 .280000001 3.967682092525 3102   55
 .300000012 3.83731116 .319999993 3.71906586 .340000004 3.611487862525 3102   56
 .360000014 3.51295061 .379999995 3.42086005 .400000006 3.327718272525 3102   57
 .425000012 3.23316859 .449999988 3.14339320 .474999994 3.061576532525 3102   58
 .500000000 2.98658914 .524999976 2.91563291 .550000012 2.850697872525 3102   59
 .574999988 2.78904017 .600000024 2.72618353 .629999995 2.662508792525 3102   60
 .660000026 2.60220368 .689999998 2.54701552 .720000029 2.485490582525 3102   61
 .759999990 2.42159634 .800000012 2.36390611 .839999974 2.307430882525 3102   62
 .879999995 2.25618204 .920000017 2.20711669 .959999979 2.162282282525 3102   63
 1.00000000 2.11396879 1.04999995 2.06455202 1.10000002 2.018342272525 3102   64
 1.14999998 1.97485369 1.20000005 1.92504843 1.27499998 1.869240432525 3102   65
 1.35000002 1.81817448 1.42499995 1.77151193 1.50000000 1.720990942525 3102   66
 1.60000002 1.66833877 1.70000005 1.62061813 1.79999995 1.577501822525 3102   67
 1.89999998 1.53633298 2.00000000 1.49872866 2.09999990 1.463377202525 3102   68
 2.20000005 1.43110672 2.29999995 1.40033212 2.40000010 1.365060862525 3102   69
 2.54999995 1.32611312 2.70000005 1.29558299 2.79999995 1.262322122525 3102   70
 3.00000000 1.22151624 3.20000005 1.18446758 3.40000010 1.150730102525 3102   71
 3.59999990 1.12030727 3.79999995 1.09130384 4.00000000 1.062216532525 3102   72
 4.25000000 1.03156309 4.50000000 1.00380165 4.75000000 .9784791932525 3102   73
 5.00000000 .954717865 5.25000000 .932782336 5.50000000 .9124324242525 3102   74
 5.75000000 .893112795 6.00000000 .873754670 6.30000019 .8536232792525 3102   75
 6.59999990 .835215775 6.90000010 .817826751 7.19999981 .7993922782525 3102   76
 7.59999990 .779064006 8.00000000 .761046505 8.39999962 .7434164102525 3102   77
 8.80000019 .727236009 9.19999981 .712784460 9.60000038 .6987963352525 3102   78
 10.0000000 .683807654 10.5000000 .668537936 11.0000000 .6543557092525 3102   79
 11.5000000 .640924109 12.0000000 .625546703 12.7500000 .6090308242525 3102   80
 13.5000000 .593231212 14.2500000 .579253798 15.0000000 .5637573762525 3102   81
 16.0000000 .548133372 17.0000000 .533438811 18.0000000 .5201794832525 3102   82
 19.0000000 .508113566 20.0000000 .496805619 21.0000000 .4864475312525 3102   83
 22.0000000 .476931241 23.0000000 .468038827 24.0000000 .4575678872525 3102   84
 25.5000000 .446585630 27.0000000 .437515619 28.0000000 .4280531342525 3102   85
 30.0000000 .416384327 32.0000000 .406194345 34.0000000 .3965543532525 3102   86
 36.0000000 .388085766 38.0000000 .380562488 40.0000000 .3726209172525 3102   87
 42.5000000 .364787283 45.0000000 .357664387 47.5000000 .3513309852525 3102   88
 50.0000000 .345529990 52.5000000 .340454878 55.0000000 .3358198712525 3102   89
 57.5000000 .331458462 60.0000000 .327492717 63.0000000 .3233689752525 3102   90
 66.0000000 .319662376 69.0000000 .316611514 72.0000000 .3136077742525 3102   91
 76.0000000 .310483052 80.0000000 .308103202 84.0000000 .3062908522525 3102   92
 88.0000000 .304877496 92.0000000 .304129079 96.0000000 .3035916572525 3102   93
 100.000000 .303798850 105.000000 .304492151 110.000000 .3060217312525 3102   94
 115.000000 .307938709 120.000000 .311490802 127.500000 .3170589832525 3102   95
 135.000000 .324343252 142.500000 .333241886 150.000000 .3461758562525 3102   96
 160.000000 .364380821 170.000000 .387408867 180.000000 .4159159992525 3102   97
 190.000000 .451716142 200.000000 .496626962 210.000000 .5534975502525 3102   98
 220.000000 .626778179 230.000000 .722826596 240.000000 .8927626382525 3102   99
 255.000000 1.21455095 270.000000 1.66066610 280.000000 2.787732062525 3102  100
 300.000000 7.64695078 320.000000 32.0716173 340.000000 21.79580152525 3102  101
 360.000000 4.92641131 380.000000 1.93454159 400.000000 .9692847862525 3102  102
 425.000000 .554036796 450.000000 .365099359 475.000000 .2638073652525 3102  103
 500.000000 .203644625 525.000000 .165091912 550.000000 .1390815832525 3102  104
 575.000000 .120836024 600.000000 .106629084 630.000000 .0956494812525 3102  105
 660.000000 .088011582 690.000000 .082796624 720.000000 .0792082212525 3102  106
 760.000000 .077781743 800.000000 .079440657 840.000000 .0849612782525 3102  107
 880.000000 .096843366 920.000000 .121259750 960.000000 .1771357282525 3102  108
 1000.00000 .405906404 1050.00000 6.82454289 1100.00000 5.669811202525 3102  109
 1150.00000 .362922980 1200.00000 .135326257 1275.00000 .0814805222525 3102  110
 1350.00000 .067185336 1425.00000 .063830493 1500.00000 .0678397682525 3102  111
 1600.00000 2.00709610 1700.00000 .091643683 1800.00000 .1131801142525 3102  112
 1900.00000 .155612894 2000.00000 .231560731 2100.00000 .3637798062525 3102  113
 2200.00000 .532485764 2300.00000 .564672971 2400.00000 .3616478762525 3102  114
 2550.00000 .173581391 2700.00000 .101383890 2800.00000 .0626053172525 3102  115
 3000.00000 .037614764 3200.00000 .025780154 3400.00000 .0193484292525 3102  116
 3600.00000 .015524039 3800.00000 .013933781 4000.00000 .0121013302525 3102  117
 4250.00000 .017858518 4500.00000 .010019391 4750.00000 .4341479382525 3102  118
 5000.00000 .011191569 5250.00000 .011343136 5500.00000 .0131607792525 3102  119
 5750.00000 .016506710 6000.00000 .024240580 6300.00000 .1880253652525 3102  120
 6600.00000 .118551401 6900.00000 .368728840 7200.00000 .1541118822525 3102  121
 7600.00000 .047031546 8000.00000 .051335651 8400.00000 .2067577862525 3102  122
 8800.00000 .221878480 9200.00000 .042097695 9600.00000 .0199195722525 3102  123
 10000.0000 .008594289 10500.0000 .071149886 11000.0000 .0037810102525 3102  124
 11500.0000 .022854740 12000.0000 .069200279 12750.0000 .0020981072525 3102  125
 13500.0000 .001627971 14250.0000 .046109203 15000.0000 .0016402262525 3102  126
 16000.0000 .029458063 17000.0000 .130854113 18000.0000 .0502274762525 3102  127
 19000.0000 .009456944 20000.0000 .070705073 21000.0000 .0243172022525 3102  128
 22000.0000 .038367457 23000.0000 .036942031 24000.0000 .0226151772525 3102  129
 25500.0000 .069917782 27000.0000 .038371766 28000.0000 .0150495922525 3102  130
 30000.0000 .021166131 32000.0000 .026460201 34000.0000 .0565505602525 3102  131
 36000.0000 .023746549 38000.0000 .004205812 40000.0000 .0324913042525 3102  132
 42500.0000 .020375006 45000.0000 .011843840 47500.0000 .0081271672525 3102  133
 50000.0000 .011519836 52500.0000 .022264406 55000.0000 .0169532242525 3102  134
 57500.0000 .020321384 60000.0000 .016414420 63000.0000 .0229886212525 3102  135
 66000.0000 .018082623 69000.0000 .032203939 72000.0000 .0126870832525 3102  136
 76000.0000 .008990626 80000.0000 .015362294 84000.0000 .0230386352525 3102  137
 88000.0000 .013447072 92000.0000 .007114579 96000.0000 .0126574952525 3102  138
 100000.000 .013806739 105000.000 .013550256 110000.000 .0136299922525 3102  139
 115000.000 .013850078 120000.000 .014341383 127500.000 .0145210592525 3102  140
 135000.000 .011994399 142500.000 .007991463 150000.000 .0078895692525 3102  141
 160000.000 .008206275 170000.000 .008248789 180000.000 .0077906912525 3102  142
 190000.000 .007096819 200000.000 .006509434 210000.000 .0061033842525 3102  143
 220000.000 .006045272 230000.000 .005877501 240000.000 .0054732062525 3102  144
 255000.000 .005270608 270000.000 .005672634 280000.000 .0062395712525 3102  145
 300000.000 .005588775 320000.000 .005429058 340000.000 .0054481402525 3102  146
 360000.000 .004134608 380000.000 .004576443 400000.000 .0054508182525 3102  147
 425000.000 .004852925 450000.000 .005400591 475000.000 .0045650072525 3102  148
 500000.000 .003995238 525000.000 .004095028 550000.000 .0044449782525 3102  149
 575000.000 .004432601 600000.000 .003668962 630000.000 .0037604722525 3102  150
 660000.000 .004102263 690000.000 .003633306 720000.000 .0033332162525 3102  151
 760000.000 .003279851 800000.000 .003243539 840000.000 .0032055942525 3102  152
 880000.000 .003123043 920000.000 .002977128 960000.000 .0027922012525 3102  153
 1000000.00 .002620025 1100000.00 .002490003 1200000.00 .0023800022525 3102  154
 1300000.00 .002284992 1400000.00 .002139233 1500000.00 .0019950132525 3102  155
 1600000.00 .001940005 1700000.00 .001914998 1800000.00 .0018799982525 3102  156
 1900000.00 .001835002 2000000.00 .001802005 2100000.00 .0017860032525 3102  157
 2200000.00 .001770001 2300000.00 .001753999 2400000.00 .0017379982525 3102  158
 2500000.00 .001721996 2600000.00 .001705994 2700000.00 .0016849272525 3102  159
 2800000.00 .001633472 2900000.00 .001577164 3000000.00 .0015300022525 3102  160
 3100000.00 .001490001 3200000.00 .001451001 3300000.00 .0014180012525 3102  161
 3400000.00 .001386001 3500000.00 .001356001 3600000.00 .0013280012525 3102  162
 3700000.00 .001300509 3800000.00 .001276061 3900000.00 .0012521212525 3102  163
 4000000.00 .001228181 4100000.00 .001204868 4200000.00 .0011828282525 3102  164
 4300000.00 .001160882 4400000.00 .001139808 4500000.00 .0011190302525 3102  165
 4600000.00 .001098252 4700000.00 .001077733 4800000.00 .0010584212525 3102  166
 4900000.00 .001039262 5000000.00 .001020102 5100000.00 .0010009422525 3102  167
 5200000.00 .000982035 5300000.00 .000964328 5400000.00 .0009467772525 3102  168
 5500000.00 .000930649 5600000.00 .000915945 5700000.00 .0009012422525 3102  169
 5800000.00 .000886609 5900000.00 .000873163 6000000.00 .0008601392525 3102  170
 6100000.00 .000847563 6200000.00 .000835951 6300000.00 .0008243712525 3102  171
 6400000.00 .000812791 6500000.00 .000802101 6600000.00 .0007923012525 3102  172
 6700000.00 .000782501 6800000.00 .000772701 6900000.00 .0007629012525 3102  173
 7000000.00 .000754501 7100000.00 .000747501 7200000.00 .0007405012525 3102  174
 7300000.00 .000733501 7400000.00 .000726501 7500000.00 .0007211012525 3102  175
 7600000.00 .000717301 7700000.00 .000713501 7800000.00 .0007097012525 3102  176
 7900000.00 .000705901 8000000.00 .000703201 8100000.00 .0007016012525 3102  177
 8200000.00 .000700001 8300000.00 .000698400 8400000.00 .0006968002525 3102  178
 8500000.00 .000695633 8600000.00 .000694900 8700000.00 .0006941672525 3102  179
 8800000.00 .000693433 8900000.00 .000692700 9000000.00 .0006919672525 3102  180
 9100000.00 .000691233 9200000.00 .000690500 9300000.00 .0006897672525 3102  181
 9400000.00 .000689033 9500000.00 .000688300 9600000.00 .0006875672525 3102  182
 9700000.00 .000686833 9800000.00 .000686100 9900000.00 .0006853672525 3102  183
 10000000.0 .000684825 10100000.0 .000684475 10200000.0 .0006841252525 3102  184
 10300000.0 .000683775 10400000.0 .000683425 10500000.0 .0006830752525 3102  185
 10600000.0 .000682725 10700000.0 .000682375 10800000.0 .0006820252525 3102  186
 10900000.0 .000681675 11000000.0 .000681325 11100000.0 .0006809752525 3102  187
 11200000.0 .000680625 11300000.0 .000680275 11400000.0 .0006799252525 3102  188
 11500000.0 .000679575 11600000.0 .000679225 11700000.0 .0006788752525 3102  189
 11800000.0 .000678525 11900000.0 .000678175 12000000.0 .0006776852525 3102  190
 12100000.0 .000677056 12200000.0 .000676426 12300000.0 .0006757972525 3102  191
 12400000.0 .000675167 12500000.0 .000674537 12600000.0 .0006739082525 3102  192
 12700000.0 .000673278 12800000.0 .000672649 12900000.0 .0006720192525 3102  193
 13000000.0 .000671390 13100000.0 .000670760 13200000.0 .0006701302525 3102  194
 13300000.0 .000669501 13400000.0 .000668871 13500000.0 .0006682422525 3102  195
 13600000.0 .000667612 13700000.0 .000666925 13800000.0 .0006659192525 3102  196
 13900000.0 .000664866 14000000.0 .000663812 14100000.0 .0006627592525 3102  197
 14200000.0 .000661705 14300000.0 .000660651 14400000.0 .0006595982525 3102  198
 14500000.0 .000658544 14600000.0 .000657491 14700000.0 .0006564372525 3102  199
 14800000.0 .000655383 14900000.0 .000654330 15000000.0 .0006532762525 3102  200
 15100000.0 .000652135 15200000.0 .000650786 15300000.0 .0006494292525 3102  201
 15400000.0 .000648072 15500000.0 .000646714 15600000.0 .0006453572525 3102  202
 15700000.0 .000643970 15800000.0 .000642400 15900000.0 .0006408002525 3102  203
 16000000.0 .000638800 16100000.0 .000636400 16200000.0 .0006340002525 3102  204
 16300000.0 .000631599 16400000.0 .000629199 16500000.0 .0006259992525 3102  205
 16600000.0 .000621999 16700000.0 .000617999 16800000.0 .0006139982525 3102  206
 16900000.0 .000609998 17000000.0 .000604498 17100000.0 .0005974982525 3102  207
 17200000.0 .000590499 17300000.0 .000583499 17400000.0 .0005764992525 3102  208
 17500000.0 .000568499 17600000.0 .000559499 17700000.0 .0005504992525 3102  209
 17800000.0 .000541499 17900000.0 .000532499 18000000.0 .0005225602525 3102  210
 18100000.0 .000511682 18200000.0 .000500805 18300000.0 .0004899272525 3102  211
 18400000.0 .000479172 18500000.0 .000467322 18600000.0 .0004539702525 3102  212
 18700000.0 .000440765 18800000.0 .000428381 18900000.0 .0004161262525 3102  213
 19000000.0 .000401843 19100000.0 .000385857 19200000.0 .0003706312525 3102  214
 19300000.0 .000355930 19400000.0 .000341972 19500000.0 .0003253282525 3102  215
 19600000.0 .000306371 19700000.0 .000288758 19800000.0 .0002721502525 3102  216
 19900000.0 .000256641 20000000.0 0.0                             2525 3102  217
                                                                  2525 3  099999
                                                                  2525 0  0    0
 2.50550E+4 5.44661E+1          0          0          0          1252533102    1
 0.000000+0 0.000000+0          0        102          0          3252533102    2
 0.000000+0 0.000000+0          0          1          8          4252533102    3
 1.000000-5 1.600000-3 1.000000+3 2.500000-3 2.000000+6 1.000000-2252533102    4
 2.000000+7 0.000000+0                                            252533102    5
 0.000000+0 0.000000+0          0          1         26         13252533102    6
 1.000000-5 3.960000-4 2.530000-2 2.227500-4 5.000000+1 3.960000-4252533102    7
 2.000000+3 3.564000-3 6.000000+4 6.336000-3 1.500000+5 9.900000-3252533102    8
 1.000000+6 2.227500-2 2.000000+6 2.227500-2 5.000000+6 3.960000-2252533102    9
 7.000000+6 3.960000-2 1.000000+7 8.910000-2 1.450000+7 8.910000-2252533102   10
 2.000000+7 0.000000+0                                            252533102   11
 0.000000+0 0.000000+0          0          8         26         13252533102   12
 1.000000-5 1.960000-2 2.530000-2 6.692000-3 5.000000+1 1.090900-6252533102   13
 2.000000+3 2.851600-3 6.000000+4 1.747200-7 1.500000+5 5.975300-9252533102   14
 1.000000+6 1.802000-9 2.000000+6 7.37120-10 5.000000+6 4.24360-10252533102   15
 7.000000+6 2.29830-10 1.000000+7 4.22300-10 1.450000+7 3.92040-10252533102   16
 2.000000+7 0.000000+0                                            252533102   17
                                                                  252533  099999
                                                                  2525 0  0    0
                                                                     0 0  0    0
 2.60540E+4 5.34762E+1          0          0         34         102625 1451    1
 0.0        0.0                 0          0          0          62625 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022625 1451    3
 3.00000E+2 0.0                 1          0        527          82625 1451    4
 26-Fe- 54 FEI/LANL   EVAL-Jun01 K.I.Zolotarev,M.Chadwick et al.  2625 1451    5
                      DIST-Feb2004                                2625 1451    6
----IRDF-2002         MATERIAL 2625                               2625 1451    7
-----INCIDENT NEUTRON DATA                                        2625 1451    8
------ENDF-6 FORMAT                                               2625 1451    9
***************************************************************** 2625 1451   10
 26-Fe- 54 FEI        EVAL-Jun01 K.I.Zolotarev                    2625 1451   11
                      DIST-May03 Mod1                  20030512   2625 1451   12
----BROND-2           MATERIAL 2625         REVISION 1            2625 1451   13
-----INCIDENT NEUTRON DATA                                        2625 1451   14
------ENDF-6 FORMAT                                               2625 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    2625 1451   16
***************************************************************** 2625 1451   17
Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko           2625 1451   18
MF=3                                                              2625 1451   19
MT= 16 - (n,2n) cross section                                     2625 1451   20
MT=107 - (n,a) cross section                                      2625 1451   21
***************************************************************** 2625 1451   22
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2625 1451   23
DOSIMETRY                                                         2625 1451   24
******************************************************************2625 1451   25
  26-Fe- 54 LANL,ORNL EVAL-SEP96 M.B.CHADWICK,P.G.YOUNG,D.HETRICK 2625 1451   26
 Ch99,He91,Fu91       DIST-SEP 1 REV4-                 20010926   2625 1451   27
----ENDF/B-VI         MATERIAL 2625         REVISION 4            2625 1451   28
MF=3                                                              2625 1451   29
MT= 103 - (n,p) cross section                                     2625 1451   30
******************************************************************2625 1451   31
******** Start of (N,2N), (N,A) bibliographical component ******* 2625 1451   32
***************************************************************** 2625 1451   33
------Russian Reactor Dosimetry File RRDF-2002                    2625 1451   34
***************************************************************** 2625 1451   35
Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko           2625 1451   36
MF=3                                                              2625 1451   37
MT= 16 - (n,2n) cross section                                     2625 1451   38
-------------------------------------                             2625 1451   39
    Excitation function for the  Fe-54(n,2n)Fe-53m+g  reaction in 2625 1451   40
the energy region from threshold to 21 MeV was evaluated by means 2625 1451   41
of statistical analysis of experimental cross section data [1-16] 2625 1451   42
and data from GNASH [31-32] calculation.                          2625 1451   43
    All experimental data if it was possible were renormalized to 2625 1451   44
the new standards for  monitor reactions cross sections and decay 2625 1451   45
data. Decay data for the iron-53 were taken from ref. [17]. Recom-2625 1451   46
mended cross sections for the reaction Al-27(n,p)Mg-27  used as a 2625 1451   47
monitor  in the measurements  [7-8], [11-14] and [16]  were taken 2625 1451   48
from new evaluation [18].                                         2625 1451   49
    Special correction was done with experimental data [1], [6].  2625 1451   50
    Data of Terrel and Holm [1] measured  at  16.89 and 17.89 MeV 2625 1451   51
have been corrected introducing the  Fc= 0.5 coefficient, because 2625 1451   52
of authors used double decreased value for positron yield.        2625 1451   53
    Data of Andreev et al.[6] were renormalized using preliminary 2625 1451   54
evaluated integral of cross section value in  the  neutron energy 2625 1451   55
range from  15.0 to 16.5 MeV.  Renormalised experimental data  of 2625 1451   56
Andreev et al. are well consistent with Ryves measurements [9-10] 2625 1451   57
and with new experimental data for  Fe-54(n,2n)Fe-53m+g  reaction 2625 1451   58
obtained by Fessler [16].                                         2625 1451   59
    Experimental data from ref.[19-27] were rejected due to their 2625 1451   60
discrepancy  with  the main bulk of experimental data [1-16]  and 2625 1451   61
data from theoretical model calculation.                          2625 1451   62
    The final procedure of evaluation Fe54(n,2n)Fe53m+g excitati- 2625 1451   63
on function from threshold to 21 MeV  has been carried out within 2625 1451   64
the framework of generalized least squares method. Rational func- 2625 1451   65
tion was used as model function [28].                             2625 1451   66
    U-235 thermal fission [29]  and  Cf-252  spontaneous fission  2625 1451   67
neutron spectra [30] averaged cross sections calculated  from the 2625 1451   68
evaluated Fe54(n,2n)Fe53m+g excitation function are the following:2625 1451   69
                                                                  2625 1451   70
        ----------------------------------------------            2625 1451   71
              TYPE OF SPECTRUM     I <CS>, mb (calc.)             2625 1451   72
        ---------------------------I------------------            2625 1451   73
         U-235  neutron  fission   I    1.2839E-3                 2625 1451   74
         CF-252 spontan. fission   I    3.6219E-3                 2625 1451   75
        ----------------------------------------------            2625 1451   76
                                                                  2625 1451   77
                                                                  2625 1451   78
MT=107 - (n,a) cross section                                      2625 1451   79
-------------------------------------                             2625 1451   80
    Excitation function for the  Fe-54(n,a)Cr-51  reaction in the 2625 1451   81
energy region from  3 MeV to 20 MeV  was  evaluated  by  means of 2625 1451   82
statistical analysis of experimental cross section data [3], [4], 2625 1451   83
[11], [15], [21], [34-49] and data from GNASH [31-32] calculation.2625 1451   84
    All experimental data were renormalized to  the new standards 2625 1451   85
for monitor reactions cross sections and decay data. Experimental 2625 1451   86
data of  S.R.Salisbury and R.A.Chalmers [5]  were rejected due to 2625 1451   87
their inconsistency  with  theoretical model calculations data in 2625 1451   88
the energy region 3-5 MeV.  Data  of  Y.M.Gledenov et al. [50] at 2625 1451   89
7 MeV were rejected due to their very big discrepancy with measu- 2625 1451   90
rements [39,46,49] and data from theoretical model calculation.   2625 1451   91
    The final procedure of evaluation  Fe-54(n,a)Cr-51 excitation 2625 1451   92
function from  3 MeV to 20 MeV  have been carried out  within the 2625 1451   93
framework of generalized least squares method.  Rational function 2625 1451   94
was used as a model function [28].                                2625 1451   95
    Integral experimental data for U-235 neutron fission spectrum 2625 1451   96
[51-53] was used for testing evaluated Fe-54(n,a)Cr-51 excitation 2625 1451   97
function. The results of testing are given in Table 1.            2625 1451   98
    Data for  U-235 thermal fission neutron spectrum  and  Cf-252 2625 1451   99
spontaneous fission neutron spectrum were taken from ref.[29] and 2625 1451  100
[30],  respectively.                                              2625 1451  101
                                                     Table 1.     2625 1451  102
 ---------------------------------------------------------------  2625 1451  103
    TYPE OF SPECTRUM   I <CS>,MB (calc.) I   <CS>, MB (measured)  2625 1451  104
 ----------------------I-----------------I----------------------  2625 1451  105
                       I                 I                        2625 1451  106
 U-235 neutron fission I    0.8459       I  0.790 +- 0.119 [51]   2625 1451  107
                       I                 I  0.850 +- 0.100 [52]   2625 1451  108
                       I                 I  0.891 +- 0.070 [53]   2625 1451  109
                       I                 I  0.850 +- 0.050 [* ]   2625 1451  110
                       I                 I                        2625 1451  111
 ----------------------I-----------------I----------------------  2625 1451  112
                       I                 I                        2625 1451  113
 CF-252 spont. fission I    1.1114       I                        2625 1451  114
                       I                 I                        2625 1451  115
 ---------------------------------------------------------------  2625 1451  116
 [*] -   Averaged cross section value obtained from ref. [51-53]  2625 1451  117
                                                                  2625 1451  118
MF=33                                                             2625 1451  119
MT= 16 - (n,2n) cross section cov. matrix                         2625 1451  120
------------------------------------------                        2625 1451  121
    Uncertainties in the evaluated  excitation function  for the  2625 1451  122
reaction Fe-54(n,2n)Fe-53m+g are given in the form of relative co-2625 1451  123
variance matrix for the 12-neutron energy groups (LB=5).  Covari- 2625 1451  124
ance matrix of uncertainties  was calculated  simultaneously with 2625 1451  125
recommended cross section data by means of PADE-2 code [33].      2625 1451  126
    Eigenvalues  of the  6-th digits  relative covariance matrix  2625 1451  127
given in the 33-file are the following:                           2625 1451  128
                                                                  2625 1451  129
    3.65349E-06    4.84130E-06    6.69851E-06    1.07852E-05      2625 1451  130
    2.27150E-05    7.28051E-05    4.72794E-04    5.38548E-03      2625 1451  131
    1.13987E-02    1.32443E-02    3.40784E-02    1.48451E-01      2625 1451  132
                                                                  2625 1451  133
MT=107 - (n,a) cross section cov. matrix                          2625 1451  134
------------------------------------------                        2625 1451  135
    Uncertainties in the evaluated  excitation function  for  the 2625 1451  136
reaction Fe-54(n,a)Cr-51 are given in the form of relative covari-2625 1451  137
ance matrix for the  17-neutron energy groups (LB=5).  Covariance 2625 1451  138
matrix  of  uncertainties  was  calculated  simultaneously  with  2625 1451  139
recommended cross section data by means of PADE-2 code [33].      2625 1451  140
    Eigenvalues  of the  6-th digits  relative covariance matrix  2625 1451  141
given in the 33-file are the following:                           2625 1451  142
                                                                  2625 1451  143
    1.85377E-09    2.23510E-09    2.38367E-09    2.64130E-09      2625 1451  144
    3.38901E-09    3.88584E-09    5.57195E-09    9.37333E-09      2625 1451  145
    2.56042E-08    1.44977E-06    8.05497E-04    1.66197E-03      2625 1451  146
    2.03640E-03    2.27545E-03    4.21154E-03    1.42809E-02      2625 1451  147
    2.58358E-02                                                   2625 1451  148
                                                                  2625 1451  149
References :                                                      2625 1451  150
 1. J.Terrell, D.M.Holm  Physical Review, v.109, p.2031, 1958     2625 1451  151
 2. M.J.Depraz et al.  Journal de Physique, v.21, p.377, May 1960 2625 1451  152
 3. D.M.Chittenden et al.  Physical Review, v.122, p.860, 1961    2625 1451  153
 4. W.G.Cross et al. Prog. Report EANDC(CAN)-16, p., January 1963 2625 1451  154
 3. W.G.Cross et al.  Prog. Report EANDC(CAN)-16, p.1, Jan. 1963  2625 1451  155
 5. S.R.Salisbury, R.A.Chalmers  Phys. Rev., v.B140, p.305, 1965  2625 1451  156
 6. M.F.Andreev, V.I.Serov  Jadernaja Fizika (Sov.), v.7, n.4,    2625 1451  157
    p.745, April 1968                                             2625 1451  158
 7. S.M.Qaim  Nuclear Physics, v.A185, p.614, May 1972            2625 1451  159
 8. R.A.Sigg, P.K.Kuroda  Inorg. Nucl. Chem., v.37, p.631, 1975   2625 1451  160
 9. T.B.Ryves et al.  J. Metrologia, v.14, n.3, p.127, June 1978  2625 1451  161
10. T.B.Ryves et al.  J. of Physics, pt.G, v.4, p.1783, 1978      2625 1451  162
11. B.M.Bahal, R.Pepelnik  Report GKSS-84-E-, 1984 ;              2625 1451  163
    B.M.Bahal, R.Pepelnik  Progress Report NEANDC(E)-252/U,(5),   2625 1451  164
    p.28, June 1984                                               2625 1451  165
12. L.R.Greenwood, R.K.Smither  Proc. of Intern. Conf. on Nuclear 2625 1451  166
    Data for Basic and Applied Science, Santa Fe, New Mexico, USA,2625 1451  167
    13-17 May 1985, v.1, p.163                                    2625 1451  168
13. T.Katoh et al.  Report JAERI-M-89-083, 1989                   2625 1451  169
14. M.Viennot et al.  Nucl. Sci. Eng., v.108, p.289, July 1991    2625 1451  170
15. A.Ercan et al.  Proc. of International Conference on Nuclear  2625 1451  171
    Data for Science and Technology, 13-17 May 1991, Julich, FRG, 2625 1451  172
    Springer-Verlag, 1992, p.376-377                              2625 1451  173
16. A.Fessler  Report JUL-3502, FZ Julich GmbH, Germany, 1998     2625 1451  174
17. E.Browne, R.B.Firestone   Table of  Radioactive  Isotopes,    2625 1451  175
    John Wiley & Sons, New York, 1986 ;                           2625 1451  176
    R.B.Firestone   Table of Isotopes, Eighth edition, Vol. 1,    2625 1451  177
    John Wiley & Sons, Inc., New York, 1995                       2625 1451  178
18. K.I.Zolotarev  Report INDC(CCP)-431, Distr.: J+R/EL, IAEA,    2625 1451  179
    Vienna, August 2002                                           2625 1451  180
19. D.L.Allan   J. Proc. Phys. Soc., v.70, p.195, 1956            2625 1451  181
20. L.A.Rayburn   Phys. Rev., v.122, p.168, 1961                  2625 1451  182
21. H.Pollehn, H.Neuert  Zeitschrift f. Naturforschung, sect.A,   2625 1451  183
    v.16, p.227, 1961                                             2625 1451  184
22. C.Carles  Comptes Rendus, v.257, p.659, July 1963             2625 1451  185
23. J.Csikai  Report EANDC-50S, v.2, p.102, July 1965             2625 1451  186
24. J.E.Strain, W.J.Ross  Report ORNL-3672, January 1965          2625 1451  187
25. J.Araminowicz, J.Dresler Rep.INR-1464, Swierk-Warsew,May 1973 2625 1451  188
26. M.Bormann et al.  Zeitsch. f. Physik, sect.A, v.277, p.203,   2625 1451  189
    June 1976                                                     2625 1451  190
27. Zhou Muyao et al. Chinese J. of Nucl. Phys., v.9, p.34, 1987  2625 1451  191
28. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2625 1451  192
    st's Meeting on Evaluation and Processing of Covariance Data, 2625 1451  193
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  2625 1451  194
29. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2625 1451  195
    Library, MAT-9228, MF=5, MT=18, eval. April 1989              2625 1451  196
30. W.Mannhart  Report IAEA-TECDOC-410, p.158, 1987               2625 1451  197
31. P.G.Young, E.D.Arthur  A Preequilibrium Statistical Nuclear   2625 1451  198
    Model Code for Calculation of Cross Section and Emission      2625 1451  199
    Spectra. Report LA-6947, Los Alamos, 1977                     2625 1451  200
32. E.L.Trykov, G.Ya.Tertychnyi  Private communication, IPPE,     2625 1451  201
    Obninsk, May 1999                                             2625 1451  202
33. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          2625 1451  203
34. P.Venugopala Rao, R.W.Fink  Phys. Rev., v.154, p.1023, 1967   2625 1451  204
35. S.M.Qaim et al.  Conf. on Chemical Nuclear Data, Measurements 2625 1451  205
    and Applicat., Univ. of Kent, Canterbury,20-22 September 1971,2625 1451  206
    p.121                                                         2625 1451  207
36. J.J.Singh  Trans. Amer. Nucl. Soc., v.15, p.147, June 1972    2625 1451  208
37. G.N.Maslov et al. Sov. J. Yadernye Konstanty, v.9, p.50, 1972 2625 1451  209
38. K.Fukuda et al.  Prog. Report NEANDC(J)-56/U, p.44, Sep. 1978 2625 1451  210
39. A.Paulsen et al.  Nucl. Sci. Eng., v.72, v.1, p.113, 1979     2625 1451  211
40. O.I.Artem'ev et al.  Atomnaja Energija (Sov.), v.49, no.3,    2625 1451  212
    p.195, September 1980                                         2625 1451  213
41. L.R.Greenwood  Progress Report DOE-ER-0046-21, p.15, May 1985 2625 1451  214
42. J.W.Meadows et al.  Annals of Nuclear Energy, v.14, p.489,    2625 1451  215
    September 1987                                                2625 1451  216
43. Y.Ikeda, C.Konno, K.Oishi et al.  Report JAERI-1312, 1988     2625 1451  217
44. Lu Hanlin et al.  Report INDC(CPR)-16, August 1989            2625 1451  218
45. S.K.Saraf et al.  Nucl. Sci. Eng., v.107, p.365, April 1991   2625 1451  219
46. J.W.Meadows, W.Mannhart et.al.  Proc. of Intern. Conference   2625 1451  220
    on Nuclear Data for Science and Technology, 13-17 May 1991,   2625 1451  221
    Julich, FRG, Springer-Verlag, 1992, p.288-290                 2625 1451  222
47. A.Grallert et al.  Report INDC(NDS)-286, p.193, IAEA, 1993    2625 1451  223
48. J.W.Meadows et al.  Annals of Nuclear Energy, v.23, p.877,    2625 1451  224
    July 1996                                                     2625 1451  225
49. Lu Hanlin et al.  Report INDC(CPR)-045, IAEA, Vienna, 1998    2625 1451  226
50. Y.M.Gledenov et al.  Report INDC(CPR)-042, IAEA, Vienna, 1997 2625 1451  227
51. H.Braun, L.Nagy  Radiochimica Acta, v.10, p.15, 1968          2625 1451  228
52. A.V.Bushuev et al.  Atomnaja Energija (Sov.), v.63, no.3,     2625 1451  229
    p.207, September 1987                                         2625 1451  230
53. O.Horibe et al.   Proc. of Conference: 50 Years with  Nuclear 2625 1451  231
    Fission, Washington D.C., 25-28 April 1989, v.2, p.923        2625 1451  232
******************************************************************2625 1451  233
********  End of (N,2N), (N,A) bibliographical component ******** 2625 1451  234
***************************************************************** 2625 1451  235
******************************************************************2625 1451  236
*********    Start of (N,P) bibliographical component   ********* 2625 1451  237
***************************************************************** 2625 1451  238
                                                                  2625 1451  239
 ENDF/B-VI MOD 5 Revision, May 2000, S.C. Frankle, R.C. Reedy,    2625 1451  240
                 P.G. Young (LANL)                                2625 1451  241
                                                                  2625 1451  242
 The secondary gamma-ray spectrum for radiative capture (MF 12,   2625 1451  243
 MT 102) has been updated for new experimental data at incident   2625 1451  244
 neutron energies up to 1 keV.                                    2625 1451  245
 The MF=12, MT=102 yields above 1 keV were adjusted slightly to   2625 1451  246
 force energy conservation.                                       2625 1451  247
 The Q-value for radiative capture was also updated in File 3.    2625 1451  248
 Details of these changes are described in Frankel et al. [Fr01]. 2625 1451  249
                                                                  2625 1451  250
******************************************************************2625 1451  251
                                                                  2625 1451  252
 ENDF/B-VI MOD 4 Evaluation, September 1997, M.B. Chadwick,       2625 1451  253
                 P.G. Young (LANL) and A.J. Koning (ECN)          2625 1451  254
                                                                  2625 1451  255
 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code     2625 1451  256
   in cooperation with ECN Petten.                                2625 1451  257
                                                                  2625 1451  258
  This evaluation provides a complete representation of the       2625 1451  259
nuclear data needed for transport, damage, heating,               2625 1451  260
radioactivity, and shielding applications over the incident       2625 1451  261
neutron energy range from 1.0E-11 to 150 MeV.  The discussion     2625 1451  262
here is divided into the region below and above 20 MeV.           2625 1451  263
                                                                  2625 1451  264
INCIDENT NEUTRON ENERGIES < 20 MeV                                2625 1451  265
                                                                  2625 1451  266
  Below 20 MeV the evaluation is based completely on the ENDF/B-  2625 1451  267
VI.1 (Release 1) evaluation by [He91] (see also [Fu86]).  The     2625 1451  268
following modifications were made to the ENDF/B-VI.1 evaluation:  2625 1451  269
                                                                  2625 1451  270
1.  The covariance files (MF=33) were removed from the file.      2625 1451  271
                                                                  2625 1451  272
2.  The derived MF=3 files for MT=203,205,207 were removed.       2625 1451  273
                                                                  2625 1451  274
                                                                  2625 1451  275
INCIDENT NEUTRON ENERGIES > 20 MeV                                2625 1451  276
                                                                  2625 1451  277
  The evaluation above 20 MeV utilizes MF=6, MT=5 to represent    2625 1451  278
all reaction data.  Production cross sections and emission        2625 1451  279
spectra are given for neutrons, protons, deuterons, tritons,      2625 1451  280
alpha particles, gamma rays, and all residual nuclides produced   2625 1451  281
(A>5) in the reaction chains. To summarize, the ENDF sections     2625 1451  282
with non-zero data above En = 20 MeV are:                         2625 1451  283
                                                                  2625 1451  284
  MF=3 MT=  1  Total Cross Section                                2625 1451  285
       MT=  2  Elastic Scattering Cross Section                   2625 1451  286
       MT=  3  Nonelastic Cross Section                           2625 1451  287
       MT=  5  Sum of Binary (n,n') and (n,x) Reactions           2625 1451  288
                                                                  2625 1451  289
  MF=4 MT=  2  Elastic Angular Distributions                      2625 1451  290
                                                                  2625 1451  291
  MF=6 MT=  5  Production Cross Sections and Energy-Angle         2625 1451  292
               Distributions for Emission Neutrons, Protons,      2625 1451  293
               Deuterons, and Alphas; and Angle-Integrated        2625 1451  294
               Spectra for Gamma Rays and Residual Nuclei That    2625 1451  295
               Are Stable Against Particle Emission               2625 1451  296
                                                                  2625 1451  297
  The evaluation is based on nuclear model calculations that      2625 1451  298
have been benchmarked to experimental data, especially for n +    2625 1451  299
Fe56 and p + Fe56 reactions [Ch96a]. We use the GNASH code        2625 1451  300
system [Yo92], which utilizes Hauser-Feshbach statistical,        2625 1451  301
preequilibrium and direct-reaction theories. Spherical optical    2625 1451  302
model calculations are used to obtain particle transmission       2625 1451  303
coefficients for the Hauser-Feshbach calculations, as well as     2625 1451  304
for the elastic neutron angular distributions.                    2625 1451  305
  Cross sections and spectra for producing individual residual    2625 1451  306
nuclei are included for reactions that exceed a cross section of  2625 1451  307
approximately 1 nb at any energy. The energy-angle-correlations   2625 1451  308
for all outgoing particles are based on Kalbach systematics       2625 1451  309
[Ka88].                                                           2625 1451  310
  A model was developed to calculate the energy distributions of  2625 1451  311
all recoil nuclei in the GNASH calculations [Ch96b]. The recoil   2625 1451  312
energy distributions are represented in the laboratory system in  2625 1451  313
MT=5, MF=6, and are given as isotropic in the lab system. Note    2625 1451  314
that all other data in MT=5,MF=6 are given in the center-of-mass  2625 1451  315
system. This method of representation requires a modification of  2625 1451  316
the original ENDF-6 format.                                       2625 1451  317
  Preequilibrium corrections were performed in the course of the  2625 1451  318
GNASH calculations using the exciton model of Kalbach [Ka77,      2625 1451  319
Ka85], validated by comparison with calculations using Feshbach,  2625 1451  320
Kerman, Koonin (FKK) theory [Ch93].  Discrete level data from     2625 1451  321
nuclear data sheets were matched to continuum level densities     2625 1451  322
using the formulation of Ignatyuk [Ig75] and pairing and shell    2625 1451  323
parameters from the Cook [Co67] analysis. Neutron and charged-    2625 1451  324
particle transmission coefficients were obtained from the         2625 1451  325
optical potentials, as discussed below.  Gamma-ray transmission   2625 1451  326
coefficients were calculated using the Kopecky-Uhl model [Ko90].  2625 1451  327
  The neutron optical model potential of Arthur et al. [Ar80]     2625 1451  328
was used to calculate transmission coefficients and cross         2625 1451  329
sections with the SCAT2 code [Be92] up to a neutron energy of 26  2625 1451  330
MeV.  Between 26 and 52 MeV, the imaginary volume component of    2625 1451  331
Arthur's potential was modified to better account for nonelastic  2625 1451  332
cross section measurements, and above 52 MeV the Semmering        2625 1451  333
potential of Madland [Ma88] was used.  For protons, the           2625 1451  334
Beccetti-Greenlees potential [Be69] was utilized below 28 MeV,    2625 1451  335
and the Madland potential [Ma88] was used at higher energies.     2625 1451  336
The global spherical potential of Perey [Pe63] was utilized for   2625 1451  337
deuterons, and the potential of Beccetti-Greenlees [Be71]         2625 1451  338
was adopted for tritons.  Finally, the alpha potential of Lemos   2625 1451  339
[Le72], as adapted by Arthur et al. [Ar80], was used for alpha    2625 1451  340
particles.                                                        2625 1451  341
  Direct reaction cross sections to discrete states were          2625 1451  342
calculated with the ECIS95 code [Re95] using deformation          2625 1451  343
parameters compiled in Nuclear Data Sheets.                       2625 1451  344
  We used the same values for the total, elastic, and nonelastic  2625 1451  345
cross sections (MF=3, MT=1,2,3) above 20 MeV as were used in the  2625 1451  346
n + 56Fe evaluation.                                              2625 1451  347
                                                                  2625 1451  348
***************************************************************** 2625 1451  349
                                                                  2625 1451  350
REFERENCES                                                        2625 1451  351
                                                                  2625 1451  352
[Ar80]  E.D. Arthur and P.G. Young, 'Evaluation of Neutron        2625 1451  353
   Cross Sections to 40 MeV for 54,56Fe," Proc. Sym. on Neutron   2625 1451  354
   Cross Sections from 10 to 50 MeV, 12-14 May 1980, Brookhaven   2625 1451  355
   National Laboratory [Eds. M. R. Bhat and S. Pearlstein, BNL-   2625 1451  356
   NCS-51245, 1980] p. 731.                                       2625 1451  357
[Be69]  F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182    2625 1451  358
   1190 (1969)                                                    2625 1451  359
[Be71]  F.D. Becchetti, Jr., and G.W. Greenlees, "Polarization    2625 1451  360
   Phenomena in Nuclear Reactions," (Ed: H.H. Barschall and       2625 1451  361
   W. Haeberli, The University of Wisconsin Press, 1971) p.682    2625 1451  362
[Be92]  O. Bersillon, "SCAT2 - A Spherical Optical Model Code,"   2625 1451  363
   in Proc. ICTP Workshop on Computation and Analysis of Nuclear  2625 1451  364
   Data Relevant to Nuclear Energy and Safety, 10 February-13     2625 1451  365
  March, 1992, Trieste, Italy, to be published in World Scientific2625 1451  366
   Press, and Progress Report of the Nuclear Physics Division,    2625 1451  367
   Bruyeres-le-Chatel 1977, CEA-N-2037, p.111 (1978).             2625 1451  368
[Ch93]  M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2625 1451  369
[Ch96a] M.B. Chadwick and P.G. Young, "GNASH Calculations of      2625 1451  370
   n,p + 54,56,57,58Fe and Benchmarking of Results" in APT        2625 1451  371
   progress report: 1 August - 1 September 1996, internal Los     2625 1451  372
   Alamos National Laboratory memo T-2-96/MS-52, 6 Aug. 1996 from 2625 1451  373
   R.E. MacFarlane to L. Waters.                                  2625 1451  374
[Ch96b] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J.      2625 1451  375
   Koning, "High-Energy Nuclear Data Libraries for Accelerator-   2625 1451  376
   Driven Technologies:  Calculational Method for Heavy Recoils," 2625 1451  377
   Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation    2625 1451  378
   Technology and Applications, Kalmar, Sweden, 3-7 June 1996     2625 1451  379
[Ch99]  M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2625 1451  380
   National Laboratory report, LA-UR-99-1222 (1999)               2625 1451  381
[Co67]  J.L. Cook, H. Ferguson, and A.R. deL Musgrove, Aust.J.    2625 1451  382
   Phys. 20, 477 (1967)                                           2625 1451  383
[Fr01]  S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos      2625 1451  384
   National Laboratory Report, LA-13812 (2001).                   2625 1451  385
[Fu86]  C.Y. Fu and D.M. Hetrick, report ORNL/TM-9964 [ENDF-341]  2625 1451  386
   (1986)                                                         2625 1451  387
[He91]  D.M. Hetrick, C.Y. Fu, and N.M. Larson, ENDF/B-VI.1       2625 1451  388
   Evaluation of n + 54Fe, personal comm. (1991)                  2625 1451  389
[Ig75]  A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J.    2625 1451  390
   Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485     2625 1451  391
   (1975)                                                         2625 1451  392
[Ka77]  C. Kalbach, Z.Phys.A  283, 401 (1977)                     2625 1451  393
[Ka85]  C. Kalbach, Los Alamos report LA-10248-MS (1985)          2625 1451  394
[Ka88]  C. Kalbach, Phys.Rev. C 37, 2350 (1988); see also         2625 1451  395
   C. Kalbach and F.M. Mann, Phys.Rev. C 23, 112 (1981)           2625 1451  396
[Ko90]  J. Kopecky and M. Uhl, Phys.Rev. C 41, 1941 (1990)        2625 1451  397
[Le72]  O.F. Lemos, "Diffusion Elastique de Particules Alpha      2625 1451  398
   de 21 a 29.6 MeV sur des Noyaux de la Region Ti-Zn," Orsay     2625 1451  399
   report, Series A, No. 136 (1976).                              2625 1451  400
[Ma88]  D.G. Madland, Proc. OECD/NEANDC Specialist's Meeting on   2625 1451  401
   Preequilibrium Nuclear Reactions, Semmering, Austria, Feb.     2625 1451  402
   1988, NEANDC-245 (1988) p.103                                  2625 1451  403
[Pe63]  C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963)      2625 1451  404
[Re95]  J. Raynal, "Notes on ECIS94," CEA informal                2625 1451  405
   report,Saclay (1995).                                          2625 1451  406
[Yo92]  P.G. Young, E.D. Arthur, and M.B. Chadwick, Los Alamos    2625 1451  407
   National Laboratory report LA-12343-MS (1992)                  2625 1451  408
                                                                  2625 1451  409
 **************************************************************** 2625 1451  410
                                                                  2625 1451  411
 ENDF/B-VI MOD 3 Revision, October 1997, V. McLane (NNDC).        2625 1451  412
                                                                  2625 1451  413
 1. Corrected residual nucleus in File 6, MT=16,103.              2625 1451  414
 2. Updated File 1 comments and corrected references.             2625 1451  415
                                                                  2625 1451  416
 **************************************************************** 2625 1451  417
                                                                  2625 1451  418
 ENDF/B-VI MOD 2 Revision, July 1991, (ORNL)                      2625 1451  419
                                                                  2625 1451  420
 The elastic transformation matrix was removed.                   2625 1451  421
                                                                  2625 1451  422
 **************************************************************** 2625 1451  423
                                                                  2625 1451  424
 ENDF/B-VI MOD 1 Evaluation, November 1989, D.M. Hetrick, C.Y. Fu,2625 1451  425
                 and N.M. Larson (ORNL)                           2625 1451  426
                                                                  2625 1451  427
    This work employed nuclear model codes including the          2625 1451  428
 Distorted Wave Born Approximation (DWBA) program DWUCK [1]       2625 1451  429
 and the Hauser-Feshbach code TNG [2,3,4].  The TNG code provides 2625 1451  430
 energy and angular distributions of particles emitted in the     2625 1451  431
 compound and pre-compound reactions, ensures consistency among   2625 1451  432
 all reactions, and maintains energy balance. details pertinent   2625 1451  433
 to the contents of this evaluation will be published at a later  2625 1451  434
 date.                                                            2625 1451  435
    Resonance  parameters and thermal cross sections are from     2625 1451  436
 Mughabghab [5] and adjusted through SAMMY by N. Larson using J.A.2625 1451  437
 Harvey data [11] between 110 and 700 keV, capture cross section  2625 1451  438
 background in File 3 was based on Allen [6].   Above 700 keV,    2625 1451  439
 54Fe data from J.A. Harvey [11] used.                            2625 1451  440
                                                                  2625 1451  441
 DESCRIPTION OF FILES                                             2625 1451  442
                                                                  2625 1451  443
 File 1  GENERAL INFORMATION ------------------------------------ 2625 1451  444
   MT=451 General information, references, and definitions.       2625 1451  445
                                                                  2625 1451  446
                                                                  2625 1451  447
 File 3  NEUTRON CROSS SECTIONS --------------------------------- 2625 1451  448
   MT=103 (n,p) cross sections                                    2625 1451  449
      Taken from the GLUCS [8] calculation in which this reaction 2625 1451  450
        was studied simultaneously with 12 other dosimetry        2625 1451  451
        reaction cross sections [9].                              2625 1451  452
                                                                  2625 1451  453
 File 33  UNCERTAINTY FILES ------------------------------------- 2625 1451  454
        An LB=8 section is included for all non-derived files as  2625 1451  455
        required by ENDF/B-VI.                                    2625 1451  456
   MT=103  (n,p) covariances were taken from the GLUCS [8]        2625 1451  457
          calculation in which this reaction was studied          2625 1451  458
          simultaneously with 12 other dosimetry reaction cross   2625 1451  459
          sections [9].                                           2625 1451  460
 ---------------------------------------------------------------- 2625 1451  461
 REFERENCES:                                                      2625 1451  462
                                                                  2625 1451  463
 [1] P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of Colorado, 2625 1451  464
     unpublished (1972).                                          2625 1451  465
 [2] C.Y. Fu, "A Consistent Nuclear Model For Compound and Pre-   2625 1451  466
     compound Reactions with Conservation of Angular Momentum,"   2625 1451  467
     report ORNL/TM-7042 (1980), and Nucl.Sci.Eng. 100, 61 (1988).2625 1451  468
 [3] C.Y Fu, "Development and Application of Multi-step           2625 1451  469
     Hauser-Feshbach/Pre-equilibrium Model Theory," Symp.         2625 1451  470
     Neutron Cross Sections from 10 to 50 MeV, Upton, N.Y.,       2625 1451  471
     May 12-14,1980, report BNL-NCS-51425, p.675.                 2625 1451  472
 [4] K. Shibata and C.Y. Fu, "Recent Improvements of the TNG      2625 1451  473
     Statistical Model Code", report ORNL/TM-10093 (1986).        2625 1451  474
 [5] S.F. Mughabghab, Neutron Cross Sections, Vol. 1: Resonance   2625 1451  475
     Parameters and Thermal Cross Sections, Part A (Academic      2625 1451  476
     Press, 1981).                                                2625 1451  477
 [6] B.J. Allen, Geel Conference, 1977.                           2625 1451  478
 [7] P.T. Guenther, D.L. Smith, A.B. Smith et al., Ann.Nucl. En.  2625 1451  479
     13 (11), 601-610 (1986).                                     2625 1451  480
 [8] D.M. Hetrick and C.Y. Fu, "GLUCS: A Generalized Least Squares2625 1451  481
     Program for Updating Cross Section Evaluations with          2625 1451  482
     Correlated Data Sets," report ORNL/TM-7341 [ENDF-303] (1980).2625 1451  483
 [9] C.Y. Fu and D.M. Hetrick, "Experience in Using the           2625 1451  484
     Covariances of Some ENDF/B-V Dosimetry Cross Sections:       2625 1451  485
     Proposed Improvements and Additions of Cross-reaction        2625 1451  486
     Covariances," Proc. Fourth ASTM-Euratom Symp. on Reactor     2625 1451  487
     Dosimetry, Gaithersburg, Maryland, March 22-26,1982,         2625 1451  488
     (US National Bureau Of Standards, 1982) p.877.               2625 1451  489
([0] S.M. Grimes, R.C. Haight, K.R. Alvar et al., Phys.Rev., C19, 2625 1451  490
     2127 (1979).                                                 2625 1451  491
[11] J.A. Harvey, private communication, 1989.                    2625 1451  492
                                                                  2625 1451  493
******************************************************************2625 1451  494
*********     End of (N,P) bibliographical component    ********* 2625 1451  495
***************************************************************** 2625 1451  496
 The Q values and threshold energies were updated prior to pro-   2625 1451  497
 cessing through the codes to comply with the values obtained     2625 1451  498
 using the NNDC calculation program which is based on the 1995    2625 1451  499
 Update to the Atomic mass Evaluation.                            2625 1451  500
                                                                  2625 1451  501
 File 2 added to the pointwise file containing only the effective 2625 1451  502
 scattering radius with no resonance parameters given.            2625 1451  503
 Taken from ENDF/B-VI                                             2625 1451  504
 ************************ C O N T E N T S *********************** 2625 1451  505
                                                                  2625 1451  506
 ***************** Program LINEAR (VERSION 2002-1) ***************2625 1451  507
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2625 1451  508
 Data Linearized to Within an Accuracy of .100000000 per-cent     2625 1451  509
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2625 1451  510
 Data Doppler Broadened to 300.000000 Kelvin                      2625 1451  511
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2625 1451  512
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2625 1451  513
 ***************** Program FIXUP (Version 2002-1) ****************2625 1451  514
 Corrected ZA/AWR in All Sections-----------------------------Yes 2625 1451  515
 Corrected Thresholds-----------------------------------------Yes 2625 1451  516
 Extended Cross Sections to 20 MeV----------------------------No  2625 1451  517
 Allow Cross Section Deletion---------------------------------No  2625 1451  518
 Allow Cross Section Reconstruction---------------------------No  2625 1451  519
 Make All Cross Sections Non-Negative-------------------------Yes 2625 1451  520
 Delete Energies Not in Ascending Order-----------------------Yes 2625 1451  521
 Deleted Duplicate Points-------------------------------------Yes 2625 1451  522
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2625 1451  523
 Check for Legal MF/MT Numbers--------------------------------Yes 2625 1451  524
 Allow Creation of Missing Sections---------------------------No  2625 1451  525
 Allow Insertion of Energy Points-----------------------------No  2625 1451  526
 Create Uniform Energy Grid-----------------------------------No  2625 1451  527
 Delete Section if Cross Section =0 at All Energies-----------Yes 2625 1451  528
 ***************** Program GROUPIE (VERSION 2002-1) **************2625 1451  529
 Unshielded Group Averages Using  640 Groups                      2625 1451  530
 Weighting Spectrum: Flat (Constant) Spectrum                     2625 1451  531
                                1        451        539          12625 1451  532
                                2        151          4          12625 1451  533
                                3         16         25          12625 1451  534
                                3        103         70          12625 1451  535
                                3        107         62          12625 1451  536
                               33         16         21          12625 1451  537
                               33        103         57          12625 1451  538
                               33        107         35          12625 1451  539
                                                                  2625 1  099999
                                                                  2625 0  0    0
 2.60540E+4 5.34760E+1          0          0          1          02625 2151    1
 2.605400+4 1.000000+0          0          0          1          02625 2151    2
 1.000000-5 7.000000+5          0          0          0          02625 2151    3
 0.000000+0 5.480000-1          0          0          0          02625 2151    4
                                                                  2625 2  099999
                                                                  2625 0  0    0
 2.60540E+4 5.34762E+1          0          0          0          02625 3 16    1
-1.33785E+7-1.33785E+7          0          0          1         652625 3 16    2
         65          1                                            2625 3 16    3
 13600000.0 .000103649 13700000.0 .000301866 13800000.0 .0005359992625 3 16    4
 13900000.0 .000884865 14000000.0 .001354120 14100000.0 .0019488152625 3 16    5
 14200000.0 .002673245 14300000.0 .003530825 14400000.0 .0045239552625 3 16    6
 14500000.0 .005653915 14600000.0 .006920745 14700000.0 .0083231552625 3 16    7
 14800000.0 .009858505 14900000.0 .011522700 15000000.0 .0133103002625 3 16    8
 15100000.0 .015214450 15200000.0 .017227050 15300000.0 .0193389002625 3 16    9
 15400000.0 .021539650 15500000.0 .023818050 15600000.0 .0261741002625 3 16   10
 15700000.0 .028571900 15800000.0 .031006167 15900000.0 .0334769002625 3 16   11
 16000000.0 .035947633 16100000.0 .038418367 16200000.0 .0408891002625 3 16   12
 16300000.0 .043359833 16400000.0 .045778600 16500000.0 .0481454002625 3 16   13
 16600000.0 .050512200 16700000.0 .052809775 16800000.0 .0550381252625 3 16   14
 16900000.0 .057197825 17000000.0 .059288875 17100000.0 .0613041002625 3 16   15
 17200000.0 .063243500 17300000.0 .065103375 17400000.0 .0668837252625 3 16   16
 17500000.0 .068583625 17600000.0 .070203075 17700000.0 .0717433752625 3 16   17
 17800000.0 .073204525 17900000.0 .074571333 18000000.0 .0758438002625 3 16   18
 18100000.0 .077116267 18200000.0 .078284383 18300000.0 .0793481502625 3 16   19
 18400000.0 .080411917 18500000.0 .081382933 18600000.0 .0822612002625 3 16   20
 18700000.0 .083139467 18800000.0 .083937067 18900000.0 .0846540002625 3 16   21
 19000000.0 .085370933 19100000.0 .086008663 19200000.0 .0865671882625 3 16   22
 19300000.0 .087125713 19400000.0 .087684238 19500000.0 .0881690752625 3 16   23
 19600000.0 .088580225 19700000.0 .088991375 19800000.0 .0894025252625 3 16   24
 19900000.0 .089749640 20000000.0 0.0                             2625 3 16   25
                                                                  2625 3  099999
 2.60540E+4 5.34762E+1          0          0          0          02625 3103    1
 8.53000E+4 8.53000E+4          0          0          1        1992625 3103    2
        199          1                                            2625 3103    3
 690000.000 3.86480E-7 720000.000 2.31888E-6 760000.000 4.63776E-62625 3103    4
 800000.000 2.08835E-5 840000.000 5.10560E-5 880000.000 8.12286E-52625 3103    5
 920000.000 .000111401 960000.000 .000141574 1000000.00 .0003158642625 3103    6
 1100000.00 .000634272 1200000.00 .001003305 1300000.00 .0016760882625 3103    7
 1400000.00 .002399496 1500000.00 .003358460 1600000.00 .0045529802625 3103    8
 1700000.00 .006521960 1800000.00 .013137700 1900000.00 .0205279002625 3103    9
 2000000.00 .027669000 2100000.00 .034561000 2200000.00 .0417467502625 3103   10
 2300000.00 .050695000 2400000.00 .059937000 2500000.00 .0719424002625 3103   11
 2600000.00 .086711200 2700000.00 .103066400 2800000.00 .1289400002625 3103   12
 2900000.00 .156400000 3000000.00 .175595909 3100000.00 .1865277272625 3103   13
 3200000.00 .188037864 3300000.00 .194305500 3400000.00 .1967550002625 3103   14
 3500000.00 .207098000 3600000.00 .226334000 3700000.00 .2456455002625 3103   15
 3800000.00 .265410000 3900000.00 .285250000 4000000.00 .2962360002625 3103   16
 4100000.00 .298368000 4200000.00 .301528500 4300000.00 .3108600002625 3103   17
 4400000.00 .321220000 4500000.00 .334012000 4600000.00 .3492360002625 3103   18
 4700000.00 .364460000 4800000.00 .379684000 4900000.00 .3949080002625 3103   19
 5000000.00 .405579000 5100000.00 .411697000 5200000.00 .4178150002625 3103   20
 5300000.00 .423933000 5400000.00 .430051000 5500000.00 .4371370002625 3103   21
 5600000.00 .445191000 5700000.00 .453245000 5800000.00 .4612990002625 3103   22
 5900000.00 .469353000 6000000.00 .473782000 6100000.00 .4745860002625 3103   23
 6200000.00 .475390000 6300000.00 .476194000 6400000.00 .4769980002625 3103   24
 6500000.00 .477802000 6600000.00 .478606000 6700000.00 .4794100002625 3103   25
 6800000.00 .480214000 6900000.00 .481018000 7000000.00 .4814590002625 3103   26
 7100000.00 .481537000 7200000.00 .481615000 7300000.00 .4816930002625 3103   27
 7400000.00 .481771000 7500000.00 .481849000 7600000.00 .4819270002625 3103   28
 7700000.00 .482005000 7800000.00 .482083000 7900000.00 .4821610002625 3103   29
 8000000.00 .482303000 8100000.00 .482509000 8200000.00 .4827150002625 3103   30
 8300000.00 .482921000 8400000.00 .483127000 8500000.00 .4833330002625 3103   31
 8600000.00 .483539000 8700000.00 .483745000 8800000.00 .4839510002625 3103   32
 8900000.00 .484157000 9000000.00 .483918000 9100000.00 .4832340002625 3103   33
 9200000.00 .482550000 9300000.00 .481866000 9400000.00 .4811820002625 3103   34
 9500000.00 .480498000 9600000.00 .479814000 9700000.00 .4791300002625 3103   35
 9800000.00 .478446000 9900000.00 .477762000 10000000.0 .4770780002625 3103   36
 10100000.0 .476394000 10200000.0 .475710000 10300000.0 .4750260002625 3103   37
 10400000.0 .474342000 10500000.0 .473600000 10600000.0 .4728000002625 3103   38
 10700000.0 .472000000 10800000.0 .471200000 10900000.0 .4704000002625 3103   39
 11000000.0 .469500000 11100000.0 .468500000 11200000.0 .4675000002625 3103   40
 11300000.0 .466500000 11400000.0 .465500000 11500000.0 .4636200002625 3103   41
 11600000.0 .460860000 11700000.0 .458100000 11800000.0 .4553400002625 3103   42
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                                                                     0 0  0    0
 2.60560E+4 5.54544E+1          0          0         34         102631 1451    1
 0.0        0.0                 0          0          0          62631 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022631 1451    3
 3.00000E+2 0.0                 1          0        261          42631 1451    4
 26-Fe- 56 FEI        EVAL-Oct02 K.I.Zolotarev                    2631 1451    5
                      DIST-Feb2004                                2631 1451    6
----IRDF-2002         MATERIAL 2631                               2631 1451    7
-----INCIDENT NEUTRON DATA                                        2631 1451    8
------ENDF-6 FORMAT                                               2631 1451    9
***************************************************************** 2631 1451   10
 26-FE- 56 FEI        EVAL-Oct02 K.I.Zolotarev                    2631 1451   11
                      DIST-Nov03                       20031105   2631 1451   12
----BROND-3           MATERIAL 2631         Revision 2            2631 1451   13
-----INCIDENT NEUTRON DATA                                        2631 1451   14
------ENDF-6 FORMAT                                               2631 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    2631 1451   16
***************************************************************** 2631 1451   17
Author  of evaluation: K.I.Zolotarev                              2631 1451   18
***************************************************************** 2631 1451   19
MF=3                                                              2631 1451   20
MT=103 -(n,p) cross section                                       2631 1451   21
-------------------------------------                             2631 1451   22
    Excitation function for the  Fe-56(n,p)Mn-56  reaction in the 2631 1451   23
energy region from threshold to 20 MeV  was evaluated by means of 2631 1451   24
statistical analysis of experimental cross section data [1-40].   2631 1451   25
    The energy dependence of cross-section  from  4.0 MeV  to the 2631 1451   26
threshold was extrapolated with  L=0  penetrability function  for 2631 1451   27
the outgoing  p + Mn-56 channel [41].                             2631 1451   28
    Analised  microscopic experimental data [1-40], [42-69]  were 2631 1451   29
renormalized if it were possible to the new recommended standards 2631 1451   30
for monitor reaction cross sections and decay data.               2631 1451   31
    Special correction was done with experimental data [2],[9-10] 2631 1451   32
and [17]. Experimental data of Terrell and Holm [2] corresponding 2631 1451   33
to neutron energies 6.54 MeV,7.41 MeV, 8.21 MeV were renormalized 2631 1451   34
to the preliminary evaluated  cross section value at  En=8.2 MeV. 2631 1451   35
Data of  Liskien and Paulsen [9]  measured  in  the energy range  2631 1451   36
12.60 - 19.58 MeV  were corrected  to  the preliminary  evaluated 2631 1451   37
integral of cross section in the energy interval 14-15 MeV.  Data 2631 1451   38
obtained by Liskien and Paulsen in the energy range 6.06-8.20 MeV 2631 1451   39
[10] were renormalized to the preliminary evaluated cross section 2631 1451   40
value at 8.0 MeV.  The correction factors  for  the  experimental 2631 1451   41
data [2], [9] and [10] were Fc=1.23487, Fc=1.09674 and Fc=1.05835,2631 1451   42
respectively. Data of Smith and Meadows [17] obtained in the expe-2631 1451   43
riment with neutrons from  D(d,n)He3 reaction in the energy range 2631 1451   44
6.486 - 9.945 MeV were renormalized  to the preliminary evaluated 2631 1451   45
cross section value at 9.945 MeV.  The correction factor for this 2631 1451   46
data was Fc=1.14066 .                                             2631 1451   47
    Experimental information about Fe-56(n,p)Mn-56 reaction exci- 2631 1451   48
tation function are given in the ref. [13],[21],[23] in the form  2631 1451   49
of cross section ratios to monitor reactions. The results of pre- 2631 1451   50
cise relative measurements  of Vonach et al. [13]  in  the energy 2631 1451   51
range 13.6-14.7 MeV were normalized  to the preliminary evaluated 2631 1451   52
absolute cross section value 107.13 mb  for Fe-56(n,p)Mn-56 reac- 2631 1451   53
tion at 14.7 MeV point. Raics et al. [21]  and  Antov et al. [23] 2631 1451   54
measured ratios of  Fe-56(n,p)Mn-56 cross section  to  U-238(n,f) 2631 1451   55
and Al-27(n,a)Na-24 reactions cross section. Recommended absolute 2631 1451   56
cross section data for U-238(n,f)  and  Al-27(n,a)Na-24 reactions 2631 1451   57
were taken from ref. [70] and [71], respectively.                 2631 1451   58
    Experimental data from refs.[5] and [11] were used partially. 2631 1451   59
It were used only data obtained at 14.5 MeV [5] and in the energy 2631 1451   60
range 3.95 - 10.0 MeV [11]. Cross et al. data [5] for the neutron 2631 1451   61
energies  13.78 MeV, 14.07 MeV and 14.73 MeV  were  rejected  due 2631 1451   62
to their  systematically  underestimation  Fe-56(n,p)Mn-56  cross 2631 1451   63
section.  The result of Grundl measurements at 14.1 MeV [11]  was 2631 1451   64
not taken into account due to a very  overestimated cross section 2631 1451   65
value obtained for this energy point.                             2631 1451   66
    Experimental cross section data [42-69] were rejected  due to 2631 1451   67
their discrepancy with the main bulk of experimental data [1-40]. 2631 1451   68
In  the  rejected  experiments  [42-51], [53], [56-58], [60-62],  2631 1451   69
[64-67] and [69] the cross section values were measured only in a 2631 1451   70
one energy point in the interval 14 - 15 MeV.                     2631 1451   71
    Statistical analysis of input cross section data was carried  2631 1451   72
out by means of PADE-2 code [72].  Rational function was used as  2631 1451   73
the model function [73].                                          2631 1451   74
    U-235 thermal fission [74]  and  Cf-252 spontaneous  fission  2631 1451   75
neutron spectra [75] averaged cross-sections calculated from the  2631 1451   76
evaluated Fe-56(n,p)Mn-56 excitation function are the following:  2631 1451   77
                                                                  2631 1451   78
  2631 1451   79
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  2631 1451   80
  2631 1451   81
 U-235 neutron fission     1.0997         1.09  +- 0.04   [76]  2631 1451   82
                                          1.13  +- 0.07   [77]  2631 1451   83
                                          1.083 +- 0.017  [78]  2631 1451   84
  2631 1451   85
 Cf-252 spont. fission     1.4626         1.471 +- 0.025  [79]  2631 1451   86
                                          1.465 +- 0.026  [80]  2631 1451   87
  2631 1451   88
                                                                  2631 1451   89
MT=33                                                             2631 1451   90
MT=103 -(n,p) cross section cov. matrix                           2631 1451   91
---------------------------------------                           2631 1451   92
    Uncertainties in the evaluated  excitation function  for  the 2631 1451   93
reaction Fe-56(n,p)Mn-56 are given in the form of relative covari-2631 1451   94
ance matrix for the  25-neutron energy groups (LB=5).  Covariance 2631 1451   95
matrix  of  uncertainties  was  calculated  simultaneously  with  2631 1451   96
recommended cross section data by means of PADE-2 code.           2631 1451   97
    Eigenvalues  of the  6-th digits  relative covariance matrix  2631 1451   98
given in the 33-file are the following:                           2631 1451   99
                                                                  2631 1451  100
    4.35195E-09    4.49367E-09    4.76919E-09    5.19445E-09      2631 1451  101
    5.64595E-09    6.15408E-09    7.11594E-09    7.89561E-09      2631 1451  102
    9.40785E-09    1.19394E-08    1.48739E-08    1.86574E-08      2631 1451  103
    2.18905E-08    1.32640E-06    2.77587E-04    3.86559E-04      2631 1451  104
    6.52483E-04    1.02062E-03    1.26078E-03    1.33119E-03      2631 1451  105
    1.81407E-03    2.05264E-03    3.00443E-03    4.57086E-03      2631 1451  106
    8.12954E-03                                                   2631 1451  107
                                                                  2631 1451  108
 References :                                                     2631 1451  109
 1. G.Brown  Philosophical Magazine, v.2, p.785, 1957             2631 1451  110
 2. J.Terrell, D.M.Holm  Phys. Rev., v.109, p.2031, 1958          2631 1451  111
 3. H.Pollehn, H.Neuert  Zeitschrift f. Naturforschung, sect. A,  2631 1451  112
    v.16, p.227, 1961                                             2631 1451  113
 4. F.Gabbard, B.D.Kern  Phys. Rev., v.128, p.1276, 1962          2631 1451  114
 5. W.G.Cross et al.  Prog. Report EANDC(CAN)-16, p.1, Jan. 1963  2631 1451  115
 6. D.C.Santry, J.P.Batler  Can. J. Phys., v.42, p.1030, 1964     2631 1451  116
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    Sections and Technology, Washington D.C., 4-7 March 1968,     2631 1451  125
    v.2, p.885                                                    2631 1451  126
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20. Ju.A.Nemilov, Ju.N.Trofimov  Progress Report YFI-26, p.25,    2631 1451  134
    November 1978                                                 2631 1451  135
21. P.Raics et al.  Proc. of the 5th All Union Conference on      2631 1451  136
    Neutron Physics, Kiev, 15-19 September 1980, v.1, p.236       2631 1451  137
22. K.Kudo  Progress Report NEANDC(J)-83/U, p.1, September 1982   2631 1451  138
23. A.Antov et al. Bulgarian J. of Physics, v.10(6), p.601, 1983  2631 1451  139
24. K.Kudo  The IAEA Advisory Group Meeting on Nuclear Standards  2631 1451  140
    Reference Data, Geel, Belgium, 1984                           2631 1451  141
25. B.M.Bahal, R.Pepelnik  Report GKSS-84-E-, 1984                2631 1451  142
26. I.Garlea et al. Proc. of the 14-th International Symposium on 2631 1451  143
    Nuclear Physics, Gaussig, GDR, 19-23 November 1984, ZFK-562,  2631 1451  144
    p.126, July 1985                                              2631 1451  145
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28. Y.Ikeda et al.  Report JAERI-1312, March 1988                 2631 1451  147
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32. S.K.Saraf et al.  Nucl. Sci. Eng., v.107, p.365, April 1991   2631 1451  153
33. P.Fuga  Nucl. Instr. and Meth., vA309, no.3, p.500, Nov. 1991 2631 1451  154
34. Y.Ikeda et al. Progress Report INDC(JPN)-162/U,p.24, Aug.1992 2631 1451  155
35. W.Mannhart, G.Boerker  Progress Report, INDC(Ger)-036/L, p.59 2631 1451  156
    July 1992                                                     2631 1451  157
36. Bao Zongyu et al. China J. Nucl. Phys., v.15,no.4,p.341, 1993 2631 1451  158
37. Y.Ikeda et al.  Journal of Nuclear Science and Technology,    2631 1451  159
    v.30, n.9, pp.870-880, September 1993                         2631 1451  160
38. Lu Hanlin et al.  Report INDC(CPR)-045, IAEA, October 1998    2631 1451  161
39. A.A.Filatenkov et al.  Report, RI-252, May 1999 ;             2631 1451  162
    A.A.Filatenkov et al.  VANT, Ser.: Yadernye Konstanty, v.2,   2631 1451  163
    p.8, Moscow, 1996                                             2631 1451  164
40. A.Fessler Report JUL-3502, FZ Julich GmbH, Germany, 1998 ;    2631 1451  165
    A.Fessler et al.  Nucl. Sci. Eng., v.134, no.2, p.171, 2000   2631 1451  166
41. S.A.Badikov, A.B.Pashchenko Voprosy Atomnoy Nauki i Tekhniki  2631 1451  167
    Ser. Jadernye Konstanty, 2(53), p.70, 1987                    2631 1451  168
42. S.G.Forbes  Phys. Rev., v.88, p.1309, December 1952           2631 1451  169
43. E.B.Paul, R.L.Clarke  Canadian J. Phys., v.31, p.267, 1953    2631 1451  170
44. G.W.Mc Clure, D.W.Kent J. Franklin Inst., v.260, p.238, 1955  2631 1451  171
45. D.L.Allan  Proc. Physical Society, section A, v.70, p.195,    2631 1451  172
    March 1957                                                    2631 1451  173
46. S.Yasumi  J. Phys. Soc. Japan, v.12, p.443, May 1957          2631 1451  174
47. P.V.March,W.T.Morton Philosophical Magazine, v.3, p.143, 1958 2631 1451  175
48. B.D.Kern et al.  Nucl. Phys., v.10, p.226, May 1959           2631 1451  176
49. M.J.Depraz et al. Journal Phys. Radium, v.21, p.377, May 1960 2631 1451  177
50. R.S.Storey et al.  Proc. Phys. Soc., v.75, p.526, 1960        2631 1451  178
51. D.M.Chittenden et al.  Phys. Rev., v.122, p.860, May 1961     2631 1451  179
52. M.Bormann et al. Zeitschrift fuer Physik, v.166, p.477, 1962  2631 1451  180
53. J.E.Strain, W.J.Ross  Report ORNL-3672, January 1965          2631 1451  181
54. J.D.Hemingway et al.  Proc. Royal Society, section A, v.292,  2631 1451  182
    p.180, May 1966                                               2631 1451  183
55. P.Cuzzocrea et al. Nuovo Cimento B, v.54, p.53, March 1968    2631 1451  184
56. S.M.Qaim et al. Proc. of Conference on Chemical Nuclear Data, 2631 1451  185
    Measurements and Applicat., Univ. of Kent, Canterbury, 20-22  2631 1451  186
    September 1971, p.121                                         2631 1451  187
57. J.J.Singh  Trans. Amer. Nucl. Soc., v.15, p.147, June 1972    2631 1451  188
58. R.Spangler et al. Ann. Nucl. Sci., v.22, p.818, November 1975 2631 1451  189
59. A.B.M.G.Mostafa  Nuclear Science and Applications, Series B:  2631 1451  190
    Physical sciences, v.9, p.10, October  1976                   2631 1451  191
60. Z.A.Ramendik et al.  Atomnaja Energija (Sov.), v.42, no.2,    2631 1451  192
    p.136, February 1977                                          2631 1451  193
61. S.Sothras  Dissertation Abstracts, v.B38, p.280, July 1978    2631 1451  194
62. D.Sharma et al. Proc. of the 21-st Nuclear Physics and Solid  2631 1451  195
    State Physics Symposium, Bombay, India, 28-31 December 1978 , 2631 1451  196
    v.2, p.349                                                    2631 1451  197
63. P.N.Ngoc et al. Progress Report INDC(HUN)-20,p.3, March 1983; 2631 1451  198
    P.N.Ngoc et al.  Nucleonika (Pol), v.29, p.87, 1984           2631 1451  199
64. P.N.Ngoc et al.  Report INDC(VN)-2, November 1983             2631 1451  200
65. I.Garlea et al. Rev. Roum. Phys., v.29, p.421, 1984           2631 1451  201
66. J.P.Gupta et al.  Pramana, v.24, p.637, 1985                  2631 1451  202
67. M.Viennot et al.  Nucl. Sci. Eng., v.108, p.289, July 1991    2631 1451  203
68. A.Ercan et al.  Proc. of an Int. Conference on Nuclear Data   2631 1451  204
    for Science and Technology, Juelich, FRG, 13-17 May 1991,     2631 1451  205
    Springer-Verlag, 1992                                         2631 1451  206
69. L.I.Klochkova et al.  Voprosy Atomnoy Nauki i Techniki, Ser.: 2631 1451  207
    Yadernye Konstanty, v.1, p.27, 1992                           2631 1451  208
70. ENDF/B-VI library,MAT=9237, eval. L.W.Weston et al. Nov.1989; 2631 1451  209
    H.Conde editor   Nuclear Data Standards for Nuclear Measu-    2631 1451  210
    rements, Report NEANDC-311 U, pp.70-74, OECD, Paris, 1992.    2631 1451  211
71. M.Wagner et al. Evaluation of cross sections for 14 important 2631 1451  212
    neutron-dosimetry reactions. Physics Data No.13-5, 1990       2631 1451  213
72. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          2631 1451  214
73. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2631 1451  215
    st's Meeting on Evaluation and Processing of Covariance Data, 2631 1451  216
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  2631 1451  217
74. L.W.Weston  et al.  Evaluated Neutron Data for Uranium-235,   2631 1451  218
    ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989    2631 1451  219
75. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        2631 1451  220
76. W.Mannhart  Proc. 5-th ASTM-EUR. Symp. on Reactor Dosimetry,  2631 1451  221
    Geesthacht, FRG, September 24-28, 1984, Vol.2, p.813, 1985    2631 1451  222
77. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 2631 1451  223
    Washington D.C., 25-28 April 1989, v.2, p.923                 2631 1451  224
78. W.Mannhart  Progress Report INDC(Ger)-045, pp.40-43, 1999     2631 1451  225
79. W.Mannhart  Handbook on Nuclear Activation Cross Sections ,   2631 1451  226
    IAEA Tech. Report Ser. No.273, p.413, 1987                    2631 1451  227
80. W.Mannhart  Validation of Differential Cross Sections with    2631 1451  228
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2631 1451  229
    September 2002                                                2631 1451  230
***************************************************************** 2631 1451  231
 The Q values and threshold energies were updated prior to pro-   2631 1451  232
 cessing through the codes to comply with the values obtained     2631 1451  233
 using the NNDC calculation program which is based on the 1995    2631 1451  234
 Update to the Atomic mass Evaluation.                            2631 1451  235
                                                                  2631 1451  236
 File 2 added to the pointwise file containing only the effective 2631 1451  237
 scattering radius with no resonance parameters given.            2631 1451  238
 Taken from ENDF/B-VI                                             2631 1451  239
***************************************************************** 2631 1451  240
 ***************** Program LINEAR (VERSION 2002-1) ***************2631 1451  241
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2631 1451  242
 Data Linearized to Within an Accuracy of .100000000 per-cent     2631 1451  243
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2631 1451  244
 Data Doppler Broadened to 300.000000 Kelvin                      2631 1451  245
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2631 1451  246
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2631 1451  247
 ***************** Program FIXUP (Version 2002-1) ****************2631 1451  248
 Corrected ZA/AWR in All Sections-----------------------------Yes 2631 1451  249
 Corrected Thresholds-----------------------------------------Yes 2631 1451  250
 Extended Cross Sections to 20 MeV----------------------------No  2631 1451  251
 Allow Cross Section Deletion---------------------------------No  2631 1451  252
 Allow Cross Section Reconstruction---------------------------No  2631 1451  253
 Make All Cross Sections Non-Negative-------------------------Yes 2631 1451  254
 Delete Energies Not in Ascending Order-----------------------Yes 2631 1451  255
 Deleted Duplicate Points-------------------------------------Yes 2631 1451  256
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2631 1451  257
 Check for Legal MF/MT Numbers--------------------------------Yes 2631 1451  258
 Allow Creation of Missing Sections---------------------------No  2631 1451  259
 Allow Insertion of Energy Points-----------------------------No  2631 1451  260
 Create Uniform Energy Grid-----------------------------------No  2631 1451  261
 Delete Section if Cross Section =0 at All Energies-----------Yes 2631 1451  262
 ***************** Program GROUPIE (VERSION 2002-1) **************2631 1451  263
 Unshielded Group Averages Using  640 Groups                      2631 1451  264
 Weighting Spectrum: Flat (Constant) Spectrum                     2631 1451  265
                                1        451        269          12631 1451  266
                                2        151          4          12631 1451  267
                                3        103         61          12631 1451  268
                               33        103         66          12631 1451  269
                                                                  2631 1  099999
                                                                  2631 0  0    0
 2.60560E+4 5.54540E+1          0          0          1          02631 2151    1
 2.605600+4 1.000000+0          0          0          1          02631 2151    2
 1.000000-5 8.500000+5          0          0          0          02631 2151    3
 0.000000+0 5.437300-1          0          0          0          02631 2151    4
                                                                  2631 2  099999
                                                                  2631 0  0    0
 2.60560E+4 5.54544E+1          0         99          0          02631 3103    1
-2.91310E+6-2.91310E+6          0          0          1        1722631 3103    2
        172          1                                            2631 3103    3
 2900000.00 5.9516E-12 3000000.00 8.5021E-11 3100000.00 1.8579E-102631 3103    4
 3200000.00 2.8657E-10 3300000.00 3.8734E-10 3400000.00 4.8811E-102631 3103    5
 3500000.00 3.19099E-9 3600000.00 2.37217E-8 3700000.00 2.30222E-72631 3103    6
 3800000.00 8.58242E-7 3900000.00 3.26945E-6 4000000.00 9.50803E-62631 3103    7
 4100000.00 2.13588E-5 4200000.00 4.12059E-5 4300000.00 7.22242E-52631 3103    8
 4400000.00 .000118637 4500000.00 .000186046 4600000.00 .0002818582631 3103    9
 4700000.00 .000415817 4800000.00 .000600658 4900000.00 .0008528442631 3103   10
 5000000.00 .001193315 5100000.00 .001648055 5200000.00 .0022481552631 3103   11
 5300000.00 .003028750 5400000.00 .004026080 5500000.00 .0052718752631 3103   12
 5600000.00 .006784800 5700000.00 .008560220 5800000.00 .0105616952631 3103   13
 5900000.00 .012519200 6000000.00 .014238450 6100000.00 .0161200002631 3103   14
 6200000.00 .018181150 6300000.00 .020072250 6400000.00 .0217811502631 3103   15
 6500000.00 .023826650 6600000.00 .025746950 6700000.00 .0270865002631 3103   16
 6800000.00 .028396700 6900000.00 .029706900 7000000.00 .0310583252631 3103   17
 7100000.00 .032450975 7200000.00 .033907625 7300000.00 .0354282752631 3103   18
 7400000.00 .037005975 7500000.00 .038640725 7600000.00 .0403027402631 3103   19
 7700000.00 .041992020 7800000.00 .043681300 7900000.00 .0453705802631 3103   20
 8000000.00 .047059860 8100000.00 .048700150 8200000.00 .0502914502631 3103   21
 8300000.00 .051829775 8400000.00 .053315125 8500000.00 .0547361002631 3103   22
 8600000.00 .056092700 8700000.00 .057449300 8800000.00 .0587423902631 3103   23
 8900000.00 .059971970 9000000.00 .061201550 9100000.00 .0624311302631 3103   24
 9200000.00 .063660710 9300000.00 .064888420 9400000.00 .0661142602631 3103   25
 9500000.00 .067340100 9600000.00 .068565940 9700000.00 .0697917802631 3103   26
 9800000.00 .071069213 9900000.00 .072398238 10000000.0 .0737272632631 3103   27
 10100000.0 .075056288 10200000.0 .076448125 10300000.0 .0779027752631 3103   28
 10400000.0 .079357425 10500000.0 .080812075 10600000.0 .0823283602631 3103   29
 10700000.0 .083906280 10800000.0 .085484200 10900000.0 .0870621202631 3103   30
 11000000.0 .088640040 11100000.0 .090238714 11200000.0 .0918581432631 3103   31
 11300000.0 .093477571 11400000.0 .095097000 11500000.0 .0967164292631 3103   32
 11600000.0 .098335857 11700000.0 .099955286 11800000.0 .1014997502631 3103   33
 11900000.0 .102969250 12000000.0 .104438750 12100000.0 .1059082502631 3103   34
 12200000.0 .107264833 12300000.0 .108508500 12400000.0 .1097521672631 3103   35
 12500000.0 .110859000 12600000.0 .111829000 12700000.0 .1127990002631 3103   36
 12800000.0 .113632500 12900000.0 .114329500 13000000.0 .1149057502631 3103   37
 13100000.0 .115361250 13200000.0 .115689750 13300000.0 .1158912502631 3103   38
 13400000.0 .115996000 13500000.0 .115908000 13600000.0 .1157240002631 3103   39
 13700000.0 .115415750 13800000.0 .114983250 13900000.0 .1144076672631 3103   40
 14000000.0 .113689000 14100000.0 .112970333 14200000.0 .1121030002631 3103   41
 14300000.0 .111087000 14400000.0 .110071000 14500000.0 .1089375002631 3103   42
 14600000.0 .107686500 14700000.0 .106435500 14800000.0 .1050908752631 3103   43
 14900000.0 .103652625 15000000.0 .102214375 15100000.0 .1007761252631 3103   44
 15200000.0 .099278768 15300000.0 .097722305 15400000.0 .0961658412631 3103   45
 15500000.0 .094609377 15600000.0 .093052914 15700000.0 .0914964502631 3103   46
 15800000.0 .089939986 15900000.0 .088383523 16000000.0 .0868270592631 3103   47
 16100000.0 .085270595 16200000.0 .083714132 16300000.0 .0822083502631 3103   48
 16400000.0 .080753250 16500000.0 .079298150 16600000.0 .0778430502631 3103   49
 16700000.0 .076387950 16800000.0 .074994575 16900000.0 .0736629252631 3103   50
 17000000.0 .072331275 17100000.0 .070999625 17200000.0 .0697291002631 3103   51
 17300000.0 .068519700 17400000.0 .067310300 17500000.0 .0661009002631 3103   52
 17600000.0 .064953475 17700000.0 .063868025 17800000.0 .0627825752631 3103   53
 17900000.0 .061697125 18000000.0 .060671725 18100000.0 .0597063752631 3103   54
 18200000.0 .058741025 18300000.0 .057775675 18400000.0 .0568670002631 3103   55
 18500000.0 .056015000 18600000.0 .055163000 18700000.0 .0543110002631 3103   56
 18800000.0 .053511638 18900000.0 .052764913 19000000.0 .0520181882631 3103   57
 19100000.0 .051271463 19200000.0 .050573338 19300000.0 .0499238132631 3103   58
 19400000.0 .049274288 19500000.0 .048624763 19600000.0 .0480200382631 3103   59
 19700000.0 .047460113 19800000.0 .046900188 19900000.0 .0463402632631 3103   60
 20000000.0 0.0                                                   2631 3103   61
                                                                  2631 3  099999
                                                                  2631 0  0    0
 2.60560E+4 5.54544E+1          0          0          0          1263133103    1
 0.000000+0 0.000000+0          0        103          0          1263133103    2
 0.000000+0 0.000000+0          1          5        378         27263133103    3
 1.000000-5 2.900000+6 5.000000+6 6.000000+6 7.000000+6 8.000000+6263133103    4
 9.000000+6 1.000000+7 1.100000+7 1.150000+7 1.200000+7 1.250000+7263133103    5
 1.300000+7 1.350000+7 1.400000+7 1.450000+7 1.500000+7 1.550000+7263133103    6
 1.600000+7 1.650000+7 1.700000+7 1.750000+7 1.800000+7 1.850000+7263133103    7
 1.900000+7 1.950000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0263133103    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0263133103    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0263133103   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0263133103   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 6.980350-3263133103   12
 2.338270-3 1.702360-4 4.353220-4-6.002120-5 3.473780-4 1.342800-4263133103   13
-1.013590-4-1.453170-4-1.032110-4-1.910370-5 5.580590-5 8.566180-5263133103   14
 6.229070-5 2.961970-6-6.242280-5-1.056550-4-1.094340-4-7.037860-5263133103   15
 1.788090-6 8.621690-5 1.524240-4 1.605400-4 6.014590-5-2.124840-4263133103   16
 2.467980-3 6.043630-4 3.578130-4 2.055220-4 1.680110-4 2.128390-4263133103   17
 1.769540-4 1.366700-4 9.916600-5 7.004770-5 5.015720-5 3.742600-5263133103   18
 2.898990-5 2.276790-5 1.801980-5 1.502850-5 1.442320-5 1.658450-5263133103   19
 2.127870-5 2.748400-5 3.331180-5 3.591800-5 3.136190-5 1.435050-5263133103   20
 2.089910-3 5.811850-4 5.051160-4 4.463010-4 2.985330-4 2.415270-4263133103   21
 2.109770-4 1.764960-4 1.378030-4 9.933400-5 6.703660-5 4.523120-5263133103   22
 3.491560-5 3.399020-5 3.868840-5 4.511620-5 5.024920-5 5.232580-5263133103   23
 5.086090-5 4.651010-5 4.095130-5 3.684360-5 3.791020-5 2.324770-3263133103   24
 8.909680-4 2.243430-4 3.463970-4 3.586080-4 2.979140-4 2.137770-4263133103   25
 1.316880-4 7.020240-5 3.717340-5 2.982110-5 3.851070-5 5.200710-5263133103   26
 6.154930-5 6.257380-5 5.457370-5 4.014340-5 2.400670-5 1.237870-5263133103   27
 1.271590-5 3.381980-5 8.624440-5 1.319090-3 6.075680-4 2.355910-4263133103   28
 1.831400-4 1.797820-4 1.702720-4 1.477000-4 1.151050-4 8.057420-5263133103   29
 5.231750-5 3.522030-5 2.987090-5 3.362030-5 4.237480-5 5.207540-5263133103   30
 5.950970-5 6.257730-5 6.025220-5 5.245210-5 3.991740-5 2.416230-5263133103   31
 9.567740-4 6.313680-4 3.548430-4 2.308720-4 1.569670-4 1.197830-4263133103   32
 1.026490-4 9.147350-5 7.836800-5 6.207430-5 4.573040-5 3.376500-5263133103   33
 2.952730-5 3.417020-5 4.646570-5 6.302500-5 7.854620-5 8.588480-5263133103   34
 7.587850-5 3.687780-5 8.246530-4 7.196220-4 5.696170-4 4.048130-4263133103   35
 2.567500-4 1.473680-4 8.506790-5 6.460670-5 7.167200-5 8.965720-5263133103   36
 1.051550-4 1.104520-4 1.034970-4 8.671160-5 6.568700-5 4.830190-5263133103   37
 4.434860-5 6.563950-5 1.265420-4 7.702400-4 6.761850-4 5.244410-4263133103   38
 3.568230-4 2.113590-4 1.126140-4 6.666460-5 6.340340-5 8.424730-5263133103   39
 1.104340-4 1.283210-4 1.311310-4 1.184390-4 9.489290-5 6.907830-5263133103   40
 5.291210-5 6.162700-5 1.143590-4 6.324280-4 5.237220-4 3.833900-4263133103   41
 2.465290-4 1.404880-4 7.815570-5 5.731600-5 6.563580-5 8.760000-5263133103   42
 1.098400-4 1.236410-4 1.252570-4 1.152190-4 9.746320-5 7.872510-5263133103   43
 6.832810-5 7.841040-5 4.660800-4 3.703690-4 2.615780-4 1.637400-4263133103   44
 9.329270-5 5.585710-5 4.758000-5 5.925580-5 8.050700-5 1.024550-4263133103   45
 1.187560-4 1.256000-4 1.212720-4 1.056640-4 7.989500-5 4.610700-5263133103   46
 3.221980-4 2.512470-4 1.743220-4 1.074110-4 6.116180-5 3.911000-5263133103   47
 3.878810-5 5.417430-5 7.796430-5 1.029630-4 1.226310-4 1.310680-4263133103   48
 1.227080-4 9.188330-5 3.231030-5 2.173730-4 1.684250-4 1.165000-4263133103   49
 7.298230-5 4.527820-5 3.576720-5 4.260230-5 6.120560-5 8.556410-5263133103   50
 1.089960-4 1.244090-4 1.241890-4 9.983000-5 4.136060-5 1.477430-4263133103   51
 1.185060-4 8.879480-5 6.555160-5 5.284920-5 5.160670-5 6.020940-5263133103   52
 7.533050-5 9.255920-5 1.067160-4 1.118820-4 1.012050-4 6.649160-5263133103   53
 1.138400-4 1.048040-4 9.446080-5 8.548980-5 7.961900-5 7.752210-5263133103   54
 7.899010-5 8.316230-5 8.870200-5 9.388370-5 9.659180-5 9.423730-5263133103   55
 1.173920-4 1.242110-4 1.246130-4 1.193480-4 1.101060-4 9.908370-5263133103   56
 8.873970-5 8.171760-5 8.089820-5 8.954360-5 1.115220-4 1.477160-4263133103   57
 1.605150-4 1.612980-4 1.513370-4 1.337330-4 1.127760-4 9.360740-5263133103   58
 8.216990-5 8.538600-5 1.115530-4 1.858920-4 1.970250-4 1.936170-4263133103   59
 1.779120-4 1.539130-4 1.268590-4 1.030300-4 8.983880-5 9.619200-5263133103   60
 2.208930-4 2.302800-4 2.251120-4 2.070470-4 1.789350-4 1.444760-4263133103   61
 1.081310-4 7.522490-5 2.563740-4 2.685600-4 2.647750-4 2.436270-4263133103   62
 2.040130-4 1.447640-4 6.437880-5 3.017630-4 3.184520-4 3.123860-4263133103   63
 2.767690-4 2.037260-4 8.360900-5 3.586650-4 3.751200-4 3.563580-4263133103   64
 2.888990-4 1.563190-4 4.204370-4 4.352960-4 4.045150-4 3.095700-4263133103   65
 5.050460-4 5.556140-4 5.751470-4 7.485460-4 9.914130-4 1.606050-3263133103   66
                                                                  263133  099999
                                                                  2631 0  0    0
                                                                     0 0  0    0
 2.60580E+4 5.74356E+1          0          0         34         102637 1451    1
 0.0        0.0                 0          0          0          62637 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022637 1451    3
 3.00000E+2 0.0                 1          0        162          42637 1451    4
 26-Fe- 58 JAERI      EVAL-OCT95 T.NAKAGAWA                       2637 1451    5
                      DIST-Feb2004                                2637 1451    6
----IRDF-2002         MATERIAL 2637                               2637 1451    7
-----INCIDENT NEUTRON DATA                                        2637 1451    8
------ENDF-6 FORMAT                                               2637 1451    9
******************************************************************2637 1451   10
 26-FE- 58 JAERI      EVAL-OCT95 T.NAKAGAWA                       2637 1451   11
                      DIST-JUL98                                  2637 1451   12
----JENDL/D-99        MATERIAL 2637                               2637 1451   13
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2637 1451   14
DOSIMETRY                                                         2637 1451   15
******************************************************************2637 1451   16
HISTORY                                                           2637 1451   17
93-10  JENDL-3.2.                                                 2637 1451   18
       RE-EVALUATION WAS MADE BY                                  2637 1451   19
         T.NAKAGAWA (NDC/JAERI): RESONANCE PARAMS, CROSS SECTIONS 2637 1451   20
         S.IGARASI (NEDAC): GAMMA-RAY PRODUCTION DATA BELOW 10 KEV2637 1451   21
       COMPILED BY T.NAKAGAWA                                     2637 1451   22
95-10  COVARIANCES WERE ESTIMATED BY T.NAKAGAWA.                  2637 1451   23
98-04  COMPILED TO JENDL DOSIMETRY FILE 99.                       2637 1451   24
02-10  COVARIANCES WERE MODIFIED BY K.SHIBATA.                    2637 1451   25
                                                                  2637 1451   26
            ===== ORIGINAL DATA FILE =====                        2637 1451   27
                                                                  2637 1451   28
 <DOSIMETRY CROSS SECTION>                                        2637 1451   29
      FE-58 CAPTURE FE-59 (HALF-LIFE = 44.503 H)                  2637 1451   30
                                                                  2637 1451   31
MF=1  GENERAL INFORMATION                                         2637 1451   32
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          2637 1451   33
                                                                  2637 1451   34
                                                                  2637 1451   35
MF=2  RESONANCE PARAMETERS                                        2637 1451   36
  MT = 151 RESOLVED RESONANCES                                    2637 1451   37
     TAKEM FROM JENDL-3.2/1/.                                     2637 1451   38
      RESONANCE REGION = 1.0E-5 EV TO 350.0 KEV                   2637 1451   39
      THE MULTILEVEL BREIT-WIGNER FORMULA WAS USED.  PARAMETERS   2637 1451   40
      WERE DETERMINED ON THE BASIS OF DATA BY GARG ET AL./2/,     2637 1451   41
      KAEPPELER ET AL./3/, ALLEN AND MACKLIN/4/.                  2637 1451   42
                                                                  2637 1451   43
      CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.      2637 1451   44
                      2200-M/S     RES. INTEG.                    2637 1451   45
         ELASTIC       6.470 B         -                          2637 1451   46
         CAPTURE       1.300 B        1.36 B                      2637 1451   47
         TOTAL         7.770 B         -                          2637 1451   48
                                                                  2637 1451   49
MF = 3 CROSS SECTIONS                                             2637 1451   50
 MT = 1   TOTAL CROSS SECTION                                     2637 1451   51
    TAKEN FROM JENDL-3.2/1/.                                      2637 1451   52
                                                                  2637 1451   53
 MT=2   ELASTIC                                                   2637 1451   54
      TOTAL CROSS SECTION - SUM OF PARTIAL CROSS SECTIONS         2637 1451   55
    TAKEN FROM JENDL-3.2/1/.                                      2637 1451   56
                                                                  2637 1451   57
 MT = 102 CAPTURE CROSS SECTION                                   2637 1451   58
    THE CAPTURE CROSS SECTION WAS ADOPTED FROM JENDL-3.2/1/.      2637 1451   59
                                                                  2637 1451   60
    IN THE RESONANCE REGION BELOW 350 KEV, THE CROSS SECTION WAS  2637 1451   61
  CALCULATED FROM THE MULTILEVEL BREIT-WIGNER FORMULA WITH        2637 1451   62
  RESONANCE PARAMETERS DETERMINED ON THE BASIS OF DATA BY GARG ET 2637 1451   63
  AL./2/, KAEPPELER ET AL./3/, AND ALLEN AND MACKLIN/4/. ABOVE    2637 1451   64
  350 KEV, THE CROSS SECTION WAS CALCULATED WITH THE OPTICAL AND  2637 1451   65
  STATISTICAL MODEL CODE CASTHY/5/ BY NORMALIZING TO 3 MB AT 500  2637 1451   66
  KEV/6/.  CONTRIBUTIONS TO THE INELASTIC SCATTERING PROCESSES    2637 1451   67
  WERE CONSIDERED BY ADOPTING THE EXCITED LEVELS IN THE FOLLOWING 2637 1451   68
  TABLE.  AND THE CONTRIBUTIONS TO THE (N,2N), (N,N'A), (N,N'P),  2637 1451   69
  (N,P) AND (N,A) REACTION CROSS SECTIONS WERE ALSO CONSIDERED IN 2637 1451   70
  THE CASTHY CALCULATION. THESE THRESHOLD REACTION CROSS SECTIONS 2637 1451   71
  WERE CALCULATED WITH GNASH/7/. THE DIRECT CAPTURE CROSS SECTION 2637 1451   72
  WAS CALCULATED WITH A SIMPLE FORMULA DERIVED BY BENZI AND       2637 1451   73
  REFFO/8/ AND ADDED TO THE RESULT OF CASTHY CALCULATION.         2637 1451   74
                                                                  2637 1451   75
    OPTICAL POTENTIAL PARAMETERS                                  2637 1451   76
    -----------------------------                                 2637 1451   77
         V  = 46.0-0.25*EN (MEV),                                 2637 1451   78
         WS = 14.0-0.2*EN  (MEV),  (IN THE GAUSSIAN FORM)         2637 1451   79
         WI = 0.125*E-0.0004*E**2 (MEV),                          2637 1451   80
         VSO= 6.0          (MEV),                                 2637 1451   81
         R  = 1.286 (FM), A0 = 0.62  (FM)                         2637 1451   82
         RS = 1.387 (FM), AS = 0.7   (FM)                         2637 1451   83
         RSO= 1.07  (FM), ASO= 0.62  (FM)                         2637 1451   84
                                                                  2637 1451   85
    LEVEL SCHEME                                                  2637 1451   86
    ------------                                                  2637 1451   87
          NO.     ENERGY(MEV)  SPIN-PARITY                        2637 1451   88
         G.S.      0.0          0 +                               2637 1451   89
          1.       0.8108       2 +                               2637 1451   90
          2.       1.6747       2 +                               2637 1451   91
          3.       2.0765       4 +                               2637 1451   92
          4.       2.1339       3 +                               2637 1451   93
          5.       2.2581       0 +                               2637 1451   94
          6.       2.6004       4 +                               2637 1451   95
          7.       2.7819       1 +                               2637 1451   96
          8.       2.8764       2 +                               2637 1451   97
          9.       3.0840       2 +                               2637 1451   98
         10.       3.1330       4 +                               2637 1451   99
         11.       3.2330       2 +                               2637 1451  100
         12.       3.2440       0 +                               2637 1451  101
       LEVELS ABOVE 3.389 MEV WERE ASSUMED TO BE OVERLAPPING.     2637 1451  102
                                                                  2637 1451  103
MF = 33 COVARIANCES OF NEUTRON CROSS SECTIONS                     2637 1451  104
 MT=102 CAPTURE CROSS SECTION                                     2637 1451  105
                                                                  2637 1451  106
    IN THE RESONANCE REGION, THE VARIANCE OF CROSS SECTION WAS    2637 1451  107
  ESTIMATED FROM STANDARD DEVIATIONS OF THE RESONANCE PARAMETERS. 2637 1451  108
  THE STANDARD DEVIATIONS WERE TAKEN FROM THE EXPERIMENTAL DATA   2637 1451  109
  WHICH WERE CONSIDERED IN THE PARAMETER EVALUATION. FOR THE      2637 1451  110
  RESONANCE PARAMETERS DETERMINED FROM THE CAPTURE AREA, THEIR    2637 1451  111
  ERRORS WERE ESTIMATED FROM THE ERROR OF CAPTURE AREA. AN ERROR  2637 1451  112
  OF 10 % WAS ASSUMED FOR OTHER CASES.                            2637 1451  113
                                                                  2637 1451  114
    ABOVE 350 KEV, COVARIANCE MATRIX WAS OBTAINED BY USING        2637 1451  115
  KALMAN/10/. ERRORS WERE CONSIDERED TO THE OPTICAL POTENTIAL AND 2637 1451  116
  LEVEL DENSITY PARAMETERS, AND THE NORMALIZATION CROSS SECTION.  2637 1451  117
                                                                  2637 1451  118
                                                                  2637 1451  119
REFERENCES                                                        2637 1451  120
 1) NAKAGAWA T. ET AL.: J. NUCL. SCI. TECHNOL., 32, 1259 (1995).  2637 1451  121
 2) GARG J.B. ET AL.: PHYS. REV., C18, 1141 (1978).               2637 1451  122
 3) KAEPPELER F. ET AL.: NUCL. SCI. ENG., 84, 234 (1983).         2637 1451  123
 4) ALLEN B.J. AND MACKLIN R.L.: J. PHYS. G., 6, 381 (1980).      2637 1451  124
 5) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                2637 1451  125
 6) TROFIMOV JU.N.: ATOMNAJA ENERGIJA, 58, 278 (1985).            2637 1451  126
 7) YOUNG P.G. AND ARTHUR E.D.: LA-6974 (1977).                   2637 1451  127
 8) BENZI V. AND REFFO G.: CCDN/NW/10 (1969).                     2637 1451  128
 9) YAMAKOSHI H.: JAERI 1261, P.30 (1979).                        2637 1451  129
10) KAWANO T. AND SHIBATA K.: JAERI-DATA/CODE 97-037 (1997)       2637 1451  130
    [IN JAPANESE]                                                 2637 1451  131
                                                                  2637 1451  132
******************************************************************2637 1451  133
 The Q values and threshold energies were updated prior to pro-   2637 1451  134
 cessing through the codes to comply with the values obtained     2637 1451  135
 using the NNDC calculation program which is based on the 1995    2637 1451  136
 Update to the Atomic mass Evaluation.                            2637 1451  137
******************************************************************2637 1451  138
 ***************** Program LINEAR (VERSION 2002-1) ***************2637 1451  139
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2637 1451  140
 Data Linearized to Within an Accuracy of .100000000 per-cent     2637 1451  141
 ***************** Program RECENT (VERSION 2002-1) ***************2637 1451  142
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2637 1451  143
 Data Linearized to within an Accuracy of .100000000 per-cent     2637 1451  144
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2637 1451  145
 Data Doppler Broadened to 300.000000 Kelvin                      2637 1451  146
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2637 1451  147
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2637 1451  148
 ***************** Program FIXUP (Version 2002-1) ****************2637 1451  149
 Corrected ZA/AWR in All Sections-----------------------------Yes 2637 1451  150
 Corrected Thresholds-----------------------------------------Yes 2637 1451  151
 Extended Cross Sections to 20 MeV----------------------------No  2637 1451  152
 Allow Cross Section Deletion---------------------------------No  2637 1451  153
 Allow Cross Section Reconstruction---------------------------No  2637 1451  154
 Make All Cross Sections Non-Negative-------------------------Yes 2637 1451  155
 Delete Energies Not in Ascending Order-----------------------Yes 2637 1451  156
 Deleted Duplicate Points-------------------------------------Yes 2637 1451  157
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2637 1451  158
 Check for Legal MF/MT Numbers--------------------------------Yes 2637 1451  159
 Allow Creation of Missing Sections---------------------------No  2637 1451  160
 Allow Insertion of Energy Points-----------------------------No  2637 1451  161
 Create Uniform Energy Grid-----------------------------------No  2637 1451  162
 Delete Section if Cross Section =0 at All Energies-----------Yes 2637 1451  163
 ***************** Program GROUPIE (VERSION 2002-1) **************2637 1451  164
 Unshielded Group Averages Using  640 Groups                      2637 1451  165
 Weighting Spectrum: Flat (Constant) Spectrum                     2637 1451  166
                                1        451        170          12637 1451  167
                                2        151          4          12637 1451  168
                                3        102        217          12637 1451  169
                               33        102        200          12637 1451  170
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 5.439890-3 4.040780-3 8.571640-4 1.102500-2 1.306150-2 1.509890-2263733102  189
 1.724460-2 1.918590-2 2.120880-2 1.205000-2 7.614630-3 3.937350-3263733102  190
 1.748330-4-3.032670-3 1.716100-2 2.007790-2 2.296380-2 2.600090-2263733102  191
 2.868950-2 1.526500-2 8.626110-3 2.794700-3-2.965560-3-6.111480-3263733102  192
 2.496400-2 2.837000-2 3.205500-2 3.559640-2 1.889820-2 1.035410-2263733102  193
 2.874230-3-4.179100-3-6.893270-3 3.422500-2 3.780380-2 4.258630-2263733102  194
 2.280370-2 1.270380-2 4.104470-3-3.570120-3-5.771380-3 4.452100-2263733102  195
 4.894050-2 2.666180-2 1.559110-2 6.239220-3-1.641400-3-3.268030-3263733102  196
 5.904900-2 3.828800-2 2.968610-2 2.309590-2 2.096800-2 2.670880-2263733102  197
 6.150400-2 7.269370-2 8.635430-2 1.136110-1 1.503490-1 1.004890-1263733102  198
 1.229590-1 1.670490-1 2.212880-1 1.648360-1 2.211800-1 2.929660-1263733102  199
 3.226240-1 4.279660-1 6.352090-1                                 263733102  200
                                                                  263733  099999
                                                                  2637 0  0    0
                                                                     0 0  0    0
 2.70590E+4 5.84269E+1          0          0         34         102725 1451    1
 0.0        0.0                 0          0          0          62725 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022725 1451    3
 3.00000E+2 0.0                 1          0        233          82725 1451    4
 27-Co- 59 IRK/FEI    EVAL-APR90 VONACH ET AL., K.I.Zolotarev     2725 1451    5
                      DIST-Feb2004                                2725 1451    6
----IRDF-2002         MATERIAL 2725                               2725 1451    7
-----INCIDENT NEUTRON DATA                                        2725 1451    8
------ENDF-6 FORMAT                                               2725 1451    9
******************************************************************2725 1451   10
 27-CO- 59 ANL,ORNL   EVAL-JUL89 A.SMITH+,G.DESAUSSURE+           2725 1451   11
 ANL/NDM-107          DIST-JUN93 REV1-JUN92            19930930   2725 1451   12
----ENDF/B-VI         MATERIAL 2725         REVISION 1            2725 1451   13
******************************************************************2725 1451   14
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2725 1451   15
DOSIMETRY                                                         2725 1451   16
******************************************************************2725 1451   17
***************************************************************** 2725 1451   18
**********   Start of (N,G) bibliographical component *********** 2725 1451   19
   MF=2,MT=151, MF=3,MT=1,2,102 taken from ENDF/B-VI Release 2    2725 1451   20
   MF=33,MT=102 taken from IRDF-90                                2725 1451   21
***************************************************************** 2725 1451   22
 REVISION 1 -- NEW RESONANCE REGION EVALUATION BY G.DESAUSSURE,   2725 1451   23
   N.M.LARSON, J.A.HARVEY, N.W.HILL, ANN. NUCL. ENERGY 19, 393    2725 1451   24
   (1992)                                                         2725 1451   25
 ORIGINAL EVALUATION                                              2725 1451   26
 A.SMITH,D.SMITH,P.GUENTHER,J.MEADOWS, R.LAWSON(ANL),             2725 1451   27
 R.HOWERTON(LLNL),M.SUGIMOTO(JAERI)                               2725 1451   28
******************************************************************2725 1451   29
 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC             2725 1451   30
 *         *          *          *          *          *         *2725 1451   31
 R.LAWSON(ANL),R.HOWERTON(LLNL),M.SUGIMOTO(JAERI)                 2725 1451   32
***************************************************************** 2725 1451   33
**********   End of (N,G) bibliographical component   *********** 2725 1451   34
***************************************************************** 2725 1451   35
***************************************************************** 2725 1451   36
**********   Start of (N,2N) bibliographical component ********** 2725 1451   37
***************************************************************** 2725 1451   38
++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++2725 1451   39
         MF/MT 2151, MF/MT 3 16 AND MF/MT 33 16 FROM FOLLOWING    2725 1451   40
         EVALUATION                                               2725 1451   41
                27-CO- 59 IRK-VIENNA EVAL-APR90                   2725 1451   42
                                     DIST-JUN90                   2725 1451   43
                IRK-EVAL.NLIB 25  2725                            2725 1451   44
++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++2725 1451   45
***************************************************************** 2725 1451   46
**********   End of (N,2N) bibliographical component  *********** 2725 1451   47
***************************************************************** 2725 1451   48
***************************************************************** 2725 1451   49
**********   Start of (N,A) bibliographical component  ********** 2725 1451   50
***************************************************************** 2725 1451   51
***************************************************************** 2725 1451   52
------Russian Reactor Dosimetry File RRDF-2002                    2725 1451   53
***************************************************************** 2725 1451   54
Author  of evaluation: K.I.Zolotarev                              2725 1451   55
***************************************************************** 2725 1451   56
MF=3                                                              2725 1451   57
MT=107 -(n,a) cross section                                       2725 1451   58
-------------------------------------                             2725 1451   59
    Excitation function for the  Co-59(n,a)Mn-56 reaction in the  2725 1451   60
energy region from 2.5 MeV   to 21 MeV was evaluated by means of  2725 1451   61
statistical analysis of  experimental cross section  data [1-28], 2725 1451   62
and data from GNASH [29] calculation.                             2725 1451   63
    All experimental data were renormalized to the new standards  2725 1451   64
for monitor reactions cross sections and decay data. Uncertainty  2725 1451   65
in the monitor reaction  cross section  was added  to  the total  2725 1451   66
uncertainty for Santry and Butler data [5].   Cross section data  2725 1451   67
measured by Huang Jianzhou et al. [18]  were renormalized to the  2725 1451   68
preliminary evaluated  integral  of excitation function  in  the  2725 1451   69
energy range 13.0 - 15.0 MeV.  Correction factor for  this  data  2725 1451   70
was equal Fc= 1.0507 .                                            2725 1451   71
    Experimental data from ref.[30-41] were rejected due to their 2725 1451   72
discrepancy  with  the main bulk of experimental data [1-28]  and 2725 1451   73
data from theoretical model calculation.                          2725 1451   74
    The final procedure of evaluation Co-59(n,a)Mn-56  excitation 2725 1451   75
function from threshold to 21 MeV has been carried out within the 2725 1451   76
framework of generalized least squares method.  Rational function 2725 1451   77
was used  as  model function [42].  Calculations was performed by 2725 1451   78
means of  Pade-2 code [43].                                       2725 1451   79
    The evaluated  Co-59(n,a)Mn-56  excitation  function averaged 2725 1451   80
on  U-235  neutron fission spectrum [44]  and  Cf-252 spontaneous 2725 1451   81
fission neutron spectrum [45] gives the next values :             2725 1451   82
  2725 1451   83
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  2725 1451   84
  2725 1451   85
                                         0.1500 +- 0.0080 [46]  2725 1451   86
 U-235 neutron fission      0.15823      0.1700 +- 0.0120 [47]  2725 1451   87
                                         0.1568 +- 0.0035 [48]  2725 1451   88
  2725 1451   89
                                         0.2208 +- 0.0014 [49]  2725 1451   90
 Cf-252 spont. fission      0.22095      0.2221 +- 0.0023 [50]  2725 1451   91
                                         0.2218 +- 0.0041 [51]  2725 1451   92
  2725 1451   93
                                                                  2725 1451   94
MT=33                                                             2725 1451   95
MT=107 -(n,a) cross section cov. matrix                           2725 1451   96
-------------------------------------------                       2725 1451   97
    Uncertainties in the evaluated  excitation function  for the  2725 1451   98
reaction Co-59(n,a)Mn-56  are given in the form of relative cova- 2725 1451   99
riance matrix for the 32-neutron energy groups (LB=5). Covariance 2725 1451  100
matrix of uncertainties was calculated simultaneously with recom- 2725 1451  101
mended cross section data by means of PADE-2 code.                2725 1451  102
    Eigenvalues  of the  6-th digits  relative covariance matrix  2725 1451  103
given in the 33-file are the following:                           2725 1451  104
                                                                  2725 1451  105
    1.11275E-08    1.13832E-08    1.19424E-08    1.27401E-08      2725 1451  106
    1.37409E-08    1.52188E-08    1.67720E-08    1.86812E-08      2725 1451  107
    2.09005E-08    2.38172E-08    2.69210E-08    3.07595E-08      2725 1451  108
    3.46853E-08    4.07806E-08    4.51537E-08    5.55085E-08      2725 1451  109
    6.19014E-08    7.83507E-08    9.39864E-08    1.01329E-07      2725 1451  110
    2.19793E-07    8.71735E-07    1.71048E-05    1.93185E-04      2725 1451  111
    1.05065E-03    1.19481E-03    2.01786E-03    2.53733E-03      2725 1451  112
    3.28491E-03    1.06037E-02    2.32281E-02    9.30559E-01      2725 1451  113
                                                                  2725 1451  114
References :                                                      2725 1451  115
 1. H.G.Blosser et.al.  Phys. Rev., v.110, p.531, 1958            2725 1451  116
 2. I.L.Preiss,R.W.Fink  Nucl. Phys., v.15, p.326, February 1960  2725 1451  117
 3. C.S.Khurana, H.S.Hans  Proc.of 4th Nuclear Physics and Solid  2725 1451  118
    State Physics Symp., 24-26 Feb. 1960, Waltair, India, p.297   2725 1451  119
 4. E.Weigold  Australian J. Phys., v.13, p.186, 1960             2725 1451  120
 5. D.C.Santry, J.P.Butler  Can. J. Phys., v.42, p.1030, 1964     2725 1451  121
 6. H.Liskien, A.Paulsen  J. Nucl. of Energy, v.19, p.73, 1965    2725 1451  122
 7. K.S.Khurana,I.M.Govil  Nucl. Phys., v.69, p.153, July 1965    2725 1451  123
 8. H.Liskien, A.Paulsen  Nucleonics, v.8, p.315, June 1966       2725 1451  124
 9. V.N.Levkovskiy et.al. Yadernaja Fizika (Sov.), v.8, n.1, p.7, 2725 1451  125
    July 1968                                                     2725 1451  126
10. J.C.Robertson, B.Audric, P.Kolkowski  J. Nucl. Energ., v.27,  2725 1451  127
    p.531, August 1973                                            2725 1451  128
11. S.K.Ghorai, J.E.Gaiser, W.L.Alford  Annals of Nucl. Energy,   2725 1451  129
    v.7, p.41, 1980                                               2725 1451  130
12. E.Zupranska et al.  Progress Report INR-1821/I/PL/A, 1980     2725 1451  131
    E.Zupranska et al.  Acta. Phys. Pol., v.B11, p.853, Nov. 1980 2725 1451  132
13. B.M.Bahal, R.Pepelnik  Report GKSS-84-E-, 1984                2725 1451  133
14. J.W.Meadows, D.L.Smith et al.  Annals of Nucl. Energy, v.14,  2725 1451  134
    p.489, 1987                                                   2725 1451  135
15. J.W.Meadows, D.L.Smith, R.D.Lawson  Annals of Nucl. Energy,   2725 1451  136
    v.14, p.603, 1987                                             2725 1451  137
16. Y.Ikeda, C.Konno, K.Oishi et al. Report JAERI-1312, 1988      2725 1451  138
17. T.B.Ryves, P.Kolkowski, S.M.Judge  Annals of Nuclear Energy,  2725 1451  139
    v.15, p.561, Dec.1988                                         2725 1451  140
18. Huang Jianzhou et al. Report INDC(CPR)-16, Vienna,August 1989 2725 1451  141
19. I.Kimura, K.Kobayashi  Nucl. Sci. Eng., v.106, p.332, 1990    2725 1451  142
20. Li Tingyan et al.  High Energy Physics and Nuclear Physics,   2725 1451  143
    v.14(6), p.542, June 1990                                     2725 1451  144
21. A.Ercan et al.  Proc. of an Intern. Conf. on Nuclear Data for 2725 1451  145
    Science and Technology, 13-17 May 1991, Julich, FRG, Springer-2725 1451  146
    Verlag, 1992, p.376-377                                       2725 1451  147
22. Y.Ikeda et al. Progress Report INDC(JPN)-162/U,p.24, Aug.1992 2725 1451  148
23. A.Grallert et al. Report INDC(NDS)-286, p.193, IAEA, 1993     2725 1451  149
24. W.Mannhart et al. Proc.of International Conference on Nuclear 2725 1451  150
    Data for Science and Technology, Gatlinburg, Tennessee, May   2725 1451  151
    9-13, 1994, v.1, pp.285-287                                   2725 1451  152
25. A.A.Filatenkov et al. VANT, Ser.:Yadernye Konstanty, v.2, p.8,2725 1451  153
    Moscow, 1996                                                  2725 1451  154
26. K.T.Osman, F.I.Habbani  Report INDC(SUD)-001, Distr.L, IAEA,  2725 1451  155
    Vienna, October 1996                                          2725 1451  156
27. A.D.Majdeddin Measurement and analysis of excitation func-    2725 1451  157
    tions for fast neutron induced reactions from threshold to    2725 1451  158
    20 MeV. PHD dissertation, Inst. of Experimental Physics ,     2725 1451  159
    Kossuth University, Hungary, June 1998                        2725 1451  160
28. A.A.Filatenkov et al. Report RI-252, St. Petersburg, May 1999 2725 1451  161
29. P.G.Young, E.D.Arthur  A Preequilibrium Statistical Nuclear   2725 1451  162
    Model Code for Calculation of Cross Section and Emission      2725 1451  163
    Spectra. Report LA-6947, Los Alamos, 1977 ;                   2725 1451  164
    E.L.Trykiv, G.Ya.Tertychnyi  Private communication, IPPE,     2725 1451  165
    Obninsk, May 1999                                             2725 1451  166
30. E.B.Paul,R.L.Clarke  Canad. J. of Phys., v.31, p.267, 1953    2725 1451  167
31. M.Bormann et al. Journal de Physique, v.22, p.602, Oct. 1961  2725 1451  168
32. F.Gabbard, B.D.Kern  Phys. Rev., v.128, n.3, p.1276, 1962     2725 1451  169
33. J.M.F.Jeronymo et al. Nucl. Phys., v.47(1), p.157, July 1963  2725 1451  170
34. J.E.Strain, W.J.Ross  Report ORNL-3672, January 1965          2725 1451  171
35. M.Bormann  et al.  Nucl. Phys., v.63, p.438, March 1965       2725 1451  172
36. U.Garuska, J.Dresler, H.Malecki  Prog. Report INR-1773/I/PL/A,2725 1451  173
    p.16, September 1978                                          2725 1451  174
37. H.M.Agrawal, K.R.Zasadny, G.F.Knoll  Trans. Amer. Nucl. Soc., 2725 1451  175
    v.47, p.431, November 1984   save                             2725 1451  176
38. M.Berrada  Progress Report to the IAEA NDS on Research        2725 1451  177
    Contract -3311.R1/RB, 15 April 1984                           2725 1451  178
39. I.Garlea et al. Revue Roumaine de Physique, v.30, p.673, 1985 2725 1451  179
40. N.I.Molla et al.  Proc.of International Conference on Nuclear 2725 1451  180
    Data for Science and Technology, Gatlinburg, Tennessee, May   2725 1451  181
    9-13, 1994, v.2, pp.938-940                                   2725 1451  182
41. R.Doczi et al.  Nucl. Sci. Eng., v.129, p.164, June 1998      2725 1451  183
42. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2725 1451  184
    st's Meeting on Evaluation and Processing of Covariance Data, 2725 1451  185
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  2725 1451  186
43. S.A.Badikov et.al.  Preprint FEI-1686, Obninsk, 1985          2725 1451  187
44. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2725 1451  188
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              2725 1451  189
45. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        2725 1451  190
46. K.Kobayashi, I.Kimura  Report NEANDC(J)-61U, p.81, Sep. 1979  2725 1451  191
47. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 2725 1451  192
    Washington D.C., 25-28 April 1989, v.2, p.923                 2725 1451  193
48. W.Mannhart   Progress Report INDC(Ger)-045, pp.40-43, 1999    2725 1451  194
49. K.Kobayashi,I.Kimura,W.Mannhart  Nucl. Sci. Technology.,v.19, 2725 1451  195
    n.5, p.341, May 1982                                          2725 1451  196
50. W.Mannhart  Handbook on Nuclear Activation Data , IAEA        2725 1451  197
    Technical Report series No.273, p.413, 1987                   2725 1451  198
51. W.Mannhart  Validation of Differential Cross Sections with    2725 1451  199
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2725 1451  200
    September 2002                                                2725 1451  201
***************************************************************** 2725 1451  202
**********   End of (N,A) bibliographical component    ********** 2725 1451  203
***************************************************************** 2725 1451  204
  The Q values and threshold energies were updated prior to pro-  2725 1451  205
  cessing through the codes to comply with the values obtained    2725 1451  206
  using the NNDC calculation program which is based on the 1995   2725 1451  207
  Update to the Atomic mass Evaluation.                           2725 1451  208
***************************************************************** 2725 1451  209
 ***************** Program LINEAR (VERSION 2002-1) ***************2725 1451  210
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2725 1451  211
 Data Linearized to Within an Accuracy of .100000000 per-cent     2725 1451  212
 ***************** Program RECENT (VERSION 2002-1) ***************2725 1451  213
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2725 1451  214
 Data Linearized to within an Accuracy of .100000000 per-cent     2725 1451  215
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2725 1451  216
 Data Doppler Broadened to 300.000000 Kelvin                      2725 1451  217
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2725 1451  218
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2725 1451  219
 ***************** Program FIXUP (Version 2002-1) ****************2725 1451  220
 Corrected ZA/AWR in All Sections-----------------------------Yes 2725 1451  221
 Corrected Thresholds-----------------------------------------Yes 2725 1451  222
 Extended Cross Sections to 20 MeV----------------------------No  2725 1451  223
 Allow Cross Section Deletion---------------------------------No  2725 1451  224
 Allow Cross Section Reconstruction---------------------------No  2725 1451  225
 Make All Cross Sections Non-Negative-------------------------Yes 2725 1451  226
 Delete Energies Not in Ascending Order-----------------------Yes 2725 1451  227
 Deleted Duplicate Points-------------------------------------Yes 2725 1451  228
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2725 1451  229
 Check for Legal MF/MT Numbers--------------------------------Yes 2725 1451  230
 Allow Creation of Missing Sections---------------------------No  2725 1451  231
 Allow Insertion of Energy Points-----------------------------No  2725 1451  232
 Create Uniform Energy Grid-----------------------------------No  2725 1451  233
 Delete Section if Cross Section =0 at All Energies-----------Yes 2725 1451  234
 ***************** Program GROUPIE (VERSION 2002-1) **************2725 1451  235
 Unshielded Group Averages Using  640 Groups                      2725 1451  236
 Weighting Spectrum: Flat (Constant) Spectrum                     2725 1451  237
                                1        451        245          12725 1451  238
                                2        151          4          12725 1451  239
                                3         16         35          12725 1451  240
                                3        102        217          12725 1451  241
                                3        107         75          12725 1451  242
                               33         16         42          12725 1451  243
                               33        102         11          12725 1451  244
                               33        107        103          12725 1451  245
                                                                  2725 1  099999
                                                                  2725 0  0    0
 2.70590E+4 5.84269E+1          0          0          1          02725 2151    1
 2.70590E+4 1.00000E+0          0          0          1          02725 2151    2
 1.00000E-5 1.00000E+5          0          0          0          02725 2151    3
 3.50000E+0 6.67200E-1          0          0          0          02725 2151    4
                                                                  2725 2  099999
                                                                  2725 0  0    0
 2.70590E+4 5.84269E+1          0          0          0          02725 3 16    1
-1.04530E+7-1.04530E+7          0          0          1         952725 3 16    2
         95          1                                            2725 3 16    3
 10600000.0 .001438929 10700000.0 .007329788 10800000.0 .0135365962725 3 16    4
 10900000.0 .026794286 11000000.0 .047102857 11100000.0 .0674114292725 3 16    5
 11200000.0 .088045429 11300000.0 .110632000 11400000.0 .1335440002725 3 16    6
 11500000.0 .156456000 11600000.0 .179368000 11700000.0 .2030660002725 3 16    7
 11800000.0 .231480000 11900000.0 .260680000 12000000.0 .2898800002725 3 16    8
 12100000.0 .319080000 12200000.0 .348198750 12300000.0 .3768300002725 3 16    9
 12400000.0 .405380000 12500000.0 .433930000 12600000.0 .4624800002725 3 16   10
 12700000.0 .489566125 12800000.0 .507869000 12900000.0 .5247080002725 3 16   11
 13000000.0 .541547000 13100000.0 .558386000 13200000.0 .5752250002725 3 16   12
 13300000.0 .592064000 13400000.0 .608903000 13500000.0 .6257420002725 3 16   13
 13600000.0 .642581000 13700000.0 .658802125 13800000.0 .6713160002725 3 16   14
 13900000.0 .683212000 14000000.0 .695108000 14100000.0 .7087826252725 3 16   15
 14200000.0 .726805000 14300000.0 .744663875 14400000.0 .7545780002725 3 16   16
 14500000.0 .761242000 14600000.0 .767676500 14700000.0 .7735500002725 3 16   17
 14800000.0 .779190750 14900000.0 .780272000 15000000.0 .7794880002725 3 16   18
 15100000.0 .778704000 15200000.0 .777920000 15300000.0 .7771360002725 3 16   19
 15400000.0 .776352000 15500000.0 .777791000 15600000.0 .7814530002725 3 16   20
 15700000.0 .785115000 15800000.0 .788777000 15900000.0 .7924390002725 3 16   21
 16000000.0 .796101000 16100000.0 .799763000 16200000.0 .8034250002725 3 16   22
 16300000.0 .807087000 16400000.0 .810749000 16500000.0 .8140205002725 3 16   23
 16600000.0 .816901500 16700000.0 .819782500 16800000.0 .8226635002725 3 16   24
 16900000.0 .825544500 17000000.0 .828425500 17100000.0 .8313065002725 3 16   25
 17200000.0 .834187500 17300000.0 .837068500 17400000.0 .8399495002725 3 16   26
 17500000.0 .842123500 17600000.0 .843590500 17700000.0 .8450575002725 3 16   27
 17800000.0 .846524500 17900000.0 .847991500 18000000.0 .8494585002725 3 16   28
 18100000.0 .850925500 18200000.0 .852392500 18300000.0 .8538595002725 3 16   29
 18400000.0 .855326500 18500000.0 .857348000 18600000.0 .8599240002725 3 16   30
 18700000.0 .862500000 18800000.0 .865076000 18900000.0 .8676520002725 3 16   31
 19000000.0 .870228000 19100000.0 .872804000 19200000.0 .8753800002725 3 16   32
 19300000.0 .877956000 19400000.0 .880532000 19500000.0 .8801300002725 3 16   33
 19600000.0 .876750000 19700000.0 .873370000 19800000.0 .8699900002725 3 16   34
 19900000.0 .866610000 20000000.0 0.0                             2725 3 16   35
                                                                  2725 3  099999
 2.70590E+4 5.84269E+1          0          0          0          02725 3102    1
 7.49193E+6 7.49193E+6          0          0          1        6412725 3102    2
        641          1                                            2725 3102    3
 .000100000 584.185484 .000105000 570.563242 .000110000 557.6219562725 3102    4
 .000115000 545.696918 .000120000 531.756360 .000127500 516.2896652725 3102    5
 .000135000 502.158548 .000142500 489.172338 .000150000 475.1176622725 3102    6
 .000160000 460.476357 .000170000 447.154582 .000180000 434.9262022725 3102    7
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 7.542020-4 7.197360-4 6.783370-4 6.327650-4 5.850490-4 5.366280-4272533107   93
 8.380390-4 9.069060-4 9.497230-4 9.693530-4 9.700350-4 9.561740-4272533107   94
 9.317100-4 8.998770-4 8.631920-4 8.235440-4 1.015840-3 1.100660-3272533107   95
 1.162040-3 1.202680-3 1.226130-3 1.235970-3 1.235370-3 1.226980-3272533107   96
 1.212910-3 1.233620-3 1.346000-3 1.438180-3 1.512010-3 1.570060-3272533107   97
 1.614950-3 1.649110-3 1.674650-3 1.515040-3 1.666300-3 1.799460-3272533107   98
 1.915510-3 2.016160-3 2.103310-3 2.178850-3 1.880800-3 2.078470-3272533107   99
 2.258530-3 2.421410-3 2.568290-3 2.700660-3 2.343020-3 2.589960-3272533107  100
 2.818450-3 3.028720-3 3.221760-3 2.904570-3 3.199650-3 3.474650-3272533107  101
 3.729920-3 3.560920-3 3.900280-3 4.217700-3 4.302840-3 4.681140-3272533107  102
 5.118740-3                                                       272533107  103
                                                                  272533  099999
                                                                  2725 0  0    0
                                                                     0 0  0    0
 2.80580E+4 5.74376E+1          0          0         34         102825 1451    1
 0.0        0.0                 0          0          0          62825 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022825 1451    3
 3.00000E+2 0.0                 1          0        378          62825 1451    4
 28-Ni- 58 IRK-IJS/FEIEVAL-AUG99 EUR.JOINT COLLAB. K.I.Zolotarev  2825 1451    5
                      DIST-Feb2004                                2825 1451    6
----IRDF-2002         MATERIAL 2825                               2825 1451    7
-----INCIDENT NEUTRON DATA                                        2825 1451    8
------ENDF-6 FORMAT                                               2825 1451    9
                                                                  2825 1451   10
*****************************   JEFF-3.0   ***********************2825 1451   11
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2825 1451   12
DOSIMETRY                                                         2825 1451   13
******************************************************************2825 1451   14
 28-NI- 58 IRK-IJS    EVAL-AUG99 EUROPEAN JOINT COLLABORATION     2825 1451   15
                                                                  2825 1451   16
   DATA TAKEN FROM   :-   EFF-3.1 (DIST-AUG99 REV1-SEP00)         2825 1451   17
MF=3                                                              2825 1451   18
MT= 16 - (n,2n)                                                   2825 1451   19
                                                                  2825 1451   20
******************************************************************2825 1451   21
 28-Ni- 58 FEI        EVAL-Dec02 K.I.Zolotarev                    2825 1451   22
                      DIST-Jan03                                  2825 1451   23
----BROND-3           MATERIAL 2825                               2825 1451   24
-----INCIDENT NEUTRON DATA                                        2825 1451   25
------ENDF-6 FORMAT                                               2825 1451   26
***************************************************************** 2825 1451   27
------Russian Reactor Dosimetry File RRDF-2002                    2825 1451   28
***************************************************************** 2825 1451   29
Author  of evaluation: K.I.Zolotarev                              2825 1451   30
***************************************************************** 2825 1451   31
MF=3                                                              2825 1451   32
MT=103 - Ni58(n,p)Co58m+g reaction                                2825 1451   33
                                                                  2825 1451   34
***************************************************************** 2825 1451   35
******* Start of JEFF-3.0 (N,2N) bibliographical component ****** 2825 1451   36
***************************************************************** 2825 1451   37
*****************************   JEFF-3.0   ***********************2825 1451   38
 28-NI- 58 IRK-IJS    EVAL-AUG99 EUROPEAN JOINT COLLABORATION     2825 1451   39
                                                                  2825 1451   40
   DATA TAKEN FROM   :-   EFF-3.1 (DIST-AUG99 REV1-SEP00)         2825 1451   41
                                                                  2825 1451   42
******************************************************************2825 1451   43
Authors and Responsibilities:                                     2825 1451   44
S.Tagesen, H.Vonach and A.Wallner, I.R.K.:                        2825 1451   45
 - Complete evaluation of the cross sections including covariance 2825 1451   46
   matrices by generalized least squares cross section update     2825 1451   47
   code GLUCS (9, 10). The total cross section is evaluated in    2825 1451   48
   broad energy bins.                                             2825 1451   49
A.Trkov, I.J.S.:                                                  2825 1451   50
 - Final assembly of the file.                                    2825 1451   51
 - Consistency corrections (interp.law in MF6 starter file).      2825 1451   52
 - Implementation of the resonance fluctuations on the smooth     2825 1451   53
   newly evaluated cross sections.                                2825 1451   54
 - Preliminary data verification and benchmarking.                2825 1451   55
                                                                  2825 1451   56
Evaluation Details:                                               2825 1451   57
The Oak Ridge Ni-58 ENDF/B-VI Revision 1 evaluation (MAT 2825)    2825 1451   58
by Larson et.al.  was the chosen starter file. All neutron        2825 1451   59
cross sections above 810 keV were re-evaluated and include        2825 1451   60
covariance data. The following data sets were selected as         2825 1451   61
"priors":                                                         2825 1451   62
        MT16     IRDF-90  (evaluation Pavlik)(11)                 2825 1451   63
                                                                  2825 1451   64
Resonance Fluctuations in the Cross Sections:                     2825 1451   65
The cross sections below 810 keV are not affected by the re-      2825 1451   66
evaluation process. Above this energy, broad bin average total    2825 1451   67
cross section from the starter file was calculated. The bins      2825 1451   68
correspond to those used in the re-evaluation process. A smooth   2825 1451   69
cross section curve was generated, conserving the bin average     2825 1451   70
values. Fluctuations modulating function was defined as the       2825 1451   71
ratio of the original and the smoothed cross section. This        2825 1451   72
modulating function is applied on the re-evaluated smooth total   2825 1451   73
cross section and the inelastic cross sections.                   2825 1451   74
                                                                  2825 1451   75
The remaining comments are taken over from the starter file,      2825 1451   76
except for the sections referring to the data, which have been    2825 1451   77
superseeded. Modified sections are identified by the use of       2825 1451   78
lower case characters.                                            2825 1451   79
                                                                  2825 1451   80
******************************************************************2825 1451   81
 CAPTURE WIDTHS CORRECTED FOR 58.7 AND 439.52 KEV RESONANCES.     2825 1451   82
 THE ELASTIC TRANSFORMATION MATRIX WAS REMOVED.                   2825 1451   83
 FIXED TYPO IN MINIMUM ENERGY IN MF=6, MT=51                      2825 1451   84
******************************************************************2825 1451   85
                                                                  2825 1451   86
   THIS WORK EMPLOYED NUCLEAR MODEL CODES INCLUDING THE           2825 1451   87
DISTORTED WAVE BORN APPROXIMATION (DWBA) PROGRAM DWUCK (1)        2825 1451   88
AND THE HAUSER-FESHBACH CODE TNG (2,3,4).  THE TNG CODE PROVIDES  2825 1451   89
ENERGY AND ANGULAR DISTRIBUTIONS OF PARTICLES EMITTED IN THE      2825 1451   90
COMPOUND AND PRE-COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL2825 1451   91
REACTIONS, AND MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE 2825 1451   92
CONTENTS OF THIS EVALUATION AND EXTENSIVE COMPARISONS OF          2825 1451   93
CALCULATIONS WITH EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5).2825 1451   94
                                                                  2825 1451   95
----- DESCRIPTION OF FILES                                        2825 1451   96
(MF-MT)                                                           2825 1451   97
  1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS.         2825 1451   98
  3-16  (n,2n) cross sections were re-evaluated.                  2825 1451   99
--------------------------------------------------------------    2825 1451  100
                UNCERTAINTY FILES                                 2825 1451  101
        ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS       2825 1451  102
        REQUIRED BY ENDF/B-VI FORMATS                             2825 1451  103
        For all evaluated reactions full covariance matrices are  2825 1451  104
        given as calculated by the bayesian evaluation update code2825 1451  105
        GLUCS. This includes full inter-reaction covariances.     2825 1451  106
                                                                  2825 1451  107
 33-16  (N,2N) covariances from GLUCS.                            2825 1451  108
                                                                  2825 1451  109
 REFERENCES:                                                      2825 1451  110
(11) M. Wagner et al., Physics Data 13-5, Fachinformationszentrum 2825 1451  111
     Karlsruhe, 1990                                              2825 1451  112
***************************************************************** 2825 1451  113
*******  End of JEFF-3.0 (N,2N) bibliographical component ******* 2825 1451  114
***************************************************************** 2825 1451  115
***************************************************************** 2825 1451  116
*******   Start of RRDF (N,P) bibliographical component   ******* 2825 1451  117
***************************************************************** 2825 1451  118
 28-Ni- 58 FEI        EVAL-Dec02 K.I.Zolotarev                    2825 1451  119
                      DIST-Jan03                                  2825 1451  120
----BROND-3           MATERIAL 2825                               2825 1451  121
-----INCIDENT NEUTRON DATA                                        2825 1451  122
------ENDF-6 FORMAT                                               2825 1451  123
***************************************************************** 2825 1451  124
------Russian Reactor Dosimetry File RRDF-2002                    2825 1451  125
***************************************************************** 2825 1451  126
Author  of evaluation: K.I.Zolotarev                              2825 1451  127
***************************************************************** 2825 1451  128
MF=3                                                              2825 1451  129
MT=103 - Ni58(n,p)Co58m+g reaction                                2825 1451  130
-------------------------------------                             2825 1451  131
    Microscopic experimental data  [1-64]  were  analyzed in  the 2825 1451  132
process of preparation  of input data base  for the evaluation of 2825 1451  133
cross sections and their uncertainty  for the  Ni-58(n,p)Co-58m+g 2825 1451  134
reaction.  During this procedure all experimental data  if it was 2825 1451  135
possible were corrected to the new recommended cross section data 2825 1451  136
for monitor reactions used in the measurements and to the new re- 2825 1451  137
commended decay data.                                             2825 1451  138
    Excitation function for the  Ni-58(n,p)Co-58m+g  reaction  in 2825 1451  139
the energy region from threshold to 20 MeV was evaluated by means 2825 1451  140
of statistical analysis of experimental cross section data [1-41].2825 1451  141
    Special correction was done with experimental data [9], [12], 2825 1451  142
[13], [15], [16], [20], [23], [26], [34], [35]. Experimental data 2825 1451  143
of Decowski et al. [9] corresponding to the neutron energy region 2825 1451  144
12.42 - 17.08 MeV  were renormalized to the preliminary evaluated 2825 1451  145
cross section value at En=14.77 MeV. Original cross sections from 2825 1451  146
ref. [9] were multiplied to the correction factor Fc=0.53807 .    2825 1451  147
    Data of Paulsen and Widera [12] measured in the energy ranges 2825 1451  148
3.35 - 6.27 MeV and 12.8 - 16.4 MeV  were corrected to the preli- 2825 1451  149
minary evaluated cross section value at  6.3 MeV  and integral of 2825 1451  150
cross section  in the energy interval  14-15 MeV.  The correction 2825 1451  151
factors for the experimental data [12] were Fc=1.059 and Fc=1.058,2825 1451  152
respectively.                                                     2825 1451  153
    Data of  Smith and Meadows [13] measured  with using neutrons 2825 1451  154
from  D(d,n)He3 reaction were renormalized to the results of this 2825 1451  155
experiment obtained with  Li7(p,n)Be7 neutron source in the over- 2825 1451  156
lapping interval 5.398 - 5.870 MeV.  D(d,n)He3 data in the energy 2825 1451  157
range 5.398 - 9.897 MeV were increased to the factor Fc=1.083 .   2825 1451  158
    Data of Wu and Chou [15]  and  Husain and Hunt [20] were also 2825 1451  159
renormalized to the  Smith and Meadows  measurements  carried out 2825 1451  160
with  Li7(p,n)Be7  neutron source. Correction factors for experi- 2825 1451  161
mental data were Fc=1.04592 [15] and Fc=1.03634 [20].             2825 1451  162
    Cross sections measured  by Hudson et al. [16]  in the energy 2825 1451  163
range 13.3 - 17.10 MeV were corrected to Filatenkov et al. experi-2825 1451  164
mental data at 14.1 MeV [40], Fc=0.95367.                         2825 1451  165
    Experimental data of  Rondio et al. [23,26] were corrected to 2825 1451  166
the preliminary evaluated  Ni-58(n,p)Co-58m+g reaction cross sec- 2825 1451  167
tion integral in the energy interval 17.3 - 18.5 MeV (Fc=0.1889). 2825 1451  168
    Data of Yuan Junqian et al. [34]  and  Li Tingyan et al. [35] 2825 1451  169
were multiplied to the factors Fc=0.9000 and Fc=0.9259 , respec-  2825 1451  170
tively, using preliminary evaluated cross section integral in the 2825 1451  171
energy interval 13.6 - 14.6 MeV.                                  2825 1451  172
    Experimental cross section data [42-64] were rejected  due to 2825 1451  173
their discrepancy with the main bulk of experimental data [1-41]. 2825 1451  174
Data of Decowski et al. [9]  obtained in the neutron energy range 2825 1451  175
from 1.95 to 4.79 MeV  were rejected for the same reason.  In the 2825 1451  176
rejected experiments [42-43], [51-55], [57-60], [62-64] the cross 2825 1451  177
section values  were measured only  in a one  energy point in the 2825 1451  178
interval 14 - 15 MeV.                                             2825 1451  179
    Statistical analysis of input cross section data was carried  2825 1451  180
out by means of PADE-2 code [65].  Rational function was used as  2825 1451  181
the model function [66].                                          2825 1451  182
     U-235 thermal fission [67] and  Cf-252 spontaneous  fission  2825 1451  183
neutron spectra [68] averaged cross sections calculated from the  2825 1451  184
the evaluated  Ni-58(n,p)Co-58m+g  excitation function  are  the  2825 1451  185
following:                                                        2825 1451  186
                                                                  2825 1451  187
  2825 1451  188
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  2825 1451  189
  2825 1451  190
 U-235 neutron fission     107.44         108.9 +- 5.2    [69]  2825 1451  191
                                          106.0 +- 7.0    [70]  2825 1451  192
                                          108.5 +- 1.4    [71]  2825 1451  193
  2825 1451  194
 Cf-252 spont. fission     117.36         117.6 +- 1.5    [72]  2825 1451  195
                                          117.5 +- 1.53   [73]  2825 1451  196
  2825 1451  197
                                                                  2825 1451  198
MT=33                                                             2825 1451  199
MT=103 -(n,p) cross section cov. matrix                           2825 1451  200
---------------------------------------                           2825 1451  201
     Uncertainties in the evaluated excitation function  for  the 2825 1451  202
reaction Ni-58(n,p)Co-58m+g are given in the form of relative co- 2825 1451  203
variance matrix for the  37-neutron energy groups (LB=5). Covari- 2825 1451  204
ance matrix of uncertainties  was calculated simultaneously  with 2825 1451  205
recommended cross section data by means of PADE-2 code.           2825 1451  206
    Eigenvalues  of the  6-th digits  relative covariance matrix  2825 1451  207
given in the 33-file are the following:                           2825 1451  208
                                                                  2825 1451  209
    3.02525E-08    3.04415E-08    3.07179E-08    3.11702E-08      2825 1451  210
    3.17809E-08    3.24784E-08    3.36976E-08    3.53449E-08      2825 1451  211
    3.74027E-08    4.12908E-08    4.46423E-08    5.24310E-08      2825 1451  212
    5.88770E-08    7.22029E-08    8.98365E-08    1.06273E-07      2825 1451  213
    1.47057E-07    1.97171E-07    2.32636E-07    3.12653E-07      2825 1451  214
    4.31346E-07    5.83111E-07    7.69089E-07    9.84635E-07      2825 1451  215
    1.17764E-06    1.35691E-06    6.11687E-05    6.46368E-04      2825 1451  216
    7.13990E-04    1.20451E-03    1.41032E-03    1.54898E-03      2825 1451  217
    2.03298E-03    3.77118E-03    4.31020E-03    5.28282E-03      2825 1451  218
    3.31282E-02                                                   2825 1451  219
                                                                  2825 1451  220
References:                                                       2825 1451  221
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    M.Rahman et al. Nuclear Science and Applications, v.1, no.1,  2825 1451  310
    p.32, January 1989                                            2825 1451  311
60. K.Kobayashi, I.Kimura  Proc. of an Intern. Conf. on Nuclear   2825 1451  312
    Data for Science and Technology, 30 May - 3 June 1988, Mito,  2825 1451  313
    Japan, Saikon Publishing Co., LTD, pp.261-265, 1989           2825 1451  314
61. N.I.Molla et al.  Proc. of Int. Conf. on Nuclear Data for     2825 1451  315
    Science and Technology, Juelich, FRG, 13-17 May 1991, p. 355  2825 1451  316
62. A.Ercan et.al.  Proc. of an Intern. Conf. on Nuclear Data for 2825 1451  317
    Science and Technology, 13-17 May 1991, Julich, FRG, Springer-2825 1451  318
    Verlag, 1992                                                  2825 1451  319
63. I.Garlea et al. Rev. Roum. Phys., v.37, no.1, pp.19-25, 1992  2825 1451  320
64. L.I.Klochkova et al.  Vop. At. Nauki i Tekhn., Ser. Yadernye  2825 1451  321
    Konstanty, v.1, p.27, 1992                                    2825 1451  322
65. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          2825 1451  323
66. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 2825 1451  324
    st's Meeting on Evaluation and Processing of Covariance Data, 2825 1451  325
    Oak Ridge, USA, 1992, OECD, Paris, 1993, p.105                2825 1451  326
67. L.W.Weston et al.  Evaluated Neutron Data  for  Uranium-235,  2825 1451  327
    ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989    2825 1451  328
68. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        2825 1451  329
69. W.Mannhart  Proc. 5-th ASTM-EUR. Symp. on Reactor Dosimetry,  2825 1451  330
    Geesthacht, FRG, September 24-28, 1984, Vol.2, p.813, 1985    2825 1451  331
70. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 2825 1451  332
    Washington D.C., 25-28 April 1989, v.2, p.923                 2825 1451  333
71. W.Mannhart  Prog. Report INDC(Ger)-045, pp.40-43, June 1999   2825 1451  334
72. W.Mannhart  Handbook on Nuclear Activation Cross Sections ,   2825 1451  335
    IAEA Technical Report Ser. No.273, p.413, 1987                2825 1451  336
73. W.Mannhart  Validation of Differential Cross Sections with    2825 1451  337
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2825 1451  338
    September 2002                                                2825 1451  339
***************************************************************** 2825 1451  340
*******    End of RRDF (N,P) bibliographical component    ******* 2825 1451  341
***************************************************************** 2825 1451  342
 The Q values and threshold energies were updated prior to pro-   2825 1451  343
 cessing through the codes to comply with the values obtained     2825 1451  344
 using the NNDC calculation program which is based on the 1995    2825 1451  345
 Update to the Atomic mass Evaluation.                            2825 1451  346
                                                                  2825 1451  347
 Psuedo Threshold of 1.0E+5 changed to 4.0E+5 ev in MF/MT=3/103   2825 1451  348
 in original input file before processing through codes.          2825 1451  349
                                                                  2825 1451  350
 File 2 added to the pointwise file containing only the effective 2825 1451  351
 scattering radius with no resonance parameters given.            2825 1451  352
 Taken from ENDF/B-VI                                             2825 1451  353
***************************************************************** 2825 1451  354
 ***************** Program LINEAR (VERSION 2002-1) ***************2825 1451  355
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2825 1451  356
 Data Linearized to Within an Accuracy of .100000000 per-cent     2825 1451  357
 ***************** Program RECENT (VERSION 2002-1) ***************2825 1451  358
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2825 1451  359
 Data Linearized to within an Accuracy of .100000000 per-cent     2825 1451  360
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2825 1451  361
 Data Doppler Broadened to 300.000000 Kelvin                      2825 1451  362
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2825 1451  363
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2825 1451  364
 ***************** Program FIXUP (Version 2002-1) ****************2825 1451  365
 Corrected ZA/AWR in All Sections-----------------------------Yes 2825 1451  366
 Corrected Thresholds-----------------------------------------Yes 2825 1451  367
 Extended Cross Sections to 20 MeV----------------------------No  2825 1451  368
 Allow Cross Section Deletion---------------------------------No  2825 1451  369
 Allow Cross Section Reconstruction---------------------------No  2825 1451  370
 Make All Cross Sections Non-Negative-------------------------Yes 2825 1451  371
 Delete Energies Not in Ascending Order-----------------------Yes 2825 1451  372
 Deleted Duplicate Points-------------------------------------Yes 2825 1451  373
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2825 1451  374
 Check for Legal MF/MT Numbers--------------------------------Yes 2825 1451  375
 Allow Creation of Missing Sections---------------------------No  2825 1451  376
 Allow Insertion of Energy Points-----------------------------No  2825 1451  377
 Create Uniform Energy Grid-----------------------------------No  2825 1451  378
 Delete Section if Cross Section =0 at All Energies-----------Yes 2825 1451  379
 ***************** Program GROUPIE (VERSION 2002-1) **************2825 1451  380
 Unshielded Group Averages Using  640 Groups                      2825 1451  381
 Weighting Spectrum: Flat (Constant) Spectrum                     2825 1451  382
                                1        451        388          02825 1451  383
                                2        151          4          02825 1451  384
                                3         16         29          02825 1451  385
                                3        103         73          02825 1451  386
                               33         16         58          02825 1451  387
                               33        103        133          02825 1451  388
                                                                  2825 1  099999
                                                                  2825 0  0    0
 2.80580E+4 5.74380E+1          0          0          1          02825 2151    1
 2.805800+4 1.000000+0          0          0          1          02825 2151    2
 1.000000-5 8.120000+5          0          0          0          02825 2151    3
 0.000000+0 6.400000-1          0          0          0          02825 2151    4
                                                                  2825 2  099999
                                                                  2825 0  0    0
 2.80580E+4 5.74376E+1          0          0          0          02825 3 16    1
-1.22190E+7-1.22190E+7          0          0          1         772825 3 16    2
         77          1                                            2825 3 16    3
 12400000.0 .000186234 12500000.0 .000945261 12600000.0 .0017445372825 3 16    4
 12700000.0 .002543812 12800000.0 .003343087 12900000.0 .0041423622825 3 16    5
 13000000.0 .005363417 13100000.0 .007006250 13200000.0 .0086490832825 3 16    6
 13300000.0 .010291917 13400000.0 .011934750 13500000.0 .0135775832825 3 16    7
 13600000.0 .015483500 13700000.0 .017652500 13800000.0 .0198330002825 3 16    8
 13900000.0 .022025000 14000000.0 .024031250 14100000.0 .0258517502825 3 16    9
 14200000.0 .028017000 14300000.0 .030527000 14400000.0 .0327212502825 3 16   10
 14500000.0 .034599750 14600000.0 .036406500 14700000.0 .0381415002825 3 16   11
 14800000.0 .039815500 14900000.0 .041428500 15000000.0 .0430853002825 3 16   12
 15100000.0 .044785900 15200000.0 .046486500 15300000.0 .0481871002825 3 16   13
 15400000.0 .049887700 15500000.0 .051421600 15600000.0 .0527888002825 3 16   14
 15700000.0 .054156000 15800000.0 .055523200 15900000.0 .0568904002825 3 16   15
 16000000.0 .058126600 16100000.0 .059231800 16200000.0 .0603370002825 3 16   16
 16300000.0 .061442200 16400000.0 .062547400 16500000.0 .0634315002825 3 16   17
 16600000.0 .064094500 16700000.0 .064757500 16800000.0 .0654205002825 3 16   18
 16900000.0 .066083500 17000000.0 .066685900 17100000.0 .0672277002825 3 16   19
 17200000.0 .067769500 17300000.0 .068311300 17400000.0 .0688531002825 3 16   20
 17500000.0 .069477400 17600000.0 .070184200 17700000.0 .0708910002825 3 16   21
 17800000.0 .071597800 17900000.0 .072304600 18000000.0 .0730607002825 3 16   22
 18100000.0 .073866100 18200000.0 .074671500 18300000.0 .0754769002825 3 16   23
 18400000.0 .076282300 18500000.0 .076938600 18600000.0 .0774458002825 3 16   24
 18700000.0 .077953000 18800000.0 .078460200 18900000.0 .0789674002825 3 16   25
 19000000.0 .079474600 19100000.0 .079981800 19200000.0 .0804890002825 3 16   26
 19300000.0 .080996200 19400000.0 .081503400 19500000.0 .0820106002825 3 16   27
 19600000.0 .082517800 19700000.0 .083025000 19800000.0 .0835322002825 3 16   28
 19900000.0 .084039400 20000000.0 0.0                             2825 3 16   29
                                                                  2825 3  099999
 2.80580E+4 5.74376E+1          0          0          0          02825 3103    1
 4.00800E+5 4.00800E+5          0          0          1        2102825 3103    2
        210          1                                            2825 3103    3
 400000.000 9.79220E-8 425000.000 2.93766E-7 450000.000 4.89610E-72825 3103    4
 475000.000 6.85454E-7 500000.000 8.96305E-7 525000.000 1.12216E-62825 3103    5
 550000.000 3.02637E-6 575000.000 6.60892E-6 600000.000 1.37449E-52825 3103    6
 630000.000 2.44342E-5 660000.000 3.51235E-5 690000.000 5.23130E-52825 3103    7
 720000.000 9.72844E-5 760000.000 .000150537 800000.000 .0002255822825 3103    8
 840000.000 .000322417 880000.000 .000426118 920000.000 .0005710122825 3103    9
 960000.000 .000722772 1000000.00 .001548276 1100000.00 .0033102152825 3103   10
 1200000.00 .005065710 1300000.00 .006936165 1400000.00 .0096017702825 3103   11
 1500000.00 .013139050 1600000.00 .017657450 1700000.00 .0232753002825 3103   12
 1800000.00 .030101100 1900000.00 .038220650 2000000.00 .0476866002825 3103   13
 2100000.00 .058510800 2200000.00 .070660150 2300000.00 .0840569002825 3103   14
 2400000.00 .098583350 2500000.00 .114089500 2600000.00 .1304045002825 3103   15
 2700000.00 .147348500 2800000.00 .164823000 2900000.00 .1825590002825 3103   16
 3000000.00 .200295000 3100000.00 .217979667 3200000.00 .2356130002825 3103   17
 3300000.00 .253246333 3400000.00 .270576000 3500000.00 .2876020002825 3103   18
 3600000.00 .304303250 3700000.00 .320679750 3800000.00 .3367052502825 3103   19
 3900000.00 .352379750 4000000.00 .367603833 4100000.00 .3823775002825 3103   20
 4200000.00 .397151167 4300000.00 .411373500 4400000.00 .4250445002825 3103   21
 4500000.00 .438715500 4600000.00 .451810167 4700000.00 .4643285002825 3103   22
 4800000.00 .476846833 4900000.00 .488749000 5000000.00 .5000350002825 3103   23
 5100000.00 .511321000 5200000.00 .521945833 5300000.00 .5319095002825 3103   24
 5400000.00 .541873167 5500000.00 .551139667 5600000.00 .5597090002825 3103   25
 5700000.00 .568278333 5800000.00 .576133500 5900000.00 .5832745002825 3103   26
 6000000.00 .590415500 6100000.00 .596852333 6200000.00 .6025850002825 3103   27
 6300000.00 .608317667 6400000.00 .613383500 6500000.00 .6177825002825 3103   28
 6600000.00 .622181500 6700000.00 .625975500 6800000.00 .6291645002825 3103   29
 6900000.00 .632353500 7000000.00 .634940750 7100000.00 .6369262502825 3103   30
 7200000.00 .638911750 7300000.00 .640897250 7400000.00 .6423411252825 3103   31
 7500000.00 .643243375 7600000.00 .644145625 7700000.00 .6450478752825 3103   32
 7800000.00 .645603000 7900000.00 .645811000 8000000.00 .6460190002825 3103   33
 8100000.00 .645924143 8200000.00 .645526429 8300000.00 .6451287142825 3103   34
 8400000.00 .644731000 8500000.00 .644333286 8600000.00 .6439355712825 3103   35
 8700000.00 .643537857 8800000.00 .642884150 8900000.00 .6419744502825 3103   36
 9000000.00 .641064750 9100000.00 .640155050 9200000.00 .6392453502825 3103   37
 9300000.00 .638335650 9400000.00 .637425950 9500000.00 .6365162502825 3103   38
 9600000.00 .635606550 9700000.00 .634696850 9800000.00 .6335150002825 3103   39
 9900000.00 .632061000 10000000.0 .630607000 10100000.0 .6291530002825 3103   40
 10200000.0 .627699000 10300000.0 .626245000 10400000.0 .6244170002825 3103   41
 10500000.0 .622215000 10600000.0 .620013000 10700000.0 .6178110002825 3103   42
 10800000.0 .615119750 10900000.0 .611939250 11000000.0 .6087587502825 3103   43
 11100000.0 .605578250 11200000.0 .601828167 11300000.0 .5975085002825 3103   44
 11400000.0 .593188833 11500000.0 .588287833 11600000.0 .5828055002825 3103   45
 11700000.0 .577323167 11800000.0 .571210167 11900000.0 .5644665002825 3103   46
 12000000.0 .557722833 12100000.0 .550347833 12200000.0 .5423415002825 3103   47
 12300000.0 .534335167 12400000.0 .525752833 12500000.0 .5165945002825 3103   48
 12600000.0 .507436167 12700000.0 .497812167 12800000.0 .4877225002825 3103   49
 12900000.0 .477632833 13000000.0 .467156167 13100000.0 .4562925002825 3103   50
 13200000.0 .445428833 13300000.0 .434565167 13400000.0 .4237015002825 3103   51
 13500000.0 .412837833 13600000.0 .401979300 13700000.0 .3911259002825 3103   52
 13800000.0 .380272500 13900000.0 .369419100 14000000.0 .3585657002825 3103   53
 14100000.0 .348010000 14200000.0 .337752000 14300000.0 .3274940002825 3103   54
 14400000.0 .317574667 14500000.0 .307994000 14600000.0 .2984133332825 3103   55
 14700000.0 .289222833 14800000.0 .280422500 14900000.0 .2716221672825 3103   56
 15000000.0 .263164250 15100000.0 .255048750 15200000.0 .2472077502825 3103   57
 15300000.0 .239641250 15400000.0 .232344500 15500000.0 .2253175002825 3103   58
 15600000.0 .218550250 15700000.0 .212042750 15800000.0 .2057830002825 3103   59
 15900000.0 .199771000 16000000.0 .193992250 16100000.0 .1884467502825 3103   60
 16200000.0 .183119500 16300000.0 .178010500 16400000.0 .1731042502825 3103   61
 16500000.0 .168400750 16600000.0 .163884500 16700000.0 .1595555002825 3103   62
 16800000.0 .155398500 16900000.0 .151413500 17000000.0 .1475865002825 3103   63
 17100000.0 .143917500 17200000.0 .140426333 17300000.0 .1371130002825 3103   64
 17400000.0 .133799667 17500000.0 .130675333 17600000.0 .1277400002825 3103   65
 17700000.0 .124804667 17800000.0 .122033500 17900000.0 .1194265002825 3103   66
 18000000.0 .116819500 18100000.0 .114355167 18200000.0 .1120335002825 3103   67
 18300000.0 .109711833 18400000.0 .107514000 18500000.0 .1054400002825 3103   68
 18600000.0 .103366000 18700000.0 .101399883 18800000.0 .0995416502825 3103   69
 18900000.0 .097683417 19000000.0 .095918850 19100000.0 .0942479502825 3103   70
 19200000.0 .092577050 19300000.0 .090987867 19400000.0 .0894804002825 3103   71
 19500000.0 .087972933 19600000.0 .086536900 19700000.0 .0851723002825 3103   72
 19800000.0 .083807700 19900000.0 .082486000 20000000.0 0.0       2825 3103   73
                                                                  2825 3  099999
                                                                  2825 0  0    0
 2.80580E+4 5.74376E+1          0          0          0          1282533 16    1
 0.000000+0 0.000000+0          0         16          0          2282533 16    2
 0.000000+0 0.000000+0          1          5        276         23282533 16    3
 1.000000-5 1.240000+7 1.300000+7 1.330000+7 1.360000+7 1.380000+7282533 16    4
 1.400000+7 1.420000+7 1.440000+7 1.460000+7 1.480000+7 1.500000+7282533 16    5
 1.550000+7 1.600000+7 1.650000+7 1.700000+7 1.750000+7 1.800000+7282533 16    6
 1.850000+7 1.900000+7 1.950000+7 2.000000+7 2.050000+7 0.000000+0282533 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533 16   10
 0.000000+0 0.000000+0 0.000000+0 3.100000-2 0.000000+0 0.000000+0282533 16   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533 16   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533 16   13
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533 16   14
 3.100000-2 2.499700-3 1.202800-3 3.854600-4 3.688600-4-1.315700-7282533 16   15
 2.889200-4 7.170200-4 1.679500-4 4.961500-3 4.961600-3 2.552100-3282533 16   16
 4.506600-3 2.783800-3 2.217500-3 3.175000-3 3.175100-3 1.902700-3282533 16   17
 1.902900-3 1.902800-3 4.394400-3 3.875100-4 2.453900-4 2.249400-4282533 16   18
 1.616300-4 2.006300-4 1.464200-4 1.204400-4 9.579200-4 9.579300-4282533 16   19
 4.504900-4 3.928800-4 4.505200-4 2.721500-4 3.523400-4 3.523500-4282533 16   20
 4.008700-4 4.008800-4 4.008800-4 1.259800-3 3.409600-4 1.906600-4282533 16   21
 2.078300-4 2.558800-4 2.034100-4 1.421000-4 3.054900-4 3.055000-4282533 16   22
 1.520100-4 2.750900-4 1.697300-4 1.330500-4 1.934500-4 1.934500-4282533 16   23
 1.020700-4 1.020800-4 1.020800-4 4.959800-4 1.152200-4 1.369000-4282533 16   24
 1.649600-4 1.159500-4 9.200400-5 7.646700-5 7.646600-5 4.067600-5282533 16   25
 6.060400-5 3.777300-5 3.362600-5 4.319600-5 4.319500-5 4.900500-5282533 16   26
 4.900600-5 4.900700-5 3.183000-4 6.197500-5 8.705400-5 8.384700-5282533 16   27
 5.124500-5 9.588500-5 9.589000-5 5.886800-5 9.732400-5 7.520900-5282533 16   28
 6.884600-5 6.844900-5 6.845300-5 7.807800-5 7.807700-5 7.807300-5282533 16   29
 2.435700-4 1.044600-4 6.287800-5 5.780500-5 6.012500-5 6.012500-5282533 16   30
 1.960200-5-2.456400-8 2.185800-5-1.205100-8-1.579500-8-1.579400-8282533 16   31
-1.414000-8-1.012200-8-9.936400-9 3.063700-4 8.538600-5 6.975700-5282533 16   32
 5.730500-5 5.730600-5 3.048300-5 4.542200-5 2.831200-5 2.520600-5282533 16   33
 3.237600-5 3.237600-5 3.672900-5 3.673100-5 3.673100-5 3.977300-4282533 16   34
 6.808000-5 2.313200-4 2.313200-4 1.293200-4 1.935000-4 1.510500-4282533 16   35
 1.196300-4 1.763700-4 1.763700-4 9.037600-5 9.038400-5 9.038300-5282533 16   36
 1.856200-4 3.601800-5 3.601900-5 1.772200-5 2.640500-5 1.645600-5282533 16   37
 1.464500-5 1.881700-5 1.881700-5 2.135100-5 2.135200-5 2.135300-5282533 16   38
 3.655000-3 2.377600-3 1.123500-3 1.208700-3 1.264000-3 7.980900-4282533 16   39
 1.149200-3 1.149200-3 7.227800-4 7.228000-4 7.228100-4 3.655000-3282533 16   40
 1.123500-3 1.208700-3 1.264000-3 7.981000-4 1.149200-3 1.149200-3282533 16   41
 7.227900-4 7.228000-4 7.228200-4 1.388700-3 6.106100-4 6.826200-4282533 16   42
 4.888500-4 6.928900-4 6.929200-4 5.040800-4 5.040700-4 5.040900-4282533 16   43
 2.601400-3 8.596000-4 8.136900-4 8.214900-4 8.214800-4 4.953700-4282533 16   44
 4.954100-4 4.954000-4 1.515000-3 6.041800-4 8.807200-4 8.807300-4282533 16   45
 6.141200-4 6.141600-4 6.141700-4 9.583900-4 6.510600-4 6.510600-4282533 16   46
 5.727100-4 5.727200-4 5.727100-4 1.860900-3 1.135800-3 7.534700-4282533 16   47
 7.535000-4 7.534900-4 1.860900-3 7.534800-4 7.534900-4 7.535000-4282533 16   48
 1.748000-3 1.066900-3 1.067000-3 1.748200-3 1.699800-3 1.747100-3282533 16   49
 0.000000+0 0.000000+0          0          8         46         23282533 16   50
 1.000000-5 0.000000+0 1.241000+7 0.000000+0 1.300000+7 6.40170-10282533 16   51
 1.330000+7 3.94500-10 1.360000+7 2.61460-10 1.380000+7 1.74300-10282533 16   52
 1.400000+7 1.70330-10 1.420000+7 1.74620-10 1.440000+7 3.09770-10282533 16   53
 1.460000+7 5.02850-10 1.480000+7 2.82740-10 1.500000+7 6.526300-9282533 16   54
 1.550000+7 9.418600-9 1.600000+7 4.607900-9 1.650000+7 1.036800-8282533 16   55
 1.700000+7 6.689100-9 1.750000+7 4.583900-9 1.800000+7 9.833900-9282533 16   56
 1.850000+7 1.095400-8 1.900000+7 1.098100-8 1.950000+7 1.169400-8282533 16   57
 2.000000+7 1.242600-8 2.050000+7 0.000000+0                      282533 16   58
                                                                  282533  099999
 2.80580E+4 5.74376E+1          0          0          0          1282533103    1
 0.000000+0 0.000000+0          0        103          0          1282533103    2
 0.000000+0 0.000000+0          1          5        780         39282533103    3
 1.000000-5 4.000000+5 1.500000+6 2.000000+6 2.500000+6 3.000000+6282533103    4
 3.500000+6 4.000000+6 4.500000+6 5.000000+6 5.500000+6 6.000000+6282533103    5
 6.500000+6 7.000000+6 7.500000+6 8.000000+6 8.500000+6 9.000000+6282533103    6
 9.500000+6 1.000000+7 1.050000+7 1.100000+7 1.150000+7 1.200000+7282533103    7
 1.250000+7 1.300000+7 1.350000+7 1.400000+7 1.450000+7 1.500000+7282533103    8
 1.550000+7 1.600000+7 1.650000+7 1.700000+7 1.750000+7 1.800000+7282533103    9
 1.850000+7 1.900000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0282533103   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533103   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533103   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533103   13
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533103   14
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0282533103   15
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 4.567480-3282533103   16
 1.178090-3 2.763340-4 2.251660-4 2.958890-4 2.662330-4 1.801580-4282533103   17
 1.091590-4 8.176260-5 9.244080-5 1.214690-4 1.491550-4 1.631620-4282533103   18
 1.601880-4 1.441130-4 1.227220-4 1.044330-4 9.561920-5 9.862530-5282533103   19
 1.106150-4 1.237940-4 1.278500-4 1.147210-4 8.380920-5 4.392650-5282533103   20
 9.698450-6-5.391860-6 5.499130-6 4.137470-5 9.563040-5 1.593670-4282533103   21
 2.240280-4 2.828400-4 3.312710-4 3.668430-4 3.887380-4 3.954750-4282533103   22
 1.003710-3 4.567020-4 1.819430-4 1.519580-4 2.072620-4 2.394060-4282533103   23
 2.259820-4 1.856030-4 1.437150-4 1.179490-4 1.144000-4 1.294700-4282533103   24
 1.541100-4 1.781630-4 1.935090-4 1.957480-4 1.846580-4 1.637450-4282533103   25
 1.389510-4 1.165140-4 1.002930-4 8.972690-5 8.017330-5 6.623010-5282533103   26
 4.612440-5 2.388530-5 7.914930-6 7.509340-6 2.979770-5 7.829020-5282533103   27
 1.529580-4 2.511390-4 3.686270-4 5.006530-4 6.425250-4 8.617720-4282533103   28
 4.686930-4 3.598500-4 2.454300-4 1.751080-4 1.485090-4 1.488850-4282533103   29
 1.615390-4 1.768020-4 1.890720-4 1.957630-4 1.965480-4 1.926850-4282533103   30
 1.863350-4 1.799310-4 1.755750-4 1.744380-4 1.761340-4 1.782190-4282533103   31
 1.762210-4 1.647870-4 1.402290-4 1.035290-4 6.169210-5 2.584340-5282533103   32
 6.998090-6 1.227500-5 4.351170-5 9.813280-5 1.709930-4 2.561150-4282533103   33
 3.478690-4 4.415720-4 5.336810-4 6.217340-4 7.406080-4 4.698480-4282533103   34
 4.261510-4 3.105910-4 2.084990-4 1.530770-4 1.414180-4 1.567140-4282533103   35
 1.808120-4 2.001940-4 2.080530-4 2.037870-4 1.910920-4 1.756680-4282533103   36
 1.631630-4 1.575100-4 1.596250-4 1.665770-4 1.717430-4 1.667020-4282533103   37
 1.451310-4 1.072230-4 6.151530-5 2.203050-5 2.289250-6 1.025870-5282533103   38
 4.684130-5 1.074370-4 1.846640-4 2.707070-4 3.587670-4 4.436710-4282533103   39
 5.219210-4 5.914870-4 6.755440-4 5.170950-4 4.878640-4 3.941380-4282533103   40
 2.906260-4 2.081330-4 1.574460-4 1.367100-4 1.374010-4 1.489810-4282533103   41
 1.621920-4 1.708060-4 1.720450-4 1.661260-4 1.553290-4 1.428380-4282533103   42
 1.314040-4 1.220480-4 1.132700-4 1.015920-4 8.378250-5 5.972660-5282533103   43
 3.385720-5 1.387210-5 7.716430-6 2.090880-5 5.544840-5 1.101620-4282533103   44
 1.817660-4 2.659880-4 3.584410-4 4.551630-4 5.528810-4 6.935630-4282533103   45
 5.768110-4 5.531400-4 4.556030-4 3.323940-4 2.207550-4 1.417480-4282533103   46
 1.011220-4 9.323110-5 1.062830-4 1.272180-4 1.451270-4 1.530470-4282533103   47
 1.484980-4 1.331520-4 1.117920-4 9.048050-5 7.406550-5 6.387610-5282533103   48
 5.713620-5 4.909770-5 3.676990-5 2.149920-5 8.674810-6 5.318290-6282533103   49
 1.751250-5 4.888850-5 1.003540-4 1.706000-4 2.568760-4 3.557620-4282533103   50
 4.637120-4 6.333340-4 6.069070-4 5.605150-4 4.534650-4 3.278320-4282533103   51
 2.158140-4 1.354730-4 9.141260-5 7.842730-5 8.615350-5 1.031270-4282533103   52
 1.195210-4 1.286180-4 1.273560-4 1.162180-4 9.845830-5 7.863670-5282533103   53
 6.065940-5 4.622520-5 3.474380-5 2.489180-5 1.654910-5 1.161150-5282533103   54
 1.335700-5 2.517250-5 4.948540-5 8.730490-5 1.382790-4 2.010270-4282533103   55
 2.735760-4 3.536950-4 4.817800-4 5.812910-4 5.312480-4 4.377140-4282533103   56
 3.288570-4 2.274940-4 1.481040-4 9.672000-5 7.264260-5 7.081360-5282533103   57
 8.390600-5 1.038060-4 1.225950-4 1.333900-4 1.313770-4 1.150770-4282533103   58
 8.728570-5 5.472140-5 2.582750-5 7.650840-6 3.665640-6 1.362650-5282533103   59
 3.491240-5 6.412560-5 9.816150-5 1.346460-4 1.719590-4 2.090840-4282533103   60
 2.454320-4 2.806830-4 3.303550-4 5.509690-4 5.154950-4 4.391610-4282533103   61
 3.415510-4 2.425000-4 1.581420-4 9.888940-5 6.904830-5 6.730480-5282533103   62
 8.747470-5 1.193440-4 1.499790-4 1.661890-4 1.585030-4 1.256480-4282533103   63
 7.668980-5 2.811230-5-3.501070-6-8.510460-6 1.331180-5 5.508020-5282533103   64
 1.069860-4 1.597770-4 2.065590-4 2.431800-4 2.678620-4 2.805190-4282533103   65
 2.821410-4 2.667540-4 5.417870-4 5.136820-4 4.421840-4 3.463000-4282533103   66
 2.471180-4 1.628990-4 1.061840-4 8.253620-5 9.022130-5 1.204470-4282533103   67
 1.584500-4 1.863210-4 1.883670-4 1.580330-4 1.027010-4 4.182840-5282533103   68
-1.978330-6-1.327090-5 1.116700-5 6.402690-5 1.326760-4 2.041440-4282533103   69
 2.680810-4 3.177620-4 3.498570-4 3.636240-4 3.600870-4 3.260650-4282533103   70
 5.356030-4 5.047340-4 4.339530-4 3.427590-4 2.515430-4 1.772730-4282533103   71
 1.309670-4 1.163850-4 1.294420-4 1.584730-4 1.862670-4 1.949470-4282533103   72
 1.733930-4 1.238480-4 6.254270-5 1.232750-5-8.083160-6 8.890820-6282533103   73
 5.948470-5 1.328500-4 2.160810-4 2.977160-4 3.693570-4 4.259120-4282533103   74
 4.650730-4 4.866190-4 4.870360-4 5.190510-4 4.882560-4 4.249420-4282533103   75
 3.458300-4 2.676380-4 2.040560-4 1.637790-4 1.491530-4 1.553460-4282533103   76
 1.707500-4 1.798490-4 1.691530-4 1.342560-4 8.344380-5 3.432480-5282533103   77
 5.388940-6 8.354180-6 4.544650-5 1.112280-4 1.962950-4 2.905760-4282533103   78
 3.853630-4 4.741820-4 5.528270-4 6.190620-4 6.913430-4 5.024060-4282533103   79
 4.788270-4 4.267050-4 3.585150-4 2.874830-4 2.254110-4 1.808090-4282533103   80
 1.570670-4 1.510140-4 1.530260-4 1.501600-4 1.322530-4 9.798390-5282533103   81
 5.640470-5 2.258470-5 1.070060-5 2.911650-5 7.923250-5 1.570580-4282533103   82
 2.556770-4 3.673960-4 4.851380-4 6.031250-4 7.170790-4 8.712440-4282533103   83
 4.970580-4 4.795620-4 4.324380-4 3.657970-4 2.920140-4 2.237100-4282533103   84
 1.713170-4 1.402170-4 1.283050-4 1.259800-4 1.202720-4 1.019710-4282533103   85
 7.128330-5 3.787990-5 1.585420-5 1.766380-5 5.050340-5 1.157090-4282533103   86
 2.100860-4 3.278250-4 4.621730-4 6.066060-4 7.554590-4 9.737830-4282533103   87
 4.965710-4 4.768580-4 4.259810-4 3.542670-4 2.752360-4 2.031230-4282533103   88
 1.494550-4 1.191020-4 1.078110-4 1.038920-4 9.468250-5 7.415140-5282533103   89
 4.629310-5 2.249660-5 1.582900-5 3.625710-5 8.855090-5 1.725350-4282533103   90
 2.844970-4 4.187960-4 5.692020-4 7.297510-4 9.749350-4 4.857170-4282533103   91
 4.593680-4 4.041610-4 3.309560-4 2.534110-4 1.850300-4 1.352320-4282533103   92
 1.058290-4 9.053390-5 7.906960-5 6.388380-5 4.475090-5 2.842960-5282533103   93
 2.474100-5 4.238370-5 8.649170-5 1.581960-4 2.554100-4 3.740190-4282533103   94
 5.090310-4 6.553620-4 8.830400-4 4.622530-4 4.355670-4 3.846720-4282533103   95
 3.182150-4 2.468290-4 1.807690-4 1.271380-4 8.806000-5 6.133630-5282533103   96
 4.348530-5 3.294650-5 3.123000-5 4.181120-5 6.821470-5 1.125520-4282533103   97
 1.750150-4 2.540930-4 3.471210-4 4.509020-4 5.621480-4 7.341490-4282533103   98
 4.443900-4 4.285000-4 3.883860-4 3.274380-4 2.526150-4 1.740560-4282533103   99
 1.032440-4 5.000760-5 1.996620-5 1.392060-5 2.917560-5 6.150500-5282533103  100
 1.066340-4 1.608980-4 2.213640-4 2.857300-4 3.521810-4 4.192940-4282533103  101
 4.859520-4 5.816950-4 4.533230-4 4.499330-4 4.120140-4 3.396280-4282533103  102
 2.425640-4 1.399160-4 5.435630-5 3.576710-6-5.659410-6 2.242670-5282533103  103
 7.696180-5 1.454850-4 2.173370-4 2.849970-4 3.440510-4 3.925320-4282533103  104
 4.301430-4 4.575930-4 4.813510-4 4.857840-4 4.796520-4 4.229260-4282533103  105
 3.212120-4 1.967440-4 8.186660-5 5.950200-6-1.591330-5 1.429150-5282533103  106
 8.259810-5 1.707280-4 2.620060-4 3.441990-4 4.099680-4 4.560900-4282533103  107
 4.822470-4 4.899470-4 4.712900-4 5.075800-4 4.787570-4 3.916490-4282533103  108
 2.653020-4 1.347580-4 3.667320-5-5.566650-6 1.196800-5 7.748840-5282533103  109
 1.717390-4 2.753360-4 3.729060-4 4.543540-4 5.144220-4 5.515150-4282533103  110
 5.665130-4 5.513000-4 4.853190-4 4.324480-4 3.299840-4 2.066050-4282533103  111
 9.851580-5 3.426120-5 2.566870-5 6.833550-5 1.479640-4 2.473420-4282533103  112
 3.510700-4 4.476680-4 5.298930-4 5.940640-4 6.391730-4 6.707940-4282533103  113
 4.268960-4 3.717220-4 2.815670-4 1.833800-4 1.050470-4 6.517590-5282533103  114
 6.955450-5 1.135560-4 1.869020-4 2.778930-4 3.760410-4 4.732300-4282533103  115
 5.638770-4 6.446410-4 7.413690-4 3.756610-4 3.387300-4 2.724920-4282533103  116
 1.974450-4 1.345130-4 9.832300-5 9.510360-5 1.240620-4 1.800840-4282533103  117
 2.562310-4 3.454750-4 4.416530-4 5.398550-4 6.807700-4 3.609990-4282533103  118
 3.428820-4 2.928950-4 2.278710-4 1.658530-4 1.206730-4 1.000320-4282533103  119
 1.060900-4 1.371230-4 1.892260-4 2.576610-4 3.377130-4 4.689640-4282533103  120
 3.773120-4 3.706070-4 3.302750-4 2.703650-4 2.058530-4 1.486660-4282533103  121
 1.063320-4 8.229690-5 7.695740-5 8.879390-5 1.152710-4 1.761240-4282533103  122
 4.157570-4 4.230810-4 3.969360-4 3.463240-4 2.815830-4 2.118020-4282533103  123
 1.437810-4 8.194610-5 2.873500-5-1.490280-5-6.107470-5 4.907200-4282533103  124
 5.238500-4 5.211570-4 4.859640-4 4.245560-4 3.440740-4 2.512660-4282533103  125
 1.518550-4 5.033710-5-9.636020-5 6.307180-4 7.025830-4 7.333670-4282533103  126
 7.226360-4 6.745020-4 5.953670-4 4.923350-4 3.722470-4 1.753660-4282533103  127
 8.655530-4 9.914960-4 1.072120-3 1.105210-3 1.093810-3 1.043780-3282533103  128
 9.621740-4 7.967120-4 1.233200-3 1.438380-3 1.597930-3 1.708340-3282533103  129
 1.771340-3 1.791690-3 1.753320-3 1.793410-3 2.115770-3 2.395310-3282533103  130
 2.626540-3 2.809320-3 2.992600-3 2.629110-3 3.114210-3 3.559090-3282533103  131
 3.955790-3 4.443820-3 3.832780-3 4.524150-3 5.174450-3 6.033490-3282533103  132
 5.486660-3 6.417000-3 7.695010-3 7.646890-3 9.373270-3 1.179240-2282533103  133
                                                                  282533  099999
                                                                  2825 0  0    0
                                                                     0 0  0    0
 2.80600E+4 5.94159E+1          0          0         34         102831 1451    1
 0.0        0.0                 0          0          0          62831 1451    2
 1.00000E+0 1.50000E+8          0          0         10       20022831 1451    3
 3.00000E+2 0.0                 1          0        395          42831 1451    4
 28-Ni- 60  LANL,ORNL EVAL-SEP97 S.CHIBA,M.B.CHADWICK,LARSON      2831 1451    5
                      DIST-Feb2004                                2831 1451    6
----IRDF-2002         MATERIAL 2831                               2831 1451    7
-----INCIDENT NEUTRON DATA                                        2831 1451    8
------ENDF-6 FORMAT                                               2831 1451    9
                                                                  2831 1451   10
******************************************************************2831 1451   11
----ENDF/B-VI         MATERIAL 2831         REVISION 3            2831 1451   12
 Ch97,Ch99            DIST-SEP 1 REV3-                 20010926   2831 1451   13
                                                                  2831 1451   14
 ENDF/B-VI MOD 4 Revision, June 2000, S.C. Frankle, R.C. Reedy,   2831 1451   15
                 P.G. Young (LANL)                                2831 1451   16
                                                                  2831 1451   17
 The secondary gamma-ray spectrum for radiative capture (MF 12,   2831 1451   18
 MT 102) has been updated for new experimental data at incident   2831 1451   19
 neutron energies up to 1 keV.                                    2831 1451   20
 The Q-value for radiative capture was also updated in File 3.    2831 1451   21
 Details of these changes are described in Frankel et al. [Fr01]. 2831 1451   22
                                                                  2831 1451   23
******************************************************************2831 1451   24
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2831 1451   25
DOSIMETRY                                                         2831 1451   26
******************************************************************2831 1451   27
                                                                  2831 1451   28
  ENDF/B-VI MOD 3 Evaluation, September 1997, S. Chiba,           2831 1451   29
                  M.B. Chadwick, P.G. Young (LANL), and           2831 1451   30
                  A.J. Koning (ECN)                               2831 1451   31
                                                                  2831 1451   32
 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code     2831 1451   33
   in cooperation with ECN Petten.                                2831 1451   34
                                                                  2831 1451   35
   This evaluation provides a complete representation of the      2831 1451   36
 nuclear data needed for transport, damage, heating,              2831 1451   37
 radioactivity, and shielding applications over the incident      2831 1451   38
 neutron energy range from 1.0E-11 to 150 MeV.  The discussion    2831 1451   39
 here is divided into the region below and above 20 MeV.          2831 1451   40
                                                                  2831 1451   41
INCIDENT NEUTRON ENERGIES < 20 MeV                                2831 1451   42
                                                                  2831 1451   43
  Below 20 MeV the evaluation is based completely on the ENDF/B-  2831 1451   44
VI.5(Rev1,Release 2) evaluation by Larson, C. Perey, Hetrich, and 2831 1451   45
Fu.                                                               2831 1451   46
                                                                  2831 1451   47
INCIDENT NEUTRON ENERGIES > 20 MeV                                2831 1451   48
                                                                  2831 1451   49
  The ENDF/B-VI Release 2 evaluation extends to 20 MeV and        2831 1451   50
includes cross sections and energy-angle data for all             2831 1451   51
significant reactions.  The present evaluation utilizes a more    2831 1451   52
compact composite reaction spectrum representation above 20 MeV   2831 1451   53
in order to reduce the length of the file. No essential data for  2831 1451   54
applications is lost with this representation.                    2831 1451   55
  The evaluation above 20 MeV utilizes MF=6, MT=5 to represent    2831 1451   56
all reaction data.  Production cross sections and emission        2831 1451   57
spectra are given for neutrons, protons, deuterons, tritons,      2831 1451   58
alpha particles, gamma rays, and all residual nuclides produced   2831 1451   59
(A>5) in the reaction chains. To summarize, the ENDF sections     2831 1451   60
with non-zero data above En = 20 MeV are:                         2831 1451   61
                                                                  2831 1451   62
  MF=3 MT=  1  Total Cross Section                                2831 1451   63
       MT=  2  Elastic Scattering Cross Section                   2831 1451   64
       MT=  3  Nonelastic Cross Section                           2831 1451   65
       MT=  5  Sum of Binary (n,n') and (n,x) Reactions           2831 1451   66
                                                                  2831 1451   67
  MF=4 MT=  2  Elastic Angular Distributions                      2831 1451   68
                                                                  2831 1451   69
  MF=6 MT=  5  Production Cross Sections and Energy-Angle         2831 1451   70
               Distributions for Emission Neutrons, Protons,      2831 1451   71
               Deuterons, Tritons, and Alphas; and Angle-         2831 1451   72
               Integrated Spectra for Gamma Rays and Residual     2831 1451   73
               Nuclei That Are Stable Against Particle Emission   2831 1451   74
                                                                  2831 1451   75
  The evaluation is based on nuclear model calculations that      2831 1451   76
have been benchmarked to experimental data, especially for n +    2831 1451   77
Ni58 and p + Ni58 reactions [Ch97]. We use the GNASH code system  2831 1451   78
[Yo92], which utilizes Hauser-Feshbach statistical,               2831 1451   79
preequilibrium and direct-reaction theories. Spherical optical    2831 1451   80
model calculations are used to obtain particle transmission       2831 1451   81
coefficients for the Hauser-Feshbach calculations, as well as     2831 1451   82
for the elastic neutron angular distributions.                    2831 1451   83
  Cross sections and spectra for producing individual residual    2831 1451   84
nuclei are included for reactions. The energy-angle-correlations  2831 1451   85
for all outgoing particles are based on Kalbach systematics       2831 1451   86
[Ka88].                                                           2831 1451   87
  A model was developed to calculate the energy distributions of  2831 1451   88
all recoil nuclei in the GNASH calculations [Ch96]. The recoil    2831 1451   89
energy distributions are represented in the laboratory system in  2831 1451   90
MT=5, MF=6, and are given as isotropic in the lab system. All     2831 1451   91
other data in MT=5,MF=6 are given in the center-of-mass system.   2831 1451   92
This method of representation utilizes the LCT=3 option approved  2831 1451   93
at the November, 1996, CSEWG meeting.                             2831 1451   94
  Preequilibrium corrections were performed in the course of the  2831 1451   95
GNASH calculations using the exciton model of Kalbach [Ka77,      2831 1451   96
Ka85], validated by comparison with calculations using Feshbach,  2831 1451   97
Kerman, Koonin (FKK) theory [Ch93].  Discrete level data from     2831 1451   98
nuclear data sheets were matched to continuum level densities     2831 1451   99
using the formulation of Gilbert and Cameron [Gi65] and pairing   2831 1451  100
and shell parameters from the Cook [Co67] analysis. Neutron and   2831 1451  101
charged- particle transmission coefficients were obtained from    2831 1451  102
the optical potentials, as discussed below.  Gamma-ray            2831 1451  103
transmission coefficients were calculated using the Kopecky-Uhl   2831 1451  104
model [Ko90].                                                     2831 1451  105
                                                                  2831 1451  106
SOME Ni-SPECIFIC INFORMATION CONCERNING THE EVAL.                 2831 1451  107
                                                                  2831 1451  108
  The neutron total cross section was evaluated based on the      2831 1451  109
least-squares method taking account of the experimental           2831 1451  110
data [Du67, Bo71, St71, Sm79, Fe80, Pe82, Ha82a, Di97].  The data 2831 1451  111
for natural Ni [Di97] was also used because there was not enough  2831 1451  112
data for Ni-60 above 20 MeV.  The data for natural Ni were        2831 1451  113
transformed to the Ni-60 cross section according to A*(2/3) law.  2831 1451  114
Result of this estimation  was used as the evaluated total cross  2831 1451  115
section data above 20 MeV.                                        2831 1451  116
                                                                  2831 1451  117
The evaluated total cross section data (1 to 250 MeV), s-wave     2831 1451  118
strength function [Mu81] and elastic scattering angular           2831 1451  119
distribution data [Bo71, Gu85, Tu73, Ya79] were used to obtain the2831 1451  120
neutron optical potential parameters. The parameter estimation was2831 1451  121
carried out based on Marquart-Bayesian approach [Sm91], where     2831 1451  122
ECIS95 code [Ra96] was used for the optical model calculation.  We2831 1451  123
have employed the energy dependence of the optical potential      2831 1451  124
similar to Delaroche's work [De89].  The initial potential        2831 1451  125
parameters were adopted from Koning and Delaroche [Ko97].  A total2831 1451  126
of 7 parameters concerning the central potential depth were       2831 1451  127
estimated with associated covariance matrix, while the geometrical2831 1451  128
parameters were fixed to the result of a similar search for n +   2831 1451  129
Ni-58. Presently obtained potential was used for the calculation  2831 1451  130
of neutron transmission coefficients and DWBA cross sections in   2831 1451  131
the energy region above 20 MeV.  Below 20 MeV, the Harper neutron 2831 1451  132
potential [Ha82b] was used for the calculation of transmission    2831 1451  133
coefficients.                                                     2831 1451  134
                                                                  2831 1451  135
The proton optical potential was also searched to obtain a good   2831 1451  136
description of proton-total reaction cross section as predicted by2831 1451  137
Wellisch-Axen systematic [We96] above 50 MeV.  The parameter      2831 1451  138
estimation was carried out by the Marquart-Bayesian approach      2831 1451  139
similar to the neutron OMP, but trying to seek the best parameter 2831 1451  140
to reproduce the reaction cross sections compiled by Carlson      2831 1451  141
[Ca96] and Wellisch values. The experimental data in Carlson      2831 1451  142
[Ca96] was scaled for Ni-60 according to A**(2/3) law.  In this   2831 1451  143
search, the geometrical parameters were fixed to be same as the   2831 1451  144
neutron potential.  The present potential gives a good description2831 1451  145
of the proton total reaction cross section from 10 MeV to 250 MeV.2831 1451  146
However, after some trial and error to reproduce both the elastic 2831 1451  147
scattering and reaction cross section data for Ni-58, we have     2831 1451  148
employed the following combination of proton potentials:          2831 1451  149
                                                                  2831 1451  150
 0 to   5 MeV  :  Harper potential [Ha82b]                        2831 1451  151
 6 to  47 MeV  :  Koning and Delaroche [Ko97]                     2831 1451  152
48 to 260 MeV  :  Present OMP                                     2831 1451  153
                                                                  2831 1451  154
For deuterons, the Lohr-Haeberli [Lo74] global potential was used;2831 1451  155
for alpha particles the McFadden-Satchler [Mc66] potential was    2831 1451  156
used; and for tritons the Becchetti-Greenlees [Be71] potential was2831 1451  157
used.  The He-3 channel was ignored.                              2831 1451  158
                                                                  2831 1451  159
The direct collective inelastic scattering to the following level 2831 1451  160
in Ni-60 was considered by the DWBA-mode calculation of ECIS95    2831 1451  161
[Ra96]:                                                           2831 1451  162
                                                                  2831 1451  163
Jpi Ex(MeV) Deformation length                                    2831 1451  164
 2+ 1.331   0.8535                                                2831 1451  165
                                                                  2831 1451  166
The deformation length was determined to much the ENDF/B-VI value 2831 1451  167
at 20 MeV.                                                        2831 1451  168
                                                                  2831 1451  169
Certain nuclear level densities were modified from the default    2831 1451  170
values in accordance with experimental level-density information  2831 1451  171
as follows. The level density of 57Fe was matched to the observed 2831 1451  172
D-0 value by modifying the pairing energy to 0.15 MeV; the level  2831 1451  173
density of the main competition channel, neutron emission to 60Ni,2831 1451  174
was adjusted to match Fischer et al.'s [Fi86] value of 3.85e3+-25%2831 1451  175
at 11 MeV excitation energy, but then increased slightly (a total 2831 1451  176
density increase of 11%) by using a pairing energy of 1.1 MeV,    2831 1451  177
since Haight's alpha production at 14 MeV is approx. 11% smaller  2831 1451  178
than Fischer et al.'s measurements. Production of residual nuclei 2831 1451  179
59Ni and 56Fe, through (n,2n) and (n,na) reactions, become        2831 1451  180
particularly important above 14 MeV. Pairing energies were        2831 1451  181
adjusted to match the level density for 59Ni at the neutron       2831 1451  182
binding energy (D0=12.9 keV), and Fischer et al.'s result for the 2831 1451  183
56Fe level density at 11 MeV.                                     2831 1451  184
                                                                  2831 1451  185
The new Haight et al. [Ha97] LANL/WNR 60Ni(n,x alpha) data up to  2831 1451  186
50 MeV was used to benchmark our model calculations [Ch97] -      2831 1451  187
agreement with experiment was good.                               2831 1451  188
                                                                  2831 1451  189
 **************************************************************** 2831 1451  190
                                                                  2831 1451  191
REFERENCES                                                        2831 1451  192
                                                                  2831 1451  193
[Be71]  F.D. Becchetti, Jr., and G.W. Greenlees in                2831 1451  194
   "Polarization Phenomena in Nuclear Reactions," (Ed: H.H.       2831 1451  195
   Barschall and W. Haeberli, The University of Wisconsin Press,  2831 1451  196
   1971) p.682                                                    2831 1451  197
[Bo71]  P. Boschung et al, Nucl.Phys. A161, 593 (1971)            2831 1451  198
[Ca96]  R.F. Carlson, Atomic Data and Nuclear Data Tables, 63,    2831 1451  199
   93 (1996)                                                      2831 1451  200
[Ch93]  M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2831 1451  201
[Ch96]  M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J.      2831 1451  202
   Koning, "High-Energy Nuclear Data Libraries for Accelerator-   2831 1451  203
   Driven Technologies:  Calculational Method for Heavy Recoils," 2831 1451  204
   Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation    2831 1451  205
   Technology and Applications, Kalmar, Sweden, 3-7 June 1996     2831 1451  206
[Ch97]  M.B. Chadwick and P.G. Young, "Model Calculations of      2831 1451  207
   n,p + 58,60,61,62,64Ni" in APT PROGRESS REPORT: 1 August - 1   2831 1451  208
   September 1997, internal Los Alamos National Laboratory memo T-2831 1451  209
   2-97/MS-51, 8 September 1997 from R.E. MacFarlane to L. Waters.2831 1451  210
[Ch99]  M.B. Chadwick, P.G. Young, G.M. Hale, et al., Los Alamos  2831 1451  211
   National Laboratory report, LA-UR-99-1222 (1999)               2831 1451  212
[Ci68]  S. Cierjack et al, report KFK-1000 (1968)                 2831 1451  213
[Co67]  J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J.    2831 1451  214
   Phys. 20, 477 (1967)                                           2831 1451  215
[De89]  J.P. Delaroche, Y. Wang and J. Rapaport, Phys.Rev.C 39,   2831 1451  216
   391 (1989)                                                     2831 1451  217
[Di97]  F. Dietrich et al., private communication (1997).         2831 1451  218
[Du67]  Yu.V. Dukarevich et al., Nucl.Phys. A92, 433 (1967)       2831 1451  219
[Fe80]  M.B. Fedorov et al., 80Kiev, 1, 309(1980)                 2831 1451  220
[Fi86]  R. Fischer, G. Traxler, M. Uhl at al., Phys Rev C34, 460  2831 1451  221
   (1986)                                                         2831 1451  222
[Fr01]  S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos      2831 1451  223
   National Laboratory Report, LA-13812 (2001).                   2831 1451  224
[Fu96]   C.Y. Fu, "Effects of shape differences in the level      2831 1451  225
   densities of three formalisms on calculated cross sections",   2831 1451  226
   personal communication, 1996 (to be published by the IAEA).    2831 1451  227
[Gi65]  A. Gilbert and A.G.W. Cameron, Can.J.Phys. 43, 1446 (1965)2831 1451  228
[Gu85]  P.P. Guss et al, Nucl.Phys. A438, 187 (1985)              2831 1451  229
[Ha82a] J.A. Harvey et al, 82Anterp  (1982) p. 856                2831 1451  230
[Ha82b] R.C. Harper and W.L. Alford, J.Phys.G. 8, 153 (1982)      2831 1451  231
[Ha97]  R.C. Haight, F.B. Bateman, S.M. Sterbenz et al., Nuclear  2831 1451  232
   Data for Science and Technol., Proc. Conf. Trieste, Italy, May 2831 1451  233
   1997, Vol. I (Edit. Compositori, Bologna, Italy, 1997) p. 603  2831 1451  234
[Ka77]  C. Kalbach, Z.Phys.A  283, 401 (1977)                     2831 1451  235
[Ka85]  C. Kalbach, Los Alamos National Laboratory report         2831 1451  236
   LA-10248-MS (1985)                                             2831 1451  237
[Ka88]  C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also          2831 1451  238
   C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981)           2831 1451  239
[Ko90]  J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990)         2831 1451  240
[Ko97]  A. Koning and J.P. Delaroche, private communication.      2831 1451  241
[La83]  D.C. Larson et al, report ORNL-TM-8203 (1983)             2831 1451  242
[Lo74]  J.M.Lohr and W.Haeberli, Nucl.Phys. A232, 381 (1974)      2831 1451  243
[Mc66]  L. McFadden and G.R. Satchler, Nucl.Phys. 84, 177 (1966)  2831 1451  244
[Mu81]  S.F. Mughabghab, M. Divadeenam and N.E. Holden, "Neutron  2831 1451  245
   Cross Sections", Vol. 1, Part A (Academic Press, 1981)         2831 1451  246
[Pe73]  F.G. Perey, private communication (1973) [EXFOR 10342]    2831 1451  247
[Pe82]  C.M. Perey et al, report ORNL-5893 (1982)                 2831 1451  248
[Pe88]  Pedroni et al, Phys.Rev.C 38, 2052 (1988)                 2831 1451  249
[Po81]  W. Poenitz, Proc. Conf. on Nuclear Data Evaluation Methods2831 1451  250
   and Procedures, Brookhaven National Laboratory Report BNL-NCS- 2831 1451  251
   51363, p.249(1981).                                            2831 1451  252
[Ra96]   J. Raynal, "Notes on ECIS94", Service de Physique        2831 1451  253
   Theorique, Saclay, France (personal communication through A. J.2831 1451  254
   Koning, 1996).                                                 2831 1451  255
[Sc73]  W. Schimmerling et al., Phys.Rev.C 7, 248 (1973)          2831 1451  256
[Sm79]  A.B. Smith et al., Nucl.Sci.Eng., 72, 293 (1979)          2831 1451  257
[Sm91]  D.L. Smith, "Probability, Statistics, and Data Uncertainty2831 1451  258
   in Nuclear Science and Technology" (American Nuclear Society,  2831 1451  259
   1991)                                                          2831 1451  260
[Sm92]  A.B. Smith et al., J.Phys.G, 18, 629 (1992)               2831 1451  261
[St71]  P. Stoler et al,, 71Knox, 1, 311 (1971)                   2831 1451  262
[Tu73]  A.I. Tutubalin et al., Neutron Physics, Proc. Conf., Kiev,2831 1451  263
   Ukraine, 1973, Vol. 3 [EXFOR 40417] p. 62                      2831 1451  264
[Ul83]  J.J. Ullmann, F.P. Brady, C.M. Castaneda, et al., Nucl.   2831 1451  265
   Phys. A427, 493 (1984)                                         2831 1451  266
[We96]  H.P. Wellisch and D. Axen, Phys.Rev.C 54, 1329 (1996)     2831 1451  267
[Ya79]  Y. Yamanouti, J. Rapaport, S.M. Grimes et al, Nuclear     2831 1451  268
   Cross Sections for Technology, Proc. Conf., Knoxville, TN,     2831 1451  269
   1979, NBS Special Publication 594 (1980) [EXFOR 10953]         2831 1451  270
[Yo92]  P.G. Young, E.D. Arthur, and M.B. Chadwick, Los Alamos    2831 1451  271
   report LA-12343-MS (1992)                                      2831 1451  272
                                                                  2831 1451  273
 **************************************************************** 2831 1451  274
                                                                  2831 1451  275
 ENDF/B-VI MOD 2 Revision, July 1991, D.C. Larson, C.M. Perey,    2831 1451  276
                 D.M. Hetrick, and C.Y. Fu (ORNL)                 2831 1451  277
                                                                  2831 1451  278
 REVISION 1 CHANGES                                               2831 1451  279
   The resonance region from 1.E-5 eV to 450 keV has been changed,2831 1451  280
 based on a SAMMY analysis by F. G. Perey of new 60Ni ORELA data  2831 1451  281
 up to 100 keV of Harvey, Hill and Perey. This new work reproduces2831 1451  282
 the thermal cross sections and includes the small resonances     2831 1451  283
 inadvertently left out in the original file.  No background      2831 1451  284
 cross sections are required in file 3 in the resonance region.   2831 1451  285
   Removed elastic transformation matrix.                         2831 1451  286
                                                                  2831 1451  287
 **************************************************************** 2831 1451  288
                                                                  2831 1451  289
 ENDF/B-VI MOD 1 Evaluation, October 1989, D.C. Larson,           2831 1451  290
                 C.M. Perey, D.M. Hetrick, and C.Y. Fu (ORNL)     2831 1451  291
                                                                  2831 1451  292
   This work employed nuclear model codes including the           2831 1451  293
 Distorted Wave Born Approximation (DWBA) program DWUCK (1)       2831 1451  294
 and the Hauser-Feshbach code TNG (2,3,4).  The TNG code provides 2831 1451  295
 energy and angular distributions of particles emitted in the     2831 1451  296
 compound and pre-compound reactions, ensures consistency among   2831 1451  297
 all reactions, and maintains energy balance. Details pertinent   2831 1451  298
 to the contents of this evaluation and extensive comparisons of  2831 1451  299
 calculations with experimental data can be found in Hetrick (5). 2831 1451  300
                                                                  2831 1451  301
----- DESCRIPTION OF FILES                                        2831 1451  302
(MF-MT)                                                           2831 1451  303
  1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS.         2831 1451  304
  2-151 RESONANCE PARAMETERS -- TAKEN FROM REF (6).  THE NEGATIVE 2831 1451  305
        ENERGY RESONANCES WERE ADJUSTED BY THE AUTHOR, C. M. PEREY2831 1451  306
        TO GIVE THE PROPER THERMAL SCATTERING AND CAPTURE.  USING 2831 1451  307
        THESE MODIFIED RESULTS, NO BACKGROUND IS REQUIRED IN 3/1  2831 1451  308
        IE, THE TOTAL, SCATTERING AND CAPTURE IS GIVEN COMPLETELY 2831 1451  309
        BY THE RESONANCE PARAMETERS FROM 1.E-5 EV TO 450 KEV.     2831 1451  310
        RESONANCE PARAMETERS ARE FROM A REICH-MOORE ANALYSIS WITH 2831 1451  311
        THE CODE SAMMY (REF 7).                                   2831 1451  312
        THUS, THE THERMAL CROSS SECTIONS ARE GIVEN BY THE         2831 1451  313
        RESONANCE PARAMETERS AND HAVE VALUES: TOTAL 3.9 B,        2831 1451  314
        ELASTIC SCATTERING 0.98 B, AND CAPTURE 2.92 B.            2831 1451  315
        NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2831 1451  316
        OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE       2831 1451  317
        PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON    2831 1451  318
        A FINER ENERGY GRID THAN GIVEN IN 4/2.                    2831 1451  319
  3-103 (N,P) CROSS SECTIONS FOR EN LESS THAN OR EQUAL TO 12 MEV  2831 1451  320
        WERE TAKEN FROM A CURVE DRAWN THROUGH THE DATA OF VONACH  2831 1451  321
        ET AL. (10). THIS CURVE WAS CONNECTED TO THE ANL DATA OF  2831 1451  322
        GREENWOOD (11) FROM 14.5 TO 15.0 MEV. FROM 15.0 TO 20.0   2831 1451  323
        MEV THE DATA OF PAULSEN AND LISKIEN (12) WERE USED        2831 1451  324
        AS A GUIDE.  THE NEW DATA BY VONACH ET AL. (10)           2831 1451  325
        RESULT IN AN INTEGRAL VALUE CLOSE TO THE 2.39 VALUE OF    2831 1451  326
        MANNHART (13).                                            2831 1451  327
--------------------------------------------------------------    2831 1451  328
            UNCERTAINTY FILES                                     2831 1451  329
        AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS  2831 1451  330
        REQUIRED BY ENDF/B-VI.                                    2831 1451  331
                                                                  2831 1451  332
 33-103 COVARIANCES - DATA OF VONACH ET AL. (10) AND CSISRS DATA  2831 1451  333
        USED AS A GUIDE.                                          2831 1451  334
 ---------------------------------------------------------------- 2831 1451  335
 REFERENCES:                                                      2831 1451  336
 (1) P.D. Kunz, "DISTORTED WAVE CODE DWUCK72," UNIV. OF           2831 1451  337
     COLORADO, UNPUBLISHED (1972).                                2831 1451  338
 (2) C.Y. Fu, Oak Ridge report ORNL/TM-7042 (1980)                2831 1451  339
 (3) C.Y Fu, Neutron Cross Sections from 10 to 50 MeV, Proc. Symp.2831 1451  340
     Upton, NY, May 1980, Brookhaven report BNL-NCS-51425 (1980)  2831 1451  341
     p. 675                                                       2831 1451  342
 (4) K. Shibata and C.Y. Fu, Oak Ridge National Laboratory report 2831 1451  343
     ORNL/TM-10093 (1986)                                         2831 1451  344
 (5) D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge National   2831 1451  345
     Laboratory report ORNL/TM-10219 [ENDF-344] (1987)            2831 1451  346
 (6) C.M. Perey, J.A. Harvey, R.L. Macklin, et al., Phys.Rev.C,   2831 1451  347
     27, 2556 (1983)                                              2831 1451  348
 (7) N.M. Larson and F.G. Perey, Oak Ridge National Laboratory    2831 1451  349
     reports ORNL/TM-7485 (1980); ORNL/TM-9179 (1984);            2831 1451  350
     ORNL/TM-9179/R1 (1985); ORNL/TM-9179/R2 (1988)               2831 1451  351
 (8) J.A. Harvey, ORELA, 80-M NE110 TA TARGET DATA, SENT TO NNDC  2831 1451  352
 (9) J.A. Harvey, ORELA, 80-M NE110 BE BLOCK DATA, SENT TO NNDC   2831 1451  353
(10) H. Vonach, M. Wagner, and R.C. Haight, "Neutron cross        2831 1451  354
     sections of 58Ni and 60Ni for 8-12 MeV neutrons," private    2831 1451  355
     communication, 1989                                          2831 1451  356
(11) L.R. Greenwood, report DOE-ER-0046-21 (1985) p. 15           2831 1451  357
(12) A. Paulsen, Nukleonik 10, 91 (1967)                          2831 1451  358
(13) W. Mannhart, Proc. Fourth ASTM-Euratom Symp. on Reactor      2831 1451  359
     Dosimetry, Vol. II, March 22-26, 1982 (1982) p. 637          2831 1451  360
(14) M. Divadeenam, Brookhaven National Laboratory report         2831 1451  361
     BNL-NCS-51346 [ENDF-294] (1979)                              2831 1451  362
(15) S.M. Grimes, R.C. Haight, K.R. Alvar, et al., Phys.Rev.C     2831 1451  363
     19, 2127 (1979)                                              2831 1451  364
  ****************************************************************2831 1451  365
 Psuedo Threshold of 0.0 added at 2.7E+6 ev to MF/MT=3/103 after  2831 1451  366
 processing thro. codes.                                          2831 1451  367
                                                                  2831 1451  368
                                                                  2831 1451  369
                                                                  2831 1451  370
 ************************ C O N T E N T S *********************** 2831 1451  371
 ***************** Program LINEAR (VERSION 2002-1) ***************2831 1451  372
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2831 1451  373
 Data Linearized to Within an Accuracy of .100000000 per-cent     2831 1451  374
 ***************** Program RECENT (VERSION 2002-1) ***************2831 1451  375
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2831 1451  376
 Data Linearized to within an Accuracy of .100000000 per-cent     2831 1451  377
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2831 1451  378
 Data Doppler Broadened to 300.000000 Kelvin                      2831 1451  379
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2831 1451  380
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2831 1451  381
 ***************** Program FIXUP (Version 2002-1) ****************2831 1451  382
 Corrected ZA/AWR in All Sections-----------------------------Yes 2831 1451  383
 Corrected Thresholds-----------------------------------------Yes 2831 1451  384
 Extended Cross Sections to 20 MeV----------------------------No  2831 1451  385
 Allow Cross Section Deletion---------------------------------No  2831 1451  386
 Allow Cross Section Reconstruction---------------------------No  2831 1451  387
 Make All Cross Sections Non-Negative-------------------------Yes 2831 1451  388
 Delete Energies Not in Ascending Order-----------------------Yes 2831 1451  389
 Deleted Duplicate Points-------------------------------------Yes 2831 1451  390
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2831 1451  391
 Check for Legal MF/MT Numbers--------------------------------Yes 2831 1451  392
 Allow Creation of Missing Sections---------------------------No  2831 1451  393
 Allow Insertion of Energy Points-----------------------------No  2831 1451  394
 Create Uniform Energy Grid-----------------------------------No  2831 1451  395
 Delete Section if Cross Section =0 at All Energies-----------Yes 2831 1451  396
 ***************** Program GROUPIE (VERSION 2002-1) **************2831 1451  397
 Unshielded Group Averages Using  640 Groups                      2831 1451  398
 Weighting Spectrum: Flat (Constant) Spectrum                     2831 1451  399
                                1        451        403          42831 1451  400
                                2        151          4          42831 1451  401
                                3        103         61          12831 1451  402
                               33        103         14          12831 1451  403
                                                                  2831 1  099999
                                                                  2831 0  0    0
 2.80600E+4 5.94160E+1          0          0          1          02831 2151    1
 2.806000+4 1.000000+0          0          0          1          02831 2151    2
 1.000000-5 4.500000+5          0          0          0          02831 2151    3
 0.000000+0 6.000000-1          0          0          0          02831 2151    4
                                                                  2831 2  099999
                                                                  2831 0  0    0
 2.80600E+4 5.94159E+1          0          0          0          02831 3103    1
-2.04150E+6-2.04150E+6          0          0          1        1742831 3103    2
        174          1                                            2831 3103    3
 2700000.00 1.27290E-8 2800000.00 3.81870E-8 2900000.00 6.36450E-82831 3103    4
 3000000.00 2.39704E-6 3100000.00 7.03836E-6 3200000.00 1.16797E-52831 3103    5
 3300000.00 1.63210E-5 3400000.00 2.09623E-5 3500000.00 5.81607E-52831 3103    6
 3600000.00 .000127916 3700000.00 .000197672 3800000.00 .0002674272831 3103    7
 3900000.00 .000337182 4000000.00 .000553104 4100000.00 .0009151922831 3103    8
 4200000.00 .001277280 4300000.00 .001639368 4400000.00 .0020014562831 3103    9
 4500000.00 .002751840 4600000.00 .003890520 4700000.00 .0050292002831 3103   10
 4800000.00 .006167880 4900000.00 .007306560 5000000.00 .0085883102831 3103   11
 5100000.00 .010013130 5200000.00 .011437950 5300000.00 .0128627702831 3103   12
 5400000.00 .014287590 5500000.00 .015850000 5600000.00 .0175500002831 3103   13
 5700000.00 .019250000 5800000.00 .020950000 5900000.00 .0226500002831 3103   14
 6000000.00 .024550000 6100000.00 .026650000 6200000.00 .0287500002831 3103   15
 6300000.00 .030850000 6400000.00 .032950000 6500000.00 .0350000002831 3103   16
 6600000.00 .037000000 6700000.00 .039000000 6800000.00 .0410000002831 3103   17
 6900000.00 .043000000 7000000.00 .045200000 7100000.00 .0476000002831 3103   18
 7200000.00 .050000000 7300000.00 .052400000 7400000.00 .0548000002831 3103   19
 7500000.00 .056900000 7600000.00 .058700000 7700000.00 .0605000002831 3103   20
 7800000.00 .062300000 7900000.00 .064100000 8000000.00 .0660000002831 3103   21
 8100000.00 .068000000 8200000.00 .070000000 8300000.00 .0720000002831 3103   22
 8400000.00 .074000000 8500000.00 .075800000 8600000.00 .0774000002831 3103   23
 8700000.00 .079000000 8800000.00 .080600000 8900000.00 .0822000002831 3103   24
 9000000.00 .083950000 9100000.00 .085850000 9200000.00 .0877500002831 3103   25
 9300000.00 .089650000 9400000.00 .091550000 9500000.00 .0933500002831 3103   26
 9600000.00 .095050000 9700000.00 .096750000 9800000.00 .0984500002831 3103   27
 9900000.00 .100150000 10000000.0 .101850000 10100000.0 .1035500002831 3103   28
 10200000.0 .105250000 10300000.0 .106950000 10400000.0 .1086500002831 3103   29
 10500000.0 .110350000 10600000.0 .112050000 10700000.0 .1137500002831 3103   30
 10800000.0 .115450000 10900000.0 .117150000 11000000.0 .1188500002831 3103   31
 11100000.0 .120550000 11200000.0 .122250000 11300000.0 .1239500002831 3103   32
 11400000.0 .125650000 11500000.0 .127350000 11600000.0 .1290500002831 3103   33
 11700000.0 .130750000 11800000.0 .132450000 11900000.0 .1341500002831 3103   34
 12000000.0 .135550000 12100000.0 .136650000 12200000.0 .1377500002831 3103   35
 12300000.0 .138850000 12400000.0 .139950000 12500000.0 .1410500002831 3103   36
 12600000.0 .142150000 12700000.0 .143250000 12800000.0 .1443500002831 3103   37
 12900000.0 .145450000 13000000.0 .146200000 13100000.0 .1466000002831 3103   38
 13200000.0 .147000000 13300000.0 .147400000 13400000.0 .1478000002831 3103   39
 13500000.0 .147850000 13600000.0 .147550000 13700000.0 .1472500002831 3103   40
 13800000.0 .146950000 13900000.0 .146650000 14000000.0 .1460520002831 3103   41
 14100000.0 .145156000 14200000.0 .144260000 14300000.0 .1433640002831 3103   42
 14400000.0 .142468000 14500000.0 .140559000 14600000.0 .1376370002831 3103   43
 14700000.0 .134715000 14800000.0 .131793000 14900000.0 .1288710002831 3103   44
 15000000.0 .125949000 15100000.0 .123027000 15200000.0 .1201050002831 3103   45
 15300000.0 .117183000 15400000.0 .114261000 15500000.0 .1113390002831 3103   46
 15600000.0 .108417000 15700000.0 .105495000 15800000.0 .1025730002831 3103   47
 15900000.0 .099651000 16000000.0 .097483667 16100000.0 .0960710002831 3103   48
 16200000.0 .094658333 16300000.0 .093245667 16400000.0 .0918330002831 3103   49
 16500000.0 .090420333 16600000.0 .089007667 16700000.0 .0875950002831 3103   50
 16800000.0 .086182333 16900000.0 .084769667 17000000.0 .0833570002831 3103   51
 17100000.0 .081944333 17200000.0 .080531667 17300000.0 .0791190002831 3103   52
 17400000.0 .077706333 17500000.0 .076620000 17600000.0 .0758600002831 3103   53
 17700000.0 .075100000 17800000.0 .074340000 17900000.0 .0735800002831 3103   54
 18000000.0 .072820000 18100000.0 .072060000 18200000.0 .0713000002831 3103   55
 18300000.0 .070540000 18400000.0 .069780000 18500000.0 .0690200002831 3103   56
 18600000.0 .068260000 18700000.0 .067500000 18800000.0 .0667400002831 3103   57
 18900000.0 .065980000 19000000.0 .065220000 19100000.0 .0644600002831 3103   58
 19200000.0 .063700000 19300000.0 .062940000 19400000.0 .0621800002831 3103   59
 19500000.0 .061420000 19600000.0 .060660000 19700000.0 .0599000002831 3103   60
 19800000.0 .059140000 19900000.0 .058380000 20000000.0 0.0       2831 3103   61
                                                                  2831 3  099999
                                                                  2831 0  0    0
 2.80600E+4 5.94160E+1          0          0          0          1283133103    1
 0.000000+0 0.000000+0          0        103          0          4283133103    2
 0.000000+0 0.000000+0          0          0          6          3283133103    3
 1.000000-5 0.000000+0 2.700000+6 1.00000-11 2.000000+7 0.000000+0283133103    4
 0.000000+0 0.000000+0          0          1          6          3283133103    5
 1.000000-5 0.000000+0 2.700000+6 5.000000-3 2.000000+7 0.000000+0283133103    6
 0.000000+0 0.000000+0          0          1         16          8283133103    7
 1.000000-5 0.000000+0 2.700000+6 7.200000-2 5.000000+6 1.800000-2283133103    8
 7.000000+6 1.012500-2 1.000000+7 1.012500-2 1.200000+7 4.500000-3283133103    9
 1.600000+7 1.800000-2 2.000000+7 0.000000+0                      283133103   10
 0.000000+0 0.000000+0          0          8         16          8283133103   11
 1.000000-5 0.000000+0 2.700000+6 4.66640-17 5.000000+6 1.240600-7283133103   12
 7.000000+6 2.178000-6 1.000000+7 1.147600-5 1.200000+7 9.112500-6283133103   13
 1.600000+7 1.928300-5 2.000000+7 0.000000+0                      283133103   14
                                                                  283133  099999
                                                                  2831 0  0    0
                                                                     0 0  0    0
 2.90630E+4 6.23890E+1          0          0         34         102925 1451    1
 0.0        0.0                 0          0          0          62925 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20022925 1451    3
 3.00000E+2 0.0                 1          0        550          82925 1451    4
 29-Cu- 63  LANL,ORNL,FEI EVAL-FEB98 A.KONING ET AL,K.Zolotarev   2925 1451    5
                      DIST-Feb2004                                2925 1451    6
----IRDF-2002         MATERIAL 2925                               2925 1451    7
-----INCIDENT NEUTRON DATA                                        2925 1451    8
------ENDF-6 FORMAT                                               2925 1451    9
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2925 1451   10
DOSIMETRY                                                         2925 1451   11
******************************************************************2925 1451   12
  29-Cu- 63 LANL,ORNL EVAL-FEB98 A.KONING,M.CHADWICK,HETRICK      2925 1451   13
 Ch98,Ch99            DIST-SEP 1 REV4-                 20010926   2925 1451   14
----ENDF/B-VI         MATERIAL 2925         REVISION 3            2925 1451   15
 **************************************************************** 2925 1451   16
***************************************************************** 2925 1451   17
 29-Cu- 63 FEI        EVAL-Nov01 K.I.Zolotarev                    2925 1451   18
                      DIST-Jan02                       20020110   2925 1451   19
----BROND-2           MATERIAL 2925                               2925 1451   20
-----INCIDENT NEUTRON DATA                                        2925 1451   21
------ENDF-6 FORMAT                                               2925 1451   22
------Russian Reactor Dosimetry File RRDF-2002                    2925 1451   23
***************************************************************** 2925 1451   24
Author  of evaluation: K.I.Zolotarev                              2925 1451   25
                    ----- MF=3 MT=107 -----                       2925 1451   26
***************************************************************** 2925 1451   27
******** Start of (N,2N), (N.G) bibliographical component ******* 2925 1451   28
***************************************************************** 2925 1451   29
                                                                  2925 1451   30
 ENDF/B-VI MOD 5 Revision, May 2000, S.C. Frankle, R.C. Reedy,    2925 1451   31
                 P.G. Young (LANL)                                2925 1451   32
                                                                  2925 1451   33
 The secondary gamma-ray spectrum for radiative capture (MF 12,   2925 1451   34
 MT 102) has been updated for new experimental data at incident   2925 1451   35
 neutron energies up to 1 keV. The Q-value for radiative capture  2925 1451   36
 was also updated in File 3.                                      2925 1451   37
 Details of these changes are described in Frankel et al. [Fr01]. 2925 1451   38
                                                                  2925 1451   39
 **************************************************************** 2925 1451   40
                                                                  2925 1451   41
 ENDF/B-VI MOD 4 Evaluation, February 1998, A.J. Koning (ECN),    2925 1451   42
                 M.B. Chadwick, P.G. Young (LANL)                 2925 1451   43
                                                                  2925 1451   44
 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code     2925 1451   45
   in cooperation with ECN Petten.                                2925 1451   46
                                                                  2925 1451   47
  This evaluation provides a complete representation of the       2925 1451   48
nuclear data needed for transport, damage, heating,               2925 1451   49
radioactivity, and shielding applications over the incident       2925 1451   50
neutron energy range from 1.0E-11 to 150 MeV.  The discussion     2925 1451   51
here is divided into the region below and above 20 MeV.           2925 1451   52
                                                                  2925 1451   53
INCIDENT NEUTRON ENERGIES < 20 MeV                                2925 1451   54
                                                                  2925 1451   55
  Below 20 MeV the evaluation is based completely on the ENDF/B-  2925 1451   56
VI (Mod 3) evaluation by D. Hetrick, C.Y. Fu, and D. Larson.      2925 1451   57
                                                                  2925 1451   58
INCIDENT NEUTRON ENERGIES > 20 MeV                                2925 1451   59
                                                                  2925 1451   60
  The ENDF/B-VI Release 2 evaluation extends to 20 MeV and        2925 1451   61
includes cross sections and energy-angle data for all             2925 1451   62
significant reactions.  The present evaluation utilizes a more    2925 1451   63
compact composite reaction spectrum representation above 20 MeV   2925 1451   64
in order to reduce the length of the file. No essential data for  2925 1451   65
applications is lost with this representation.                    2925 1451   66
  The evaluation above 20 MeV utilizes MF=6, MT=5 to represent    2925 1451   67
all reaction data.  Production cross sections and emission        2925 1451   68
spectra are given for neutrons, protons, deuterons, tritons,      2925 1451   69
alpha particles, gamma rays, and all residual nuclides produced   2925 1451   70
(A>5) in the reaction chains. To summarize, the ENDF sections     2925 1451   71
with non-zero data above En = 20 MeV are:                         2925 1451   72
                                                                  2925 1451   73
  MF=3 MT=  1  Total Cross Section                                2925 1451   74
       MT=  2  Elastic Scattering Cross Section                   2925 1451   75
       MT=  3  Nonelastic Cross Section                           2925 1451   76
       MT=  5  Sum of Binary (n,n') and (n,x) Reactions           2925 1451   77
                                                                  2925 1451   78
  MF=4 MT=  2  Elastic Angular Distributions                      2925 1451   79
                                                                  2925 1451   80
  MF=6 MT=  5  Production Cross Sections and Energy-Angle         2925 1451   81
               Distributions for Emission Neutrons, Protons,      2925 1451   82
               Deuterons, Tritons, and Alphas; and Angle-         2925 1451   83
               Integrated Spectra for Gamma Rays and Residual     2925 1451   84
               Nuclei That Are Stable Against Particle Emission   2925 1451   85
                                                                  2925 1451   86
  The evaluation is based on nuclear model calculations that      2925 1451   87
have been benchmarked to experimental data, especially for n +    2925 1451   88
Cu65 and p + Cu65 reactions [Ch98]. We use the GNASH code system  2925 1451   89
[Yo92], which utilizes Hauser-Feshbach statistical, preequilib-   2925 1451   90
rium and direct-reaction theories. Spherical optical model        2925 1451   91
calculations are used to obtain particle transmission             2925 1451   92
coefficients for the Hauser-Feshbach calculations, as well as     2925 1451   93
for the elastic neutron angular distributions.                    2925 1451   94
  Cross sections and spectra for producing individual residual    2925 1451   95
nuclei are included for reactions. The energy-angle-correlations  2925 1451   96
for all outgoing particles are based on Kalbach systematics       2925 1451   97
[Ka88].                                                           2925 1451   98
  A model was developed to calculate the energy distributions of  2925 1451   99
all recoil nuclei in the GNASH calculations [Ch96a]. The recoil   2925 1451  100
energy distributions are represented in the laboratory system in  2925 1451  101
MT=5, MF=6, and are given as isotropic in the lab system. All     2925 1451  102
other data in MT=5,MF=6 are given in the center-of-mass system.   2925 1451  103
This method of representation utilizes the LCT=3 option approved  2925 1451  104
at the November, 1996, CSEWG meeting.                             2925 1451  105
  Preequilibrium corrections were performed in the course of the  2925 1451  106
GNASH calculations using the exciton model of Kalbach [Ka77,      2925 1451  107
Ka85], validated by comparison with calculations using Feshbach,  2925 1451  108
Kerman, Koonin (FKK) theory [Ch93].  Discrete level data from     2925 1451  109
nuclear data sheets were matched to continuum level densities     2925 1451  110
using the formulation of Ignatyuk et al. [Ig75] and pairing and   2925 1451  111
shell parameters from the Cook [Co67] analysis. Neutron and       2925 1451  112
charged- particle transmission coefficients were obtained from    2925 1451  113
the optical potentials, as discussed below.  Gamma-ray            2925 1451  114
transmission coefficients were calculated using the Kopecky-Uhl   2925 1451  115
model [Ko90].                                                     2925 1451  116
                                                                  2925 1451  117
SPECIFIC INFORMATION CONCERNING THE 63Cu EVALUATION               2925 1451  118
                                                                  2925 1451  119
This evaluation is documented in some detail in Ref. [Ko98b].     2925 1451  120
                                                                  2925 1451  121
The neutron total cross section above 20 MeV was obtained by      2925 1451  122
evaluating experimental data, with a particular emphasis on the   2925 1451  123
Finlay [Fi93] elemental data. This resulted in an evaluated       2925 1451  124
elemental Cu total cross section; to obtain an isotopic 63Cu total2925 1451  125
cross section, it was assumed that 63Cu and 65Cu have total cross 2925 1451  126
sections in an A**2/3 ratio to one another. The total neutron     2925 1451  127
nonelastic cross section was obtained directly from an optical    2925 1451  128
model calculation (see below), after verifying that it was in good2925 1451  129
agreement with the experimental data [Ko98b].                     2925 1451  130
                                                                  2925 1451  131
To obtain the neutron optical potential we used total cross       2925 1451  132
section data from 1.2 to 4.5 MeV [Gu86] and from 5.3 to 600 MeV   2925 1451  133
[Fi93], and elastic scattering angular distribution data from 1.6 2925 1451  134
to 96 MeV [Br50, Sa60, Ki74, El82, Gu86]. The optical potential   2925 1451  135
parameters were obtained using a combination of a grid search code2925 1451  136
and the interactive optical model viewer ECISVIEW [Ko97], both    2925 1451  137
built around the coupled channels code ECIS96 [Ra94]. The energy  2925 1451  138
dependence of the optical model parameters is as described in     2925 1451  139
[Ko98]. This optical potential was used for the calculation, with 2925 1451  140
ECIS96, of neutron transmission coefficients and DWBA cross       2925 1451  141
sections for the entire energy region above 20 MeV.               2925 1451  142
                                                                  2925 1451  143
Due to the lack of proton elastic scattering data in numerical    2925 1451  144
form, we used a combination of global optical models for the      2925 1451  145
proton channel. The Becchetti-Greenlees potential [Be69]was       2925 1451  146
adopted below 47 MeV, and the non-relativistic version of the     2925 1451  147
Madland potential [Ma88] above 47 MeV. At this particular energy  2925 1451  148
point the two potentials join smoothly.                           2925 1451  149
                                                                  2925 1451  150
For deuterons, the Lohr-Haeberli global potential [Lo74] was used;2925 1451  151
for alpha particles the Moyen potential (MacFadden-Satchler       2925 1451  152
[Ma66]) was used; and for tritons the Becchetti-Greenlees         2925 1451  153
potential [Be71] was used. The He-3 channel was ignored, due to   2925 1451  154
its small importance.                                             2925 1451  155
                                                                  2925 1451  156
Following Delaroche et al. [De82], we adopted the weak-coupling   2925 1451  157
model for direct collective inelastic scattering for Cu-63, using 2925 1451  158
Ni-64 as a basis. For the calculation of the cross sections,      2925 1451  159
ECIS96 was used in DWBA mode. We used the following direct        2925 1451  160
transitions for Cu-63  (ground state 3/2- ) :                     2925 1451  161
                                                                  2925 1451  162
Jpi Ex(MeV) Deformation lengths                                   2925 1451  163
 0.5- 0.669   Delta(2)=0.319                                      2925 1451  164
 2.5- 0.962   Delta(2)=0.552                                      2925 1451  165
 3.5- 1.327   Delta(2)=0.638                                      2925 1451  166
 1.5- 1.547   Delta(2)=0.451                                      2925 1451  167
 1.5- 3.382   Delta(3)=0.313                                      2925 1451  168
 2.5- 3.632   Delta(3)=0.384                                      2925 1451  169
 3.5- 3.882   Delta(3)=0.444                                      2925 1451  170
 4.5- 4.132   Delta(3)=0.496                                      2925 1451  171
                                                                  2925 1451  172
No measurements exist for neutron-induced emission spectra above  2925 1451  173
20 MeV for 63Cu. However, for Cu-65 there exists 25.7 MeV (n,xn)  2925 1451  174
data by Marcinkowski et al [Ma83]. This has been used to benchmark2925 1451  175
the Cu-65 data. Without adjusting any of the level density or pre-2925 1451  176
equilibrium parameters the GNASH calculation was in good agreement2925 1451  177
with these data. Hence we also adopted these parameters for the   2925 1451  178
whole energy region for Cu-63.                                    2925 1451  179
                                                                  2925 1451  180
****************************************************************  2925 1451  181
                                                                  2925 1451  182
REFERENCES                                                        2925 1451  183
                                                                  2925 1451  184
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[Ka77]  C. Kalbach, Z.Phys.A  283, 401 (1977)                     2925 1451  233
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   Specialists' Meeting on the Nucleon Nucleus Optical Model up to2925 1451  242
   200 MeV, Bruyeres-le-Chatel, November 13-15 1996. Available at 2925 1451  243
   http://db.nea.fr/html/science/om200/.                          2925 1451  244
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   Data for Accelerator-Driven Systems: Nuclear models, Experiment2925 1451  246
   and Data Libraries", to appear in Mucl. Instr. Meth. A (1998). 2925 1451  247
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   neutron and proton datafiles up to 150 MeV for 63Cu and 65Cu", 2925 1451  249
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   JEFF report (1998).                                            2925 1451  251
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[Sa60]  G.L. Salmon, Nucl.Phys. 21, 15 (1960)                     2925 1451  264
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   LA-12343-MS (1992)                                             2925 1451  266
                                                                  2925 1451  267
 **************************************************************** 2925 1451  268
                                                                  2925 1451  269
 ENDF/B-VI MOD 3 Revision, July 1991 (ORNL)                       2925 1451  270
                                                                  2925 1451  271
 MOD 3 changes                                                    2925 1451  272
   1) Corrections to MF=6, MT=65 at 17.0 MeV to prevent negative  2925 1451  273
      values in the angular distribution.                         2925 1451  274
   2) Corrections to MF=33, MT=102                                2925 1451  275
                                                                  2925 1451  276
 **************************************************************** 2925 1451  277
                                                                  2925 1451  278
 * Note there was no MOD 2 released.                              2925 1451  279
                                                                  2925 1451  280
 **************************************************************** 2925 1451  281
                                                                  2925 1451  282
 ENDF/B-VI MOD 1 Evaluation, October 1989, D. Hetrick, F.Y. Fu,   2925 1451  283
           D. Larson (ORNL)                                       2925 1451  284
                                                                  2925 1451  285
   This work employed several nuclear model codes including the   2925 1451  286
 optical-model code GENOA [1], the Distorted Wave Born            2925 1451  287
 Approximation (DWBA) program DWUCK [2], and the Hauser-Feshbach  2925 1451  288
 code TNG [3,4]. The TNG code provides energy and angular         2925 1451  289
 distributions of particles emitted in the compound and pre-      2925 1451  290
 compound reactions, ensures consistency among all reactions, and 2925 1451  291
 maintains energy balance. Details pertinent to the contents of   2925 1451  292
 this evaluation and extensive comparisons of calculations with   2925 1451  293
 experimental data can be found in reference [5].                 2925 1451  294
                                                                  2925 1451  295
----- DESCRIPTION OF FILES                                        2925 1451  296
(MF-MT)                                                           2925 1451  297
  1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS.         2925 1451  298
  2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB[6].  POINT2925 1451  299
        WISE RECONSTRUCTION COMPARED WITH DATA [7] SHOWED POORER  2925 1451  300
        FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT 2925 1451  301
        99.5 KEV.  REICH-MOORE PARAMETERS ARE GIVEN.  AGREEMENT   2925 1451  302
        WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND 2925 1451  303
        FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN       2925 1451  304
        AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND     2925 1451  305
        COMPARED WITH THE BINNED DATA.  THIS IS PROBABLY DUE TO   2925 1451  306
        TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES    2925 1451  307
        SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION.             2925 1451  308
        NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2925 1451  309
        OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE       2925 1451  310
        PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON    2925 1451  311
        A FINER ENERGY GRID THAN GIVEN IN 4/2.                    2925 1451  312
  3-1   THE TOTAL CROSS SECTION IS GIVEN BY RESONANCE PARAMETERS  2925 1451  313
        FROM 1.E-5 EV TO 99.5 KEV.  FROM 1.E-5 TO 1 EV, -0.9B IS  2925 1451  314
        GIVEN TO REDUCE THE ELASTIC AND GIVE THE CORRECT TOTAL    2925 1451  315
        THERMAL CROSS SECTION (9.6 B).  FROM 1 EV TO 170 EV THIS  2925 1451  316
        GOES LINEARLY TO ZERO.  A SMALL CONTRIBUTION FROM 3/102 IS2925 1451  317
        REQUIRED FROM 60 TO 99.5 KEV, WHICH WHEN ADDED TO 2/151   2925 1451  318
        REPRODUCES THE CAPTURE DATA.  FROM 99.5 KEV TO 1.12 MEV   2925 1451  319
        CU63 DATA FROM [7] IS USED, AFTER APPROPRIATE AVERAGING.  2925 1451  320
        ABOVE THIS, NO ISOTOPIC DATA IS AVAILABLE.  FROM 1.12 TO  2925 1451  321
        4.0 MEV,NAT CU  DATA OF PEREY [8] USED IN V5 IS RETAINED. 2925 1451  322
        FROM 4.0 TO 20 MEV, NAT CU DATA OF LARSON ET.AL [9] IS    2925 1451  323
        AVERAGED AND USED.  COMPARISONS FROM 1.2 TO 4.5           2925 1451  324
        MEV WITH AVERAGED ARGONNE DATA FOR NAT CU [10] SHOW       2925 1451  325
        1% AGREEMENT.                                             2925 1451  326
  3-2   ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY        2925 1451  327
        SUBTRACTING THE NONELASTIC (3-3) FROM THE TOTAL.  THE     2925 1451  328
        THERMAL VALUE OF 5.1 B IS REPRODUCED.                     2925 1451  329
  3-102 (N,G) DATA TAKEN FROM RESONANCE PARAMETERS FROM 1.E-5 EVTO2925 1451  330
        99.5 KEV.  A SMALL BACKGROUND IS GIVEN HERE WHICH WHEN    2925 1451  331
        ADDED TO THE RESONACE CONTRIBUTION REPRODUCES EXPERIMENTAL2925 1451  332
        DATA,INCLUDING THE THERMAL VALUE OF 4.50B.  V5 DATA FROM  2925 1451  333
        99.5 KEV TO 20.0 MEV WERE REPLACED BY POINTS ON A CURVE   2925 1451  334
        DRAWN THROUGH DATA FROM THE CSISRS LIBRARY [5,13]; RESULTS2925 1451  335
        COMPARABLE TO EYE GUIDE IN REF [14].                      2925 1451  336
 ---------------------------------------------------------------- 2925 1451  337
 UNCERTAINTY FILES                                                2925 1451  338
        ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS       2925 1451  339
        REQUIRED BY ENDF/B-VI FORMATS                             2925 1451  340
                                                                  2925 1451  341
 33-1   TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 200 EV  2925 1451  342
        EXPLICIT FROM 200 EV TO 20 MEV, USING LB=0,1 AND 8.       2925 1451  343
 33-2   EXPLICIT FROM 1E-5 T0 200 EV, DERIVED FROM 200EV TO 20 MEV2925 1451  344
 33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW 2925 1451  345
        ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CSISRS 2925 1451  346
        DATA [5,13,14] FROM 99.5 KEV TO 20 MEV.                   2925 1451  347
 **************************************************************** 2925 1451  348
                                                                  2925 1451  349
 REFERENCES:                                                      2925 1451  350
                                                                  2925 1451  351
 [1] F.G. Perey, computer code GENOA, ORNL, unpublished (1967)    2925 1451  352
 [2] P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of           2925 1451  353
     Colorado, unpublished (1972)                                 2925 1451  354
 [3] C.Y. Fu, report ORNL/TM-7042 (1980); also, C.Y Fu,           2925 1451  355
     Symp. on Neutron Cross Sections from 10 to 50 MeV, Upton, NY,2925 1451  356
     May 1980, Brookhaven National Lab. report BNL-NCS-51245      2925 1451  357
     (1980) p.675                                                 2925 1451  358
 [4] K. Shibata and C.Y. Fu, report ORNL/TM-10093 (1986)          2925 1451  359
 [5] D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge report     2925 1451  360
     ORNL/TM-9083 [ENDF-337] (1984)                               2925 1451  361
 [6] S.F. Mughabghab, M. Divadeenam, and N.E. Holden, "Neutron    2925 1451  362
     Cross Sections, Vol. 1, Neutron Resonance Parameters and     2925 1451  363
     Thermal Cross Sections, Part A, Z=1-60," (Academic Press,    2925 1451  364
     1981)                                                        2925 1451  365
 [7] M.S. Pandey, J.B. Garg and J.A. Harvey, Phys.Rev. C 15, 600  2925 1451  366
     (1977), and private communication.                           2925 1451  367
 [8] F.G. Perey, private communication (1977)                     2925 1451  368
 [9] D.C. Larson, Symp. on Neutron Cross Sections from 10 to 50   2925 1451  369
     MeV, Upton, NY, May 1980, Brookhaven National Lab. report    2925 1451  370
     BNL-NCS-51245 (1980) p.277                                   2925 1451  371
[10] P. Guenther, D.L. Smith, A.B. Smith and J.F. Whalen, Nucl.   2925 1451  372
     Phys. A, 448, 280 (1986) [CSISRS data set 12869/002], and    2925 1451  373
     W.P. Poenitz and J.F. Whalen, Argonne report ANL/NDM-80      2925 1451  374
     (1983) [CSISRS data set 12853]                               2925 1451  375
[11] D.M. Hetrick and C.Y. Fu, Oak Ridge report ORNL/TM-7341      2925 1451  376
     [ENDF-303] (1980)                                            2925 1451  377
[12] C.Y. Fu and D.M. Hetrick, Proc. Fourth ASTM-Euratom Symp.    2925 1451  378
     on Reactor Dosimetry, Gaithersburg, Maryland, March 22-26,   2925 1451  379
     1982 (U.S. National Bureau of Standards) p.877               2925 1451  380
[13] CSISRS Library, National Nuclear Data Center, Brookhaven     2925 1451  381
     National Laboratory, Upton, N.Y. 11973.                      2925 1451  382
[14] V. McLane, C.L. Dunford and P.F. Rose, "Neutron Cross        2925 1451  383
     Sections, Vol. 2, Neutron Cross Section Curves" (Academic    2925 1451  384
     Press, 1988)                                                 2925 1451  385
[15] S.M. Qaim, Radiochimica Acta, 25, 13 (1978)                  2925 1451  386
[16] M.G. Delfini, J. Kopecky, R.E. Chrien et al., Nucl.Phys.     2925 1451  387
     A404, 250 (1983)                                             2925 1451  388
                                                                  2925 1451  389
***************************************************************** 2925 1451  390
********   End of (N,2N), (N.G) bibliographical component ******* 2925 1451  391
***************************************************************** 2925 1451  392
***************************************************************** 2925 1451  393
********       Start of (N,A) bibliographical component   ******* 2925 1451  394
***************************************************************** 2925 1451  395
------Russian Reactor Dosimetry File RRDF-2002                    2925 1451  396
***************************************************************** 2925 1451  397
Author  of evaluation: K.I.Zolotarev                              2925 1451  398
***************************************************************** 2925 1451  399
                                                                  2925 1451  400
                    ----- MF=3 MT=107 -----                       2925 1451  401
    Evaluation of Cu-63(n,a)Co-60m+g- excitation function was car-2925 1451  402
ried out by means of statistical analysis of cross sections from  2925 1451  403
data base prepared in the energy range 2 - 20 Mev. In the energy  2925 1451  404
range 3.56 - 19.55 MeV  input data base  was formed with using of 2925 1451  405
experimental data from ref. [1-19].  Cross section data  in  the  2925 1451  406
interval 2.0 - 3.5 MeV were taken from theoretical model calcula- 2925 1451  407
tion.  Experimental data  included  in  the input data base were  2925 1451  408
renormalized using new cross sections standards for monitor reac- 2925 1451  409
tions and new standards for decay data.                           2925 1451  410
    The special correction  was applied to the experimental data  2925 1451  411
[2,3,12,13,15,18]. Cross section data of A.Paulsen and H.Liskien  2925 1451  412
[2-3] measured in the energy region 12.09 - 19.55 MeV with using  2925 1451  413
T(d,n)He4 neutron source were multiplied to the factor 1.20805 .  2925 1451  414
Experimental data of Lu Hanlin et al. [12,18] , Wang Yongchag et  2925 1451  415
al. [13] and Konno et al. [15]  were multiplied  to  the factors  2925 1451  416
0.88110, 0.86000, 0.84377 and 1.060, respectively. The correction 2925 1451  417
factors were derived from preliminary evaluated  cross sections   2925 1451  418
integrals in the energy intervals 8.4 - 11.4 and 13 - 15 MeV .    2925 1451  419
    Data  of A.Paulsen and H.Liskien [2]  in  the energy  range   2925 1451  420
5.76 - 11.48 MeV  measured  with using  D(d,n)He3 , Be9(a,n)C12 , 2925 1451  421
C14(d,n)N15 , N15(d,n)O16  neutron sources  were rejected  due to 2925 1451  422
their inconsistency with precision measurements  of  G.Winkler et 2925 1451  423
al. [8]  and integral experimental data for U-235 fission neutron 2925 1451  424
spectrum [20-23]  and Cf-252 spontaneous fission neutron spectrum 2925 1451  425
[25-26]. Cross sections measured by J.Kantele and D.Gardner [27], 2925 1451  426
M.Bormann et al. [28], G.Maslov et al. [29] and K.Kayashima et al.2925 1451  427
[30]  were also rejected due to the big discrepancy with the main 2925 1451  428
bulk experimental data.                                           2925 1451  429
    The final procedure  evaluation of (n,a) excitation function  2925 1451  430
was carried out by means of Pade-2 code [31].                     2925 1451  431
    Evaluated excitation function for the reaction  Cu63(n,a)Co60 2925 1451  432
was tested  with using  integral experimental  data  [20-24]  for 2925 1451  433
U-235 thermal fission neutron spectrum and evaluated integral ex- 2925 1451  434
perimental data [32-33]  for Cf-252 spontaneous  fission  neutron 2925 1451  435
spectrum.  Calculated  and  measured average cross section values 2925 1451  436
for U-235 thermal fission neutron spectrum [34] and Cf-252 sponta-2925 1451  437
neous fission neutron spectrum [35] are given in the table 1.     2925 1451  438
                                                      Table 1     2925 1451  439
  2925 1451  440
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  2925 1451  441
  2925 1451  442
 U-235 neutron fission    0.53294        0.5269 +- 0.0316 [20]  2925 1451  443
                                         0.520  +- 0.040  [21]  2925 1451  444
                                         0.519  +- 0.035  [22]  2925 1451  445
                                         0.5273 +- 0.0156 [23]  2925 1451  446
                                         0.538  +- 0.015  [23]  2925 1451  447
                                         0.4935 +- 0.0242 [24]  2925 1451  448
  2925 1451  449
 CF-252 spont. fission    0.69248        0.709  +- 0.017  [25]  2925 1451  450
                                         0.675  +- 0.018  [26]  2925 1451  451
                                         0.6897 +- 0.0130 [32]  2925 1451  452
                                         0.6887 +- 0.0135 [33]  2925 1451  453
  2925 1451  454
                                                                  2925 1451  455
                    ----- MF=33 MT=107 -----                      2925 1451  456
    Uncertainties in the evaluated  excitation function  for the  2925 1451  457
reaction Cu-63(n,a)Co-60m+g are given in the form of relative co- 2925 1451  458
variance matrix for the 18-neutron energy groups (LB=5).  Covari- 2925 1451  459
ance matrix of uncertainties was calculated simultaneously  with  2925 1451  460
recommended cross section data by means of PADE-2 code.           2925 1451  461
    Eigenvalues  of the  6-th digits  relative covariance matrix  2925 1451  462
given in the 33-file are the following:                           2925 1451  463
                                                                  2925 1451  464
    9.39333E-10    1.02943E-09    1.18681E-09    1.49652E-09      2925 1451  465
    2.03282E-09    2.85265E-09    3.69906E-09    6.46604E-09      2925 1451  466
    7.96491E-09    7.69999E-08    4.12497E-06    6.99817E-04      2925 1451  467
    1.07280E-03    1.33316E-03    1.89667E-03    4.15078E-03      2925 1451  468
    6.87556E-03    8.81528E-03                                    2925 1451  469
                                                                  2925 1451  470
References :                                                      2925 1451  471
 1. B.Czapp, H.Vonach  Oesterr. Akad. Wiss, Math, Naturw.         2925 1451  472
    Anzeiger, v.97, p.13, January 1960                            2925 1451  473
 2. A.Paulsen, H.Liskien  Nukleonik, v.10, p.91, July 1967        2925 1451  474
 3. A.Paulsen  Zeitschrift f. Phys., v.205, p.226, August 1967    2925 1451  475
 4. R.C.Barrall et al.  Report AFWL-TR-68-134, March 1969         2925 1451  476
 6. G.Winkler  Nucl. Sci. Eng., v.67, n.2, p.260, August 1978     2925 1451  477
 8. G.Winkler, D.L.Smith, J.W.Meadows  Nucl. Sci. Eng., v.76,     2925 1451  478
    p.30, October 1980                                            2925 1451  479
 9. U.Garuska et al.  Prog. Report INDC(POL)-11, p.15, July 1980  2925 1451  480
10. O.I.Artem'ev et al.  Atomnaja Energija (Sov.), v.49, n.3,     2925 1451  481
    p.195, September 1980                                         2925 1451  482
11. L.R.Greenwood  Progress Report ASTM-STP-956, p.743, 1987      2925 1451  483
12. Lu Hanlin et al.  China Journal of Nuclear Phys., v.12. n.4,  2925 1451  484
    p. 373, 1990                                                  2925 1451  485
13. Wang Yongchang et al. Chinese J. High Energy Phys. and Nucl.  2925 1451  486
    Phys., v.14, p.919, October 1990                              2925 1451  487
14. J.Csikai, C.M.Buczko, R.Pepelnik, H.M.Agrawal Annals of Nucl. 2925 1451  488
    Energy, v.18, n.1, p.1, 1991                                  2925 1451  489
15. C.Konno et al.  Report JAERI-1329, October 1993               2925 1451  490
16. J.W.Meadows et al.  Annals of Nucl. Energy, v.23, p.877, 1996 2925 1451  491
17. A.A.Filatenkov et al.  VANT, Ser.: Yadernye Konstanty, v.2,   2925 1451  492
    p.8, Moscow, 1996                                             2925 1451  493
18. Lu Hanlin et al.  Report INDC(CPR)-045, IAEA, October 1998    2925 1451  494
19. A.A.Filatenkov et al.  Report RI-252, St.Petersburg, May 1999 2925 1451  495
20. R.Lloret Progress Report EANDC(E)-57, p.172, February 1965    2925 1451  496
21. A.Fabry, J.P.Deworm  Progress Report EANDC(E)-66, p.125,      2925 1451  497
    February 1966                                                 2925 1451  498
22. K.Kobayashi et al.  Nucl. Sci. Techn., v.13, p.531, Oct. 1976 2925 1451  499
23. L.P.Geraldo et al.  Radiochimica Acta, v.57, pp.63-67, 1992   2925 1451  500
24. W.Mannhart  Progress Report INDC(Ger)-045, pp.40-43, 1999     2925 1451  501
25. G.Winkler et al.  Nucl. Sci. Eng., v.78, p.415, August 1981   2925 1451  502
26. W.Mannhart  Proc. of Int. Conf. Nuclear Data for Science and  2925 1451  503
    Technology, 6-10 September 1982, Antwerp, Holland, D.Reidel   2925 1451  504
    Publishing Company, p.429                                     2925 1451  505
27. J.Kantele, D.Gardner  Nucl. Phys., v.35, p.353, 1962          2925 1451  506
28. M.Bormann et al.  Nucl. Phys., v.A186, p.65, May 1972         2925 1451  507
29. G.N.Maslov, F.Nasyrov, N.F.Pashkin  Yadernye Konstanty, v.9,  2925 1451  508
    p.50, Obninsk, 1972                                           2925 1451  509
30. K.Kayashima et al.  Prog. Rep. NEANDC(J)-61U, p.94, Sep. 1979 2925 1451  510
31. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          2925 1451  511
32. W.Mannhart   Handbook on Nuclear Activation Cross Sections,   2925 1451  512
    IAEA Technical Report series No.273, p.413, 1987              2925 1451  513
33. W.Mannhart  Validation of Differential Cross Sections with    2925 1451  514
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2925 1451  515
    September 2002                                                2925 1451  516
34. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2925 1451  517
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              2925 1451  518
35. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        2925 1451  519
***************************************************************** 2925 1451  520
********       End of (N,A)bibliographical component      ******* 2925 1451  521
***************************************************************** 2925 1451  522
                                                                  2925 1451  523
                                                                  2925 1451  524
                                                                  2925 1451  525
 ************************ C O N T E N T S *********************** 2925 1451  526
 ***************** Program LINEAR (VERSION 2002-1) ***************2925 1451  527
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2925 1451  528
 Data Linearized to Within an Accuracy of .100000000 per-cent     2925 1451  529
 ***************** Program RECENT (VERSION 2002-1) ***************2925 1451  530
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2925 1451  531
 Data Linearized to within an Accuracy of .100000000 per-cent     2925 1451  532
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2925 1451  533
 Data Doppler Broadened to 300.000000 Kelvin                      2925 1451  534
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2925 1451  535
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2925 1451  536
 ***************** Program FIXUP (Version 2002-1) ****************2925 1451  537
 Corrected ZA/AWR in All Sections-----------------------------Yes 2925 1451  538
 Corrected Thresholds-----------------------------------------Yes 2925 1451  539
 Extended Cross Sections to 20 MeV----------------------------No  2925 1451  540
 Allow Cross Section Deletion---------------------------------No  2925 1451  541
 Allow Cross Section Reconstruction---------------------------No  2925 1451  542
 Make All Cross Sections Non-Negative-------------------------Yes 2925 1451  543
 Delete Energies Not in Ascending Order-----------------------Yes 2925 1451  544
 Deleted Duplicate Points-------------------------------------Yes 2925 1451  545
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2925 1451  546
 Check for Legal MF/MT Numbers--------------------------------Yes 2925 1451  547
 Allow Creation of Missing Sections---------------------------No  2925 1451  548
 Allow Insertion of Energy Points-----------------------------No  2925 1451  549
 Create Uniform Energy Grid-----------------------------------No  2925 1451  550
 Delete Section if Cross Section =0 at All Energies-----------Yes 2925 1451  551
 ***************** Program GROUPIE (VERSION 2002-1) **************2925 1451  552
 Unshielded Group Averages Using  640 Groups                      2925 1451  553
 Weighting Spectrum: Flat (Constant) Spectrum                     2925 1451  554
                                1        451        562          52925 1451  555
                                2        151          4          12925 1451  556
                                3         16         34          12925 1451  557
                                3        102        217          52925 1451  558
                                3        107         63          12925 1451  559
                               33         16         58          12925 1451  560
                               33        102         23          32925 1451  561
                               33        107         38          12925 1451  562
                                                                  2925 1  099999
                                                                  2925 0  0    0
 2.90630E+4 6.23890E+1          0          0          1          02925 2151    1
 2.90630E+4 1.00000E+0          0          0          1          02925 2151    2
 1.00000E-5 9.95000E+4          0          0          0          02925 2151    3
 1.50000E+0 6.70000E-1          0          0          0          02925 2151    4
                                                                  2925 2  099999
                                                                  2925 0  0    0
 2.90630E+4 6.23890E+1          0          0          0          02925 3 16    1
-1.08540E+7-1.08540E+7          0          0          1         912925 3 16    2
         91          1                                            2925 3 16    3
 11000000.0 .000429103 11100000.0 .002018629 11200000.0 .0036728762925 3 16    4
 11300000.0 .006750000 11400000.0 .011250000 11500000.0 .0182500002925 3 16    5
 11600000.0 .027750000 11700000.0 .039500000 11800000.0 .0535000002925 3 16    6
 11900000.0 .067948571 12000000.0 .082845714 12100000.0 .0977428572925 3 16    7
 12200000.0 .113333107 12300000.0 .133082000 12400000.0 .1535240002925 3 16    8
 12500000.0 .173966000 12600000.0 .194408000 12700000.0 .2150142502925 3 16    9
 12800000.0 .236606000 12900000.0 .258362000 13000000.0 .2801180002925 3 16   10
 13100000.0 .301874000 13200000.0 .322831375 13300000.0 .3389970002925 3 16   11
 13400000.0 .354364000 13500000.0 .369731000 13600000.0 .3850980002925 3 16   12
 13700000.0 .400465000 13800000.0 .415832000 13900000.0 .4311990002925 3 16   13
 14000000.0 .446566000 14100000.0 .461933000 14200000.0 .4772576252925 3 16   14
 14300000.0 .492328000 14400000.0 .507356000 14500000.0 .5223840002925 3 16   15
 14600000.0 .537412000 14700000.0 .551971000 14800000.0 .5637160002925 3 16   16
 14900000.0 .574992000 15000000.0 .586268000 15100000.0 .5975440002925 3 16   17
 15200000.0 .608696250 15300000.0 .619106000 15400000.0 .6293920002925 3 16   18
 15500000.0 .639678000 15600000.0 .649964000 15700000.0 .6598785002925 3 16   19
 15800000.0 .667564000 15900000.0 .674878000 16000000.0 .6821920002925 3 16   20
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 16400000.0 .704348000 16500000.0 .708112000 16600000.0 .7118760002925 3 16   22
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 4600000.00 .000936931 4700000.00 .001118145 4800000.00 .0013251452925 3107   12
 4900000.00 .001559945 5000000.00 .001824395 5100000.00 .0021201152925 3107   13
 5200000.00 .002448415 5300000.00 .002810215 5400000.00 .0032059852925 3107   14
 5500000.00 .003635675 5600000.00 .004098705 5700000.00 .0045939402925 3107   15
 5800000.00 .005119685 5900000.00 .005673745 6000000.00 .0062534952925 3107   16
 6100000.00 .006855950 6200000.00 .007481480 6300000.00 .0081195202925 3107   17
 6400000.00 .008770100 6500000.00 .009433220 6600000.00 .0100963402925 3107   18
 6700000.00 .010761520 6800000.00 .011428760 6900000.00 .0120960002925 3107   19
 7000000.00 .012763240 7100000.00 .013430480 7200000.00 .0140867502925 3107   20
 7300000.00 .014732050 7400000.00 .015377350 7500000.00 .0160226502925 3107   21
 7600000.00 .016654800 7700000.00 .017273800 7800000.00 .0178928002925 3107   22
 7900000.00 .018511800 8000000.00 .019130800 8100000.00 .0197498002925 3107   23
 8200000.00 .020365669 8300000.00 .020978406 8400000.00 .0215911442925 3107   24
 8500000.00 .022203881 8600000.00 .022816619 8700000.00 .0234293562925 3107   25
 8800000.00 .024042094 8900000.00 .024654831 9000000.00 .0252811332925 3107   26
 9100000.00 .025921000 9200000.00 .026560867 9300000.00 .0272007332925 3107   27
 9400000.00 .027840600 9500000.00 .028480467 9600000.00 .0291384502925 3107   28
 9700000.00 .029814550 9800000.00 .030490650 9900000.00 .0311667502925 3107   29
 10000000.0 .031842850 10100000.0 .032518950 10200000.0 .0331950502925 3107   30
 10300000.0 .033876856 10400000.0 .034564367 10500000.0 .0352518782925 3107   31
 10600000.0 .035939389 10700000.0 .036626900 10800000.0 .0373144112925 3107   32
 10900000.0 .038001922 11000000.0 .038689433 11100000.0 .0393769442925 3107   33
 11200000.0 .040038313 11300000.0 .040673538 11400000.0 .0413087632925 3107   34
 11500000.0 .041943988 11600000.0 .042545000 11700000.0 .0431118002925 3107   35
 11800000.0 .043678600 11900000.0 .044203383 12000000.0 .0446861502925 3107   36
 12100000.0 .045168917 12200000.0 .045598283 12300000.0 .0459742502925 3107   37
 12400000.0 .046350217 12500000.0 .046662700 12600000.0 .0469117002925 3107   38
 12700000.0 .047160700 12800000.0 .047350950 12900000.0 .0474824502925 3107   39
 13000000.0 .047564250 13100000.0 .047596350 13200000.0 .0475778002925 3107   40
 13300000.0 .047508600 13400000.0 .047389050 13500000.0 .0472191502925 3107   41
 13600000.0 .047000400 13700000.0 .046732800 13800000.0 .0464083172925 3107   42
 13900000.0 .046026950 14000000.0 .045645583 14100000.0 .0452040172925 3107   43
 14200000.0 .044702250 14300000.0 .044200483 14400000.0 .0436496502925 3107   44
 14500000.0 .043049750 14600000.0 .042449850 14700000.0 .0418086502925 3107   45
 14800000.0 .041126150 14900000.0 .040443650 15000000.0 .0397611502925 3107   46
 15100000.0 .039047329 15200000.0 .038302186 15300000.0 .0375570432925 3107   47
 15400000.0 .036811900 15500000.0 .036066757 15600000.0 .0353216142925 3107   48
 15700000.0 .034576471 15800000.0 .033832900 15900000.0 .0330909002925 3107   49
 16000000.0 .032348900 16100000.0 .031606900 16200000.0 .0308649002925 3107   50
 16300000.0 .030122900 16400000.0 .029401975 16500000.0 .0287021252925 3107   51
 16600000.0 .028002275 16700000.0 .027302425 16800000.0 .0266232332925 3107   52
 16900000.0 .025964700 17000000.0 .025306167 17100000.0 .0246673332925 3107   53
 17200000.0 .024048200 17300000.0 .023429067 17400000.0 .0228303332925 3107   54
 17500000.0 .022252000 17600000.0 .021673667 17700000.0 .0211157502925 3107   55
 17800000.0 .020578250 17900000.0 .020040750 18000000.0 .0195231502925 3107   56
 18100000.0 .019025450 18200000.0 .018527750 18300000.0 .0180491172925 3107   57
 18400000.0 .017589550 18500000.0 .017129983 18600000.0 .0166884172925 3107   58
 18700000.0 .016264850 18800000.0 .015841283 18900000.0 .0154346002925 3107   59
 19000000.0 .015044800 19100000.0 .014655000 19200000.0 .0142808172925 3107   60
 19300000.0 .013922250 19400000.0 .013563683 19500000.0 .0132195502925 3107   61
 19600000.0 .012889850 19700000.0 .012560150 19800000.0 .0122416252925 3107   62
 19900000.0 .011934275 20000000.0 0.0                             2925 3107   63
                                                                  2925 3  099999
                                                                  2925 0  0    0
 2.90630E+4 6.23890E+1          0          0          0          1292533 16    1
 0.000000+0 0.000000+0          0         16          0          4292533 16    2
 0.000000+0 0.000000+0          1          5        153         17292533 16    3
 1.000000-5 1.100000+7 1.130000+7 1.225000+7 1.275000+7 1.325000+7292533 16    4
 1.375000+7 1.425000+7 1.475000+7 1.525000+7 1.575000+7 1.625000+7292533 16    5
 1.675000+7 1.750000+7 1.850000+7 1.950000+7 2.000000+7 0.000000+0292533 16    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533 16   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533 16   11
 1.568800-1 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533 16   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533 16   13
 0.000000+0 0.000000+0 1.649800-2 1.263100-3 5.039300-4 7.932200-5292533 16   14
 9.138100-5 3.029900-5 1.833000-5 1.758900-4-7.656800-5 9.709000-5292533 16   15
 5.961700-5 1.228200-5 2.074900-4 7.240200-3 1.675800-3 2.178400-4292533 16   16
 2.160400-4 1.263500-4 1.443500-4 3.289900-4 1.648100-4 1.433800-4292533 16   17
 1.842100-4 8.463600-5 4.954500-4 8.182900-3 1.627500-4 2.678500-4292533 16   18
 1.149800-4 1.672700-4 2.374300-4 2.171400-4 1.300400-4 1.671000-4292533 16   19
 1.078100-4 4.957700-4 7.246600-4 1.456500-4 5.954200-5 6.188600-5292533 16   20
 1.737000-4 1.511300-4 5.528100-5 1.205500-4-6.040100-6 1.333700-4292533 16   21
 7.711100-4-1.807300-5 9.487900-5 8.962400-5 9.446400-5 7.407300-5292533 16   22
 8.608700-5 5.145100-5 1.174900-4 1.573700-4 1.440200-4 9.828400-5292533 16   23
 9.177300-5 1.207300-4 1.211400-4 9.613200-5 1.039800-4 3.204500-4292533 16   24
 2.009500-5 1.154400-4 1.379200-4 1.309700-4 1.265200-4 8.967900-5292533 16   25
 6.769700-4 1.521600-4 1.301200-4 1.714800-4 4.253100-5 1.696700-4292533 16   26
 5.824400-4-2.261500-5 2.014700-4 2.037800-5 1.756900-4 3.814400-4292533 16   27
 2.641600-5 1.714800-4 5.399600-5 5.812700-4-1.256900-4 3.553400-4292533 16   28
 6.634900-4-3.627400-4 1.521200-3                                 292533 16   29
 0.000000+0 0.000000+0         17          4         68         34292533 16   30
 1.000000-5 0.000000+0 1.100000+7-1.000000+0 1.130000+7-6.000000-1292533 16   31
 1.225000+7-1.000000+0 1.275000+7-1.000000+0 1.325000+7-1.000000+0292533 16   32
 1.375000+7-1.000000+0 1.425000+7-1.000000+0 1.475000+7-1.000000+0292533 16   33
 1.525000+7-1.000000+0 1.575000+7-1.000000+0 1.625000+7-1.000000+0292533 16   34
 1.675000+7-1.000000+0 1.750000+7-1.000000+0 1.850000+7-1.000000+0292533 16   35
 1.950000+7-1.000000+0 2.000000+7 0.000000+0 1.000000-5 0.000000+0292533 16   36
 1.102600+7 0.000000+0 1.130000+7 3.960800-1 1.225000+7 1.284400-1292533 16   37
 1.275000+7 8.508900-2 1.325000+7 9.046000-2 1.375000+7 2.692000-2292533 16   38
 1.425000+7 2.776900-2 1.475000+7 1.254500-2 1.525000+7 1.790100-2292533 16   39
 1.575000+7 2.601900-2 1.625000+7 2.413400-2 1.675000+7 1.953000-2292533 16   40
 1.750000+7 2.410900-2 1.850000+7 2.575800-2 1.950000+7 3.900300-2292533 16   41
 2.000000+7 0.000000+0                                            292533 16   42
 0.000000+0 0.000000+0          0          1         40         20292533 16   43
 1.000000-5 0.000000+0 1.100000+7 0.000000+0 1.130000+7 8.471500-2292533 16   44
 1.150000+7 8.471500-2 1.170000+7 8.471500-2 1.190000+7 8.471500-2292533 16   45
 1.225000+7 1.484800-2 1.275000+7 6.516200-3 1.325000+7 7.364600-3292533 16   46
 1.375000+7 6.522000-4 1.425000+7 6.940000-4 1.475000+7 1.416300-4292533 16   47
 1.525000+7 2.884100-4 1.575000+7 6.092700-4 1.625000+7 5.242000-4292533 16   48
 1.675000+7 3.432900-4 1.750000+7 5.231400-4 1.850000+7 5.971400-4292533 16   49
 1.950000+7 1.369100-3 2.000000+7 0.000000+0                      292533 16   50
 0.000000+0 0.000000+0          0          8         40         20292533 16   51
 1.000000-5 0.000000+0 1.100000+7 0.000000+0 1.130000+7 1.906100-7292533 16   52
 1.150000+7 1.715500-6 1.170000+7 9.942200-6 1.190000+7 3.445300-5292533 16   53
 1.225000+7 2.093200-5 1.275000+7 3.342100-5 1.325000+7 8.570500-5292533 16   54
 1.375000+7 1.160100-5 1.425000+7 1.756700-5 1.475000+7 4.802800-6292533 16   55
 1.525000+7 1.187800-5 1.575000+7 2.951100-5 1.625000+7 2.828100-5292533 16   56
 1.675000+7 1.956500-5 1.750000+7 3.216400-5 1.850000+7 4.021600-5292533 16   57
 1.950000+7 1.010100-4 2.000000+7 0.000000+0                      292533 16   58
                                                                  292533  099999
 2.90630E+4 6.23890E+1          0          0          0          1292533102    1
 0.000000+0 0.000000+0          0        102          0          3292533102    2
 0.000000+0 0.000000+0          0          1          8          4292533102    3
 1.000000-5 1.600000-3 1.000000+3 2.500000-3 2.000000+6 3.600000-3292533102    4
 2.000000+7 0.000000+0                                            292533102    5
 0.000000+0 0.000000+0          0          1         46         23292533102    6
 1.000000-5 3.960000-4 2.530000-2 9.900000-5 1.000000-1 9.900000-5292533102    7
 1.000000+0 9.900000-5 2.000000+0 9.900000-5 5.000000+0 9.900000-5292533102    8
 1.000000+1 9.900000-5 2.000000+1 9.900000-5 5.000000+1 9.900000-5292533102    9
 1.000000+2 9.900000-5 2.000000+2 3.960000-4 5.000000+2 3.960000-4292533102   10
 2.000000+3 9.900000-3 5.000000+4 3.960000-2 1.000000+5 2.227500-2292533102   11
 1.000000+6 9.900000-3 2.000000+6 9.900000-3 3.000000+6 9.900000-3292533102   12
 4.000000+6 3.960000-2 6.000000+6 3.960000-2 8.000000+6 3.960000-2292533102   13
 1.000000+7 3.960000-2 2.000000+7 0.000000+0                      292533102   14
 0.000000+0 0.000000+0          0          8         46         23292533102   15
 1.000000-5 5.843100-5 2.530000-2 1.241300-5 1.000000-1 6.956500-6292533102   16
 1.000000+0 3.461000-7 2.000000+0 1.780400-7 5.000000+0 6.724400-8292533102   17
 1.000000+1 3.020600-8 2.000000+1 1.385600-8 5.000000+1 3.880000-9292533102   18
 1.000000+2 1.215200-9 2.000000+2 3.172900-9 5.000000+2 2.856700-5292533102   19
 2.000000+3 1.138900-5 5.000000+4 4.542800-7 1.000000+5 1.780400-7292533102   20
 1.000000+6 1.822500-8 2.000000+6 4.225000-9 3.000000+6 3.136000-9292533102   21
 4.000000+6 1.000000-8 6.000000+6 6.833800-9 8.000000+6 5.184000-9292533102   22
 1.000000+7 4.096000-9 2.000000+7 0.000000+0                      292533102   23
                                                                  292533  099999
 2.90630E+4 6.23890E+1          0          0          0          1292533107    1
 0.000000+0 0.000000+0          0        107          0          1292533107    2
 0.000000+0 0.000000+0          1          5        210         20292533107    3
 1.000000-5 2.200000+6 4.500000+6 5.000000+6 6.000000+6 7.000000+6292533107    4
 8.000000+6 9.000000+6 1.000000+7 1.100000+7 1.200000+7 1.300000+7292533107    5
 1.400000+7 1.450000+7 1.500000+7 1.600000+7 1.700000+7 1.800000+7292533107    6
 1.900000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533107    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533107    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0292533107    9
 0.000000+0 0.000000+0 0.000000+0 3.902680-3 2.149090-3 7.948570-4292533107   10
 5.549280-5 1.029480-4 3.315760-4 4.150520-4 3.335650-4 1.632360-4292533107   11
 4.687710-6-5.850760-5-3.540730-5 3.810960-6 6.278900-5 9.816090-5292533107   12
 4.445110-5-1.103690-4-3.652170-4 2.048910-3 1.277850-3 5.023710-4292533107   13
 3.104390-4 4.303990-4 5.159110-4 4.627090-4 2.978470-4 1.072940-4292533107   14
-9.929380-6-2.363430-5 6.667170-7 5.510420-5 1.089130-4 9.101280-5292533107   15
-2.337240-5-2.412000-4 1.403750-3 1.139720-3 7.598930-4 5.295980-4292533107   16
 4.362880-4 3.941200-4 3.411740-4 2.492870-4 1.306720-4 4.805720-5292533107   17
 9.034280-6-1.641020-5 1.661120-6 6.958950-5 1.707410-4 2.942290-4292533107   18
 1.430690-3 1.171940-3 7.971110-4 5.514220-4 4.345810-4 3.760900-4292533107   19
 3.055560-4 1.896340-4 8.544220-5 2.295550-5-3.706030-5-4.438810-5292533107   20
 4.268180-5 2.163080-4 4.676900-4 1.230320-3 1.067120-3 8.606320-4292533107   21
 6.657200-4 4.806270-4 3.023890-4 1.475950-4 6.104790-5 2.518420-5292533107   22
 3.893420-6 1.881610-5 7.051740-5 1.450370-4 2.353030-4 1.167910-3292533107   23
 1.098490-3 9.064420-4 6.368410-4 3.512730-4 1.303170-4 3.773650-5292533107   24
 1.762610-5 3.077580-5 8.134670-5 1.278940-4 1.424820-4 1.145190-4292533107   25
 1.153480-3 1.034720-3 7.810150-4 4.620260-4 1.832590-4 5.101270-5292533107   26
 1.413080-5 2.017000-5 8.668080-5 1.691200-4 2.283950-4 2.472330-4292533107   27
 1.019520-3 8.586540-4 5.832950-4 2.813990-4 1.006260-4 2.759680-5292533107   28
-6.493400-6 4.651990-5 1.727150-4 3.297290-4 4.943410-4 8.217660-4292533107   29
 6.464730-4 3.759330-4 1.718880-4 6.780650-5-1.364010-5 9.720900-7292533107   30
 1.407710-4 3.698800-4 6.635980-4 5.910990-4 4.124830-4 2.402880-4292533107   31
 1.360380-4 3.274150-5 2.902680-6 1.040010-4 3.151620-4 6.171420-4292533107   32
 3.612330-4 2.787220-4 2.169140-4 1.413740-4 9.211770-5 1.194900-4292533107   33
 2.202080-4 3.862950-4 2.811990-4 2.707110-4 2.463720-4 2.133570-4292533107   34
 1.939780-4 1.950960-4 2.180510-4 2.960220-4 3.144670-4 3.107020-4292533107   35
 2.817370-4 2.377330-4 1.849270-4 3.947940-4 4.559440-4 4.588000-4292533107   36
 4.126890-4 3.275050-4 6.282220-4 7.551020-4 8.366480-4 8.809310-4292533107   37
 1.092850-3 1.456080-3 1.843700-3 2.235280-3 3.158140-3 4.788580-3292533107   38
                                                                  292533  099999
                                                                  2925 0  0    0
                                                                     0 0  0    0
 2.90650E+4 6.43700E+1          0          0         34         102931 1451    1
 0.0        0.0                 0          0          0          62931 1451    2
 1.00000E+0 1.50000E+8          0          0         10       20022931 1451    3
 3.00000E+2 0.0                 1          0        384          42931 1451    4
 29-Cu- 65  LANL,ORNL EVAL-FEB98 A.KONING,M.CHADWICK,HETRICK      2931 1451    5
                      DIST-Feb2002                                2931 1451    6
----IRDF-2002         MATERIAL 2931                               2931 1451    7
-----INCIDENT NEUTRON DATA                                        2931 1451    8
------ENDF-6 FORMAT                                               2931 1451    9
******************************************************************2931 1451   10
  29-Cu- 65 LANL,ORNL EVAL-FEB98 A.KONING,M.CHADWICK,HETRICK      2931 1451   11
 Ch98,Ch99            DIST-SEP 1 REV4-                 20010926   2931 1451   12
----ENDF/B-VI         MATERIAL 2931         REVISION 4            2931 1451   13
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2931 1451   14
DOSIMETRY                                                         2931 1451   15
******************************************************************2931 1451   16
                                                                  2931 1451   17
 **************************************************************** 2931 1451   18
                                                                  2931 1451   19
 ENDF/B-VI MOD 5 Revision, May 2000, S.C. Frankle, R.C. Reedy,    2931 1451   20
                 P.G. Young (LANL)                                2931 1451   21
                                                                  2931 1451   22
 The secondary gamma-ray spectrum for radiative capture (MF 12,   2931 1451   23
 MT 102) has been updated for new experimental data at incident   2931 1451   24
 neutron energies up to 1 keV.                                    2931 1451   25
 The MF=12, MT=102 yields above 1 keV were adjusted slightly to   2931 1451   26
 force energy conservation.                                       2931 1451   27
 The Q-value for radiative capture was also updated in File 3.    2931 1451   28
 Details of these changes are described in Frankel et al. [Fr01]. 2931 1451   29
                                                                  2931 1451   30
 **************************************************************** 2931 1451   31
                                                                  2931 1451   32
 ENDF/B-VI MOD 4 Evaluation, February 1998, A.J. Koning (ECN),    2931 1451   33
                 M.B. Chadwick, P.G. Young (LANL)                 2931 1451   34
                                                                  2931 1451   35
 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code     2931 1451   36
   in cooperation with ECN Petten.                                2931 1451   37
                                                                  2931 1451   38
   This evaluation provides a complete representation of the      2931 1451   39
 nuclear data needed for transport, damage, heating,              2931 1451   40
 radioactivity, and shielding applications over the incident      2931 1451   41
 neutron energy range from 1.0E-11 to 150 MeV.  The discussion    2931 1451   42
 here is divided into the region below and above 20 MeV.          2931 1451   43
                                                                  2931 1451   44
INCIDENT NEUTRON ENERGIES < 20 MeV                                2931 1451   45
                                                                  2931 1451   46
  Below 20 MeV the evaluation is based completely on the ENDF/B-  2931 1451   47
VI (Release 2) evaluation by D. Hetrick, C.Y. Fu, and D. Larson.  2931 1451   48
                                                                  2931 1451   49
INCIDENT NEUTRON ENERGIES > 20 MeV                                2931 1451   50
                                                                  2931 1451   51
  The ENDF/B-VI Release 2 evaluation extends to 20 MeV and        2931 1451   52
includes cross sections and energy-angle data for all             2931 1451   53
significant reactions.  The present evaluation utilizes a more    2931 1451   54
compact composite reaction spectrum representation above 20 MeV   2931 1451   55
in order to reduce the length of the file. No essential data for  2931 1451   56
applications is lost with this representation.                    2931 1451   57
  The evaluation above 20 MeV utilizes MF=6, MT=5 to represent    2931 1451   58
all reaction data.  Production cross sections and emission        2931 1451   59
spectra are given for neutrons, protons, deuterons, tritons,      2931 1451   60
alpha particles, gamma rays, and all residual nuclides produced   2931 1451   61
(A>5) in the reaction chains. To summarize, the ENDF sections     2931 1451   62
with non-zero data above En = 20 MeV are:                         2931 1451   63
                                                                  2931 1451   64
  MF=3 MT=  1  Total Cross Section                                2931 1451   65
       MT=  2  Elastic Scattering Cross Section                   2931 1451   66
       MT=  3  Nonelastic Cross Section                           2931 1451   67
       MT=  5  Sum of Binary (n,n') and (n,x) Reactions           2931 1451   68
                                                                  2931 1451   69
  MF=4 MT=  2  Elastic Angular Distributions                      2931 1451   70
                                                                  2931 1451   71
  MF=6 MT=  5  Production Cross Sections and Energy-Angle         2931 1451   72
               Distributions for Emission Neutrons, Protons,      2931 1451   73
               Deuterons, Tritons, and Alphas; and Angle-         2931 1451   74
               Integrated Spectra for Gamma Rays and Residual     2931 1451   75
                                                                  2931 1451   76
               Nuclei That Are Stable Against Particle Emission   2931 1451   77
                                                                  2931 1451   78
  The evaluation is based on nuclear model calculations that      2931 1451   79
have been benchmarked to experimental data, especially for n +    2931 1451   80
Cu65 and p + Cu65 reactions (Ch98). We use the GNASH code system  2931 1451   81
(Yo92), which utilizes Hauser-Feshbach statistical, preequilib-   2931 1451   82
rium and direct-reaction theories. Spherical optical model        2931 1451   83
calculations are used to obtain particle transmission             2931 1451   84
coefficients for the Hauser-Feshbach calculations, as well as     2931 1451   85
for the elastic neutron angular distributions.                    2931 1451   86
  Cross sections and spectra for producing individual residual    2931 1451   87
nuclei are included for reactions. The energy-angle-correlations  2931 1451   88
for all outgoing particles are based on Kalbach systematics       2931 1451   89
(Ka88).                                                           2931 1451   90
  A model was developed to calculate the energy distributions of  2931 1451   91
all recoil nuclei in the GNASH calculations (Ch96a). The recoil   2931 1451   92
energy distributions are represented in the laboratory system in  2931 1451   93
MT=5, MF=6, and are given as isotropic in the lab system. All     2931 1451   94
other data in MT=5,MF=6 are given in the center-of-mass system.   2931 1451   95
This method of representation utilizes the LCT=3 option approved  2931 1451   96
at the November, 1996, CSEWG meeting.                             2931 1451   97
  Preequilibrium corrections were performed in the course of the  2931 1451   98
GNASH calculations using the exciton model of Kalbach (Ka77,      2931 1451   99
Ka85), validated by comparison with calculations using Feshbach,  2931 1451  100
Kerman, Koonin (FKK) theory [Ch93].  Discrete level data from     2931 1451  101
nuclear data sheets were matched to continuum level densities     2931 1451  102
using the formulation of Ignatyuk et al. (Ig75) and pairing and   2931 1451  103
shell parameters from the Cook (Co67) analysis. Neutron and       2931 1451  104
charged- particle transmission coefficients were obtained from    2931 1451  105
the optical potentials, as discussed below.  Gamma-ray            2931 1451  106
transmission coefficients were calculated using the Kopecky-Uhl   2931 1451  107
model (Ko90).                                                     2931 1451  108
                                                                  2931 1451  109
SPECIFIC INFORMATION CONCERNING THE 65Cu EVALUATION               2931 1451  110
                                                                  2931 1451  111
This evaluation is documented in some detail in Ref. (Ko98b).     2931 1451  112
                                                                  2931 1451  113
The neutron total cross section above 20 MeV was obtained by      2931 1451  114
evaluating experimental data, with a particular emphasis on the   2931 1451  115
Finlay (Fi93) elemental data. This resulted in an evaluated       2931 1451  116
elemental Cu total cross section; to obtain an isotopic 65Cu total2931 1451  117
cross section, it was assumed that 63Cu and 65Cu have total cross 2931 1451  118
sections in an A**2/3 ratio to one another. The total neutron     2931 1451  119
nonelastic cross section was obtained directly from an optical    2931 1451  120
model calculation (see below), after verifying that it was in good2931 1451  121
agreement with the experimental data (Ko98b).                     2931 1451  122
                                                                  2931 1451  123
To obtain the neutron optical potential we used total cross       2931 1451  124
section data from 1.2 to 4.5 MeV (Gu86) and from 5.3 to 600 MeV   2931 1451  125
(Fi93), and elastic scattering angular distribution data from 1.6 2931 1451  126
to 96 MeV (Br50, Sa60, Ki74, El82, Gu86). The optical potential   2931 1451  127
parameters were obtained using a combination of a grid search code2931 1451  128
and the interactive optical model viewer ECISVIEW [Ko97], both    2931 1451  129
built around the coupled channels code ECIS96 [Ra94]. The energy  2931 1451  130
dependence of the optical model parameters is as described in     2931 1451  131
[Ko98]. This optical potential was used for the calculation, with 2931 1451  132
ECIS96, of neutron transmission coefficients and DWBA cross       2931 1451  133
sections for the entire energy region above 20 MeV.               2931 1451  134
                                                                  2931 1451  135
Due to the lack of proton elastic scattering data in numerical    2931 1451  136
form, we used a combination of global optical models for the      2931 1451  137
proton channel. The Becchetti-Greenlees potential [Be69]was       2931 1451  138
adopted below 47 MeV, and the non-relativistic version of the     2931 1451  139
Madland potential [Ma88] above 47 MeV. At this particular energy  2931 1451  140
point the two potentials join smoothly.                           2931 1451  141
                                                                  2931 1451  142
For deuterons, the Lohr-Haeberli global potential [Lo74] was used;2931 1451  143
for alpha particles the Moyen potential (MacFadden-Satchler       2931 1451  144
[Ma66]) was used; and for tritons the Becchetti-Greenlees         2931 1451  145
potential [Be71] was used. The He-3 channel was ignored, due to   2931 1451  146
its small importance.                                             2931 1451  147
                                                                  2931 1451  148
Following Delaroche et al. [De82], we adopted the weak-coupling   2931 1451  149
model for direct collective inelastic scattering for Cu-65, using 2931 1451  150
Ni-64 as a basis. For the calculation of the cross sections,      2931 1451  151
ECIS96 was used in DWBA mode. We used the following direct        2931 1451  152
transitions for Cu-65  (ground state 3/2- ) :                     2931 1451  153
                                                                  2931 1451  154
Jpi Ex(MeV) Deformation length (Delta) or parameter (Beta)        2931 1451  155
 0.5- 0.771  Beta(2)=0.0566                                       2931 1451  156
 2.5- 1.116  Beta(2)=0.0980                                       2931 1451  157
 3.5- 1.481  Beta(2)=0.1132                                       2931 1451  158
 1.5- 1.743  Beta(2)=0.0800                                       2931 1451  159
 1.5- 3.185  Delta(3)=0.3167                                      2931 1451  160
 2.5- 3.435  Delta(3)=0.3879                                      2931 1451  161
 3.5- 3.685  Delta(3)=0.4479                                      2931 1451  162
 4.5- 3.935  Delta(3)=0.5008                                      2931 1451  163
                                                                  2931 1451  164
Only one measurement exists for neutron-induced emission spectra  2931 1451  165
above 20 MeV for 65Cu: the 25.7 MeV (n,xn) data by Marcinkowski et2931 1451  166
al (Ma83). Without adjusting any of the level density or pre-     2931 1451  167
equilibrium parameters the GNASH calculation was in good agreement2931 1451  168
with these data (Ko98b). Hence we adopted these parameters for the2931 1451  169
whole energy region.                                              2931 1451  170
                                                                  2931 1451  171
****************************************************************  2931 1451  172
                                                                  2931 1451  173
REFERENCES                                                        2931 1451  174
                                                                  2931 1451  175
[Ab93]  W. Abfalterer, R.W. Finlay, S.M. Grimes, and V. Mishra,   2931 1451  176
   Phys.Rev. C47, 1033 (1993)                                     2931 1451  177
[Al83]  R. Alarcon and J. Rapaport, Nucl.Phys. A458, 502 (1986)   2931 1451  178
[Ar80]  E.D. Arthur and P.G. Young, 'Evaluation of Neutron Cross  2931 1451  179
   Sections to 40 MeV for 54,56Fe," Proc. Sym. on Neutron Cross   2931 1451  180
   Sections from 10 to 50 MeV, 12-14 May 1980, Brookhaven National2931 1451  181
   Laboratory [Eds. M. R. Bhat and S. Pearlstein, BNL-NCS- 51245, 2931 1451  182
   1980] p. 731.                                                  2931 1451  183
[Be69]  F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182,   2931 1451  184
   1190 (1969)                                                    2931 1451  185
[Be71]  F.D. Becchetti, Jr., and G.W. Greenlees in "Polarization  2931 1451  186
   Phenomena in Nuclear Reactions," (Ed: H.H. Barschall and W.    2931 1451  187
   Haeberli, The University of Wisconsin Press, 1971) p.682.      2931 1451  188
[Be92]  O. Bersillon, "SCAT2 - A Spherical Optical Model Code,"   2931 1451  189
   in Proc. ICTP Workshop on Computation and Analysis of Nuclear  2931 1451  190
   data Relevant to Nuclear Energy and Safety, February-March,    2931 1451  191
   1999 Trieste, Italy, to be published in World Scientific Press,2931 1451  192
   and Progress Report of the Nuclear Physics Division, Bruyeres- 2931 1451  193
   le-Chatel 1977, CEA-N-2037 (1978) p.111                        2931 1451  194
[Br50]  S. Bratenahl, S. Fernbach, R.H. Hildebrand et al.,        2931 1451  195
   Phys.Rev. 77, 597 (1950)                                       2931 1451  196
[Ch93]  M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2931 1451  197
[Ch96]  M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J.      2931 1451  198
   Koning, "High-Energy Nuclear Data Libraries for Accelerator-   2931 1451  199
   Driven Technologies:  Calculational Method for Heavy Recoils," 2931 1451  200
   Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation    2931 1451  201
   Technology and Applications, Kalmar, Sweden, 3-7 June 1996     2931 1451  202
[Ch98]  M.B. Chadwick and P.G. Young, "GNASH Calculations of      2931 1451  203
   n,p + Cu isotopes and Benchmarking of Results" in APT PROGRESS 2931 1451  204
   REPORT: 1 February - 1 March 1998, internal Los Alamos National2931 1451  205
   Laboratory memo, 6 Mar.1998 from R.E. MacFarlane to L. Waters. 2931 1451  206
[Ch99]  M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2931 1451  207
   National Laboratory report, LA-UR-99-1222 (1999)               2931 1451  208
[Co67]  J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J.    2931 1451  209
   Phys. 20, 477 (1967)                                           2931 1451  210
[De82]  J.P. Delaroche, S.M. El-Kadi, P.P. Guss, C.E. Floyd and   2931 1451  211
   R.L. Walter, Nucl. Phys. A390, 541 (1982).                     2931 1451  212
[El82]  S.M. El-Kadi, C.E. Nelson, F.O. Purser et al., Nucl.Phys. 2931 1451  213
   A390, 509 (1982)                                               2931 1451  214
[Fi93]  R. W. Finlay, W. P. Abfalterer, G. Fink et al., Phys. Rev 2931 1451  215
   C 47, 237 (1993)                                               2931 1451  216
[Fr01]  S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos      2931 1451  217
   National Laboratory Report, LA-13812 (2001).                   2931 1451  218
[Gu86]  P. Guenther, D.L. Smith, A.B. Smith, J.F. Whalen, Nucl.   2931 1451  219
   Phys. A448, 280 (1986)                                         2931 1451  220
[Ig75]  A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J.    2931 1451  221
   Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485     2931 1451  222
   (1975)                                                         2931 1451  223
[Ka77]  C. Kalbach, Z.Phys.A  283, 401 (1977)                     2931 1451  224
[Ka85]  C. Kalbach, Los Alamos National Laboratory report         2931 1451  225
   LA-10248-MS (1985)                                             2931 1451  226
[Ka88]  C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also          2931 1451  227
   C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981)           2931 1451  228
[Ki74]  W.E. Kinney, F.G. Perey, report ORNL-4908 (1974)          2931 1451  229
[Ko90]  J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990)         2931 1451  230
[Ko97]  A.J. Koning, J.J. van Wijk and J.-P. Delaroche, "ECISVIEW:2931 1451  231
   A Graphical Interface for ECIS95", Proceedings of the NEA      2931 1451  232
   Specialists' Meeting on the Nucleon Nucleus Optical Model up to2931 1451  233
   200 MeV, Bruyeres-le-Chatel, November 13-15 1996. Available at 2931 1451  234
   http://db.nea.fr/html/science/om200/.                          2931 1451  235
[Ko98]  A.J. Koning, J.-P. Delaroche and O. Bersillon, "Nuclear   2931 1451  236
  Data for Accelerator-Driven Systems: Nuclear models, Experiments2931 1451  237
   and Data Libraries", to appear in Mucl. Instr. Meth. A (1998). 2931 1451  238
[Ko98b] A.J. Koning, M.B. Chadwick, and P.G. Young, "ENDF/B-VI    2931 1451  239
   neutron and proton datafiles up to 150 MeV for 63Cu and 65Cu", 2931 1451  240
   Los Alamos National Laboratory report LAUR- (1998); ECN lab and2931 1451  241
   JEFF report (1998).                                            2931 1451  242
[Lo74]  J.M. Lohr and W. Haeberli, Nucl.Phys. A232, 381 (1974)    2931 1451  243
[Ma66]  Macfadden and Satchler, Nuc.Phys. 84, 177 (1966)          2931 1451  244
[Ma83]  A. Marcinkowski, R.W. Finlay, G. Randers-Pehrson et al.,  2931 1451  245
   Nucl.Phys. A402, 220 (1983)                                    2931 1451  246
[Ma88]   D.G. Madland, "Recent Results in the Development of a    2931 1451  247
   Global Medium-Energy Nucleon-Nucleus Optical-Model Potential,  2931 1451  248
   "Proc. OECD/NEANDC Specialist's Mtg. on Preequilibrium Nuclear 2931 1451  249
   Reactions, Semmering, Austria, 10-12 Feb. 1988, NEANDC-245 'U' 2931 1451  250
   (1988).                                                        2931 1451  251
[Pe63]  C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963)      2931 1451  252
[Ra94]  J. Raynal, Notes on ECIS94, CEA Saclay Report CEA-N-2772  2931 1451  253
   (1994)                                                         2931 1451  254
[Sa60]  G.L. Salmon, Nucl.Phys. 21, 15 (1960)                     2931 1451  255
[Yo92]  P.G. Young, E.D. Arthur, and M.B. Chadwick, report        2931 1451  256
   LA-12343-MS (1992)                                             2931 1451  257
                                                                  2931 1451  258
 **************************************************************** 2931 1451  259
                                                                  2931 1451  260
 ENDF/B-VI MOD 3 Revision, March 1991, ORNL                       2931 1451  261
                                                                  2931 1451  262
 MOD 3 changes                                                    2931 1451  263
   1) Corrections to MF=6, MT=63 at 17.5 MeV to prevent negative  2931 1451  264
      values in the angular distribution.                         2931 1451  265
                                                                  2931 1451  266
 **************************************************************** 2931 1451  267
                                                                  2931 1451  268
 * Note there was no MOD 2 released.                              2931 1451  269
                                                                  2931 1451  270
 **************************************************************** 2931 1451  271
                                                                  2931 1451  272
 ENDF/B-VI MOD 1 Evaluation, November 1989, D. Hetrick, F.Y. Fu,  2931 1451  273
           D. Larson (ORNL)                                       2931 1451  274
                                                                  2931 1451  275
    This work employed several nuclear model codes including the  2931 1451  276
 optical-model code GENOA [1], the Distorted Wave Born            2931 1451  277
 Approximation (DWBA) program DWUCK [2], and the Hauser-Feshbach  2931 1451  278
 code TNG [3,4]. The TNG code provides energy and angular         2931 1451  279
 distributions of particles emitted in the compound and pre-      2931 1451  280
 compound reactions, ensures consistency among all reactions, and 2931 1451  281
 maintains energy balance. Details pertinent to the contents of   2931 1451  282
 this evaluation and extensive comparisons of calculations with   2931 1451  283
 experimental data can be found in reference [5].                 2931 1451  284
                                                                  2931 1451  285
----- DESCRIPTION OF FILES                                        2931 1451  286
(MF-MT)                                                           2931 1451  287
  1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS.         2931 1451  288
  2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB [6]. POINT2931 1451  289
        WISE RECONSTRUCTION COMPARED WITH DATA [7] SHOWED POORER  2931 1451  290
        FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT 2931 1451  291
        99.5 KEV.  REICH-MOORE PARAMETERS ARE GIVEN.  AGREEMENT   2931 1451  292
        WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND 2931 1451  293
        FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN       2931 1451  294
        AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND     2931 1451  295
        COMPARED WITH THE BINNED DATA.  THIS IS PROBABLY DUE TO   2931 1451  296
        TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES    2931 1451  297
        SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION.             2931 1451  298
        NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2931 1451  299
        OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE       2931 1451  300
        PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON    2931 1451  301
        A FINER ENERGY GRID THAN GIVEN IN 4/2.                    2931 1451  302
  3-16  (N,2N) CROSS SECTIONS WERE TAKEN FROM THE GLUCS [12]      2931 1451  303
        CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL-     2931 1451  304
        TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS          2931 1451  305
        SECTIONS [13].                                            2931 1451  306
 33-16  (N,2N) COVARIANCES WERE TAKEN FROM THE GLUCS [12]         2931 1451  307
        CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL-     2931 1451  308
        TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS          2931 1451  309
        SECTIONS [13].                                            2931 1451  310
 **************************************************************** 2931 1451  311
                                                                  2931 1451  312
 REFERENCES:                                                      2931 1451  313
                                                                  2931 1451  314
 [1] F.G. Perey, computer code GENOA, ORNL, unpublished (1967)    2931 1451  315
 [2] P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of           2931 1451  316
     Colorado, unpublished (1972)                                 2931 1451  317
 [3] C.Y. Fu, report ORNL/TM-7042 (1980); also, C.Y Fu,           2931 1451  318
     Symp. on Neutron Cross Sections from 10 to 50 MeV, Upton, NY,2931 1451  319
     May 1980, Brookhaven National Lab. report BNL-NCS-51245      2931 1451  320
     (1980) p.675                                                 2931 1451  321
 [4] K. Shibata and C.Y. Fu, report ORNL/TM-10093 (1986)          2931 1451  322
 [5] D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge report     2931 1451  323
     ORNL/TM-9083 [ENDF-337] (1984)                               2931 1451  324
 [6] S.F. Mughabghab, M. Divadeenam, and N.E. Holden, "Neutron    2931 1451  325
     Cross Sections, Vol. 1, Neutron Resonance Parameters and     2931 1451  326
     Thermal Cross Sections, Part A, Z=1-60," (Academic Press,    2931 1451  327
     1981)                                                        2931 1451  328
 [7] M.S. Pandey, J.B. Garg and J.A. Harvey, Phys.Rev. C 15, 600  2931 1451  329
     (1977), and private communication.                           2931 1451  330
 [8] F.G. Perey, private communication (1977)                     2931 1451  331
 [9] D.C. Larson, Symp. on Neutron Cross Sections from 10 to 50   2931 1451  332
     MeV, Upton, NY, May 1980, Brookhaven National Lab. report    2931 1451  333
     BNL-NCS-51245 (1980) p.277                                   2931 1451  334
[10] P. Guenther, D.L. Smith, A.B. Smith and J.F. Whalen, Nucl.   2931 1451  335
     Phys. A, 448, 280 (1986) [CSISRS data set 12869/002], and    2931 1451  336
     W.P. Poenitz and J.F. Whalen, Argonne report ANL/NDM-80      2931 1451  337
     (1983) [CSISRS data set 12853]                               2931 1451  338
[11] A.I. Dyumin, D.M. Kaminker, G.N. Popova, and V.A. Smolin,    2931 1451  339
     Izv.Akad.Nauk SSSR, Ser.Fiz. 36, 852 (1972)                  2931 1451  340
[12] D.M. Hetrick and C.Y. Fu, Oak Ridge report ORNL/TM-7341      2931 1451  341
     [ENDF-303] (1980)                                            2931 1451  342
[13] C.Y. Fu and D.M. Hetrick, Proc. Fourth ASTM-Euratom Symp.    2931 1451  343
     on Reactor Dosimetry, Gaithersburg, Maryland, March 22-26,   2931 1451  344
     1982 (U.S. National Bureau of Standards) p.877               2931 1451  345
[14] CSISRS Library, National Nuclear Data Center, Brookhaven     2931 1451  346
     National Laboratory, Upton, N.Y. 11973.                      2931 1451  347
[15] V. McLane, C.L. Dunford and P.F. Rose, "Neutron Cross        2931 1451  348
     Sections, Vol. 2, Neutron Cross Section Curves" (Academic    2931 1451  349
     Press, 1988)                                                 2931 1451  350
[16] S.M. Qaim and G. Stoecklin, Nucl.Phys. A257, 233 (1976)      2931 1451  351
[17] S.M. Qaim, Radiochimica Acta, 25, 13 (1978)                  2931 1451  352
[18] M.G. Delfini, J. Kopecky, R.E. Chrien et al., Nucl.Phys.     2931 1451  353
     A404, 250 (1983)                                             2931 1451  354
 **************************************************************** 2931 1451  355
  The Q values and threshold energies were updated prior to pro-  2931 1451  356
  cessing through the codes to comply with the values obtained    2931 1451  357
  using the NNDC calculation program which is based on the 1995   2931 1451  358
  Update to the Atomic mass Evaluation.                           2931 1451  359
 ************************ C O N T E N T S *********************** 2931 1451  360
 ***************** Program LINEAR (VERSION 2002-1) ***************2931 1451  361
 For All Data Greater than 1.0000E-10 barns in Absolute Value     2931 1451  362
 Data Linearized to Within an Accuracy of .100000000 per-cent     2931 1451  363
 ***************** Program RECENT (VERSION 2002-1) ***************2931 1451  364
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2931 1451  365
 Data Linearized to within an Accuracy of .100000000 per-cent     2931 1451  366
 ***************** Program SIGMA1 (VERSION 2002-1) ***************2931 1451  367
 Data Doppler Broadened to 300.000000 Kelvin                      2931 1451  368
 for All Data Greater than 1.0000E-10 barns in Absolute Value     2931 1451  369
 Data Linearized to Within an Accuracy pf .100000000 per-cent     2931 1451  370
 ***************** Program FIXUP (Version 2002-1) ****************2931 1451  371
 Corrected ZA/AWR in All Sections-----------------------------Yes 2931 1451  372
 Corrected Thresholds-----------------------------------------Yes 2931 1451  373
 Extended Cross Sections to 20 MeV----------------------------No  2931 1451  374
 Allow Cross Section Deletion---------------------------------No  2931 1451  375
 Allow Cross Section Reconstruction---------------------------No  2931 1451  376
 Make All Cross Sections Non-Negative-------------------------Yes 2931 1451  377
 Delete Energies Not in Ascending Order-----------------------Yes 2931 1451  378
 Deleted Duplicate Points-------------------------------------Yes 2931 1451  379
 Check for Ascending MAT/MF/MT Order--------------------------Yes 2931 1451  380
 Check for Legal MF/MT Numbers--------------------------------Yes 2931 1451  381
 Allow Creation of Missing Sections---------------------------No  2931 1451  382
 Allow Insertion of Energy Points-----------------------------No  2931 1451  383
 Create Uniform Energy Grid-----------------------------------No  2931 1451  384
 Delete Section if Cross Section =0 at All Energies-----------Yes 2931 1451  385
 ***************** Program GROUPIE (VERSION 2002-1) **************2931 1451  386
 Unshielded Group Averages Using  640 Groups                      2931 1451  387
 Weighting Spectrum: Flat (Constant) Spectrum                     2931 1451  388
                                1        451        392          52931 1451  389
                                2        151          4          52931 1451  390
                                3         16         37          12931 1451  391
                               33         16         62          12931 1451  392
                                                                  2931 1  099999
                                                                  2931 0  0    0
 2.90650E+4 6.43700E+1          0          0          1          02931 2151    1
 2.906500+4 1.000000+0          0          0          1          02931 2151    2
 1.000000-5 9.950000+4          0          0          0          02931 2151    3
 1.500000+0 6.700000-1          0          0          0          02931 2151    4
                                                                  2931 2  099999
                                                                  2931 0  0    0
 2.90650E+4 6.43700E+1          0          0          0          02931 3 16    1
-9.91020E+6-9.91020E+6          0          0          1        1012931 3 16    2
        101          1                                            2931 3 16    3
 10000000.0 .000366266 10100000.0 .004894626 10200000.0 .0105964472931 3 16    4
 10300000.0 .016298268 10400000.0 .022000089 10500000.0 .0367329002931 3 16    5
 10600000.0 .060496700 10700000.0 .084260500 10800000.0 .1080243002931 3 16    6
 10900000.0 .131788100 11000000.0 .159085000 11100000.0 .1899150002931 3 16    7
 11200000.0 .220745000 11300000.0 .251575000 11400000.0 .2824050002931 3 16    8
 11500000.0 .314504000 11600000.0 .347872000 11700000.0 .3812400002931 3 16    9
 11800000.0 .414608000 11900000.0 .447976000 12000000.0 .4801010002931 3 16   10
 12100000.0 .510983000 12200000.0 .541865000 12300000.0 .5727470002931 3 16   11
 12400000.0 .603629000 12500000.0 .630458000 12600000.0 .6532340002931 3 16   12
 12700000.0 .676010000 12800000.0 .698786000 12900000.0 .7215620002931 3 16   13
 13000000.0 .741987000 13100000.0 .760061000 13200000.0 .7781350002931 3 16   14
 13300000.0 .796209000 13400000.0 .814283000 13500000.0 .8305190002931 3 16   15
 13600000.0 .844917000 13700000.0 .859315000 13800000.0 .8737130002931 3 16   16
 13900000.0 .888111000 14000000.0 .900663000 14100000.0 .9113690002931 3 16   17
 14200000.0 .922075000 14300000.0 .932781000 14400000.0 .9434870002931 3 16   18
 14500000.0 .952211000 14600000.0 .958953000 14700000.0 .9656950002931 3 16   19
 14800000.0 .972437000 14900000.0 .979179000 15000000.0 .9856050002931 3 16   20
 15100000.0 .991715000 15200000.0 .997825000 15300000.0 1.003935002931 3 16   21
 15400000.0 1.01004500 15500000.0 1.01484000 15600000.0 1.018320002931 3 16   22
 15700000.0 1.02180000 15800000.0 1.02528000 15900000.0 1.028760002931 3 16   23
 16000000.0 1.03373000 16100000.0 1.04019000 16200000.0 1.046650002931 3 16   24
 16300000.0 1.05311000 16400000.0 1.05957000 16500000.0 1.063630002931 3 16   25
 16600000.0 1.06529000 16700000.0 1.06695000 16800000.0 1.068610002931 3 16   26
 16900000.0 1.07027000 17000000.0 1.07157000 17100000.0 1.072510002931 3 16   27
 17200000.0 1.07345000 17300000.0 1.07439000 17400000.0 1.075330002931 3 16   28
 17500000.0 1.07734000 17600000.0 1.08042000 17700000.0 1.083500002931 3 16   29
 17800000.0 1.08658000 17900000.0 1.08966000 18000000.0 1.089750002931 3 16   30
 18100000.0 1.08685000 18200000.0 1.08395000 18300000.0 1.081050002931 3 16   31
 18400000.0 1.07815000 18500000.0 1.07277167 18600000.0 1.064915002931 3 16   32
 18700000.0 1.05705833 18800000.0 1.04920167 18900000.0 1.041345002931 3 16   33
 19000000.0 1.03348833 19100000.0 1.02563167 19200000.0 1.017775002931 3 16   34
 19300000.0 1.00991833 19400000.0 1.00206167 19500000.0 .9942050002931 3 16   35
 19600000.0 .986348333 19700000.0 .978491667 19800000.0 .9706350002931 3 16   36
 19900000.0 .962778333 20000000.0 0.0                             2931 3 16   37
                                                                  2931 3  099999
                                                                  2931 0  0    0
 2.90650E+4 6.43700E+1          0          0          0          1293133 16    1
 0.0000E+00 0.0000E+00          0         16          0          2293133 16    2
 0.0000E+00 0.0000E+00          1          5        300         24293133 16    3
 1.0000E-05 1.0000E+07 1.0500E+07 1.1000E+07 1.1500E+07 1.2000E+07293133 16    4
 1.2500E+07 1.3000E+07 1.3500E+07 1.4000E+07 1.4500E+07 1.5000E+07293133 16    5
 1.5500E+07 1.6000E+07 1.6500E+07 1.7000E+07 1.7500E+07 1.8000E+07293133 16    6
 1.8500E+07 1.9000E+07 1.9200E+07 1.9400E+07 1.9600E+07 2.0000E+07293133 16    7
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00293133 16    8
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00293133 16    9
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00293133 16   10
 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.2849E-02293133 16   11
-3.9100E-03 9.8124E-04 3.2315E-04 2.5973E-04 1.6943E-04 1.0837E-04293133 16   12
 5.2219E-05 4.5076E-05 3.6396E-05 1.4418E-05 2.1146E-05 2.1805E-05293133 16   13
 2.1931E-05 2.1318E-05 2.1522E-05 2.2348E-05 2.9580E-05 2.2389E-05293133 16   14
 2.5489E-05 2.5389E-05 2.8747E-05 1.1582E-03 9.4407E-05 2.2976E-04293133 16   15
 1.6573E-04 1.1914E-04 8.3873E-05 4.3373E-05 3.6631E-05 3.1684E-05293133 16   16
 1.1438E-05 1.8007E-05 1.8412E-05 1.8521E-05 1.7912E-05 1.8306E-05293133 16   17
 1.8801E-05 2.5446E-05 1.8989E-05 2.1853E-05 2.1701E-05 2.4893E-05293133 16   18
 1.0426E-03 4.1291E-04 3.5993E-04 2.4206E-04 1.6476E-04 8.2857E-05293133 16   19
 7.0722E-05 6.0039E-05 2.2260E-05 3.4439E-05 3.5246E-05 3.5284E-05293133 16   20
 3.4112E-05 3.4653E-05 3.5725E-05 4.7927E-05 3.4885E-05 4.0981E-05293133 16   21
 4.0699E-05 4.6995E-05 1.6804E-03 5.1367E-04 3.7077E-04 2.3022E-04293133 16   22
 1.0876E-04 9.5181E-05 7.5902E-05 3.0612E-05 4.4708E-05 4.6020E-05293133 16   23
 4.5981E-05 4.4753E-05 4.5221E-05 4.6593E-05 6.1095E-05 4.5008E-05293133 16   24
 5.2412E-05 5.2045E-05 5.9698E-05 1.5662E-03 4.6015E-04 3.0034E-04293133 16   25
 1.3181E-04 1.1846E-04 8.7882E-05 3.8955E-05 5.3423E-05 5.5298E-05293133 16   26
 5.5174E-05 5.4093E-05 5.4391E-05 5.6078E-05 7.1784E-05 5.4017E-05293133 16   27
 6.1977E-05 6.1527E-05 6.9508E-05 1.6388E-03 3.8739E-04 1.8183E-04293133 16   28
 1.6833E-04 1.0963E-04 5.4807E-05 6.8444E-05 7.1184E-05 7.0989E-05293133 16   29
 6.9696E-05 7.0329E-05 7.2399E-05 9.1321E-05 7.1362E-05 7.9338E-05293133 16   30
 7.8939E-05 8.7688E-05 1.6381E-03 2.7820E-04 2.9569E-04 1.5183E-04293133 16   31
 8.4051E-05 9.2687E-05 9.9014E-05 9.7400E-05 9.5524E-05 9.6112E-05293133 16   32
 9.8898E-05 1.2500E-04 9.5565E-05 1.0835E-04 1.0739E-04 1.2076E-04293133 16   33
 7.2642E-04 1.3861E-04 2.1090E-04 1.3154E-04 1.2590E-04 1.3899E-04293133 16   34
 1.3473E-04 1.3248E-04 1.3243E-04 1.3654E-04 1.7246E-04 1.2855E-04293133 16   35
 1.4860E-04 1.4753E-04 1.6696E-04 7.4020E-04 2.2844E-04 1.3272E-04293133 16   36
 1.3480E-04 1.4740E-04 1.4311E-04 1.4019E-04 1.4023E-04 1.4475E-04293133 16   37
 1.8498E-04 1.3536E-04 1.5870E-04 1.5766E-04 1.7994E-04 2.5205E-04293133 16   38
 6.7831E-05 1.5774E-04 1.5403E-04 1.5480E-04 1.4692E-04 1.4845E-04293133 16   39
 1.5385E-04 2.1458E-04 1.4114E-04 1.7986E-04 1.7866E-04 2.1467E-04293133 16   40
 4.9848E-04 7.7213E-05 1.8584E-04 1.5113E-04 1.7339E-04 1.6481E-04293133 16   41
 1.6703E-04 1.1799E-04 1.6769E-04 1.2330E-04 1.2252E-04 8.4028E-05293133 16   42
 3.4942E-04 1.7432E-04 1.9975E-04 2.0482E-04 1.8271E-04 1.7572E-04293133 16   43
 1.6743E-04 1.7022E-04 1.5696E-04 1.5582E-04 1.4329E-04 5.2876E-04293133 16   44
 1.9487E-04 2.1525E-04 1.9401E-04 1.9702E-04 1.6642E-04 1.6184E-04293133 16   45
 1.5555E-04 1.5458E-04 1.4089E-04 2.9887E-04 1.8750E-04 2.0981E-04293133 16   46
 1.8656E-04 1.7332E-04 1.7942E-04 1.6365E-04 1.6255E-04 1.4448E-04293133 16   47
 3.3467E-04 2.2613E-04 2.0243E-04 1.7545E-04 1.8875E-04 1.6806E-04293133 16   48
 1.6691E-04 1.4225E-04 1.1229E-03-7.4862E-05 3.1309E-04 2.2013E-04293133 16   49
 2.7176E-04 2.6985E-04 1.8472E-04 4.9986E-04 1.6697E-04 2.0915E-04293133 16   50
 1.7615E-04 1.7495E-04 1.4909E-04 1.3873E-03 1.1714E-04 5.8852E-04293133 16   51
 5.8437E-04 3.4575E-04 4.7121E-04 2.5339E-04 2.5176E-04 1.7365E-04293133 16   52
 3.0426E-03 1.1867E-03 9.8857E-04 3.0015E-03 9.8197E-04 2.7731E-03293133 16   53
 0.0000E+00 0.0000E+00          0          8         48         24293133 16   54
 1.0000E-05 0.0000E+00 1.0000E+07 1.8167E-06 1.0500E+07 9.2309E-07293133 16   55
 1.1000E+07 5.7456E-06 1.1500E+07 2.8213E-05 1.2000E+07 5.2413E-05293133 16   56
 1.2500E+07 8.4423E-05 1.3000E+07 1.1260E-04 1.3500E+07 6.0382E-05293133 16   57
 1.4000E+07 7.0182E-05 1.4500E+07 2.6190E-05 1.5000E+07 5.5253E-05293133 16   58
 1.5500E+07 4.0563E-05 1.6000E+07 6.4379E-05 1.6500E+07 3.7846E-05293133 16   59
 1.7000E+07 4.2917E-05 1.7500E+07 1.4672E-04 1.8000E+07 6.5269E-05293133 16   60
 1.8500E+07 1.7207E-04 1.9000E+07 5.8043E-05 1.9200E+07 3.7985E-04293133 16   61
 1.9400E+07 3.6370E-04 1.9600E+07 3.0778E-04 2.0000E+07 2.6557E-04293133 16   62
                                                                  293133  099999
                                                                  2931 0  0    0
                                                                     0 0  0    0
 3.00640E+4 6.33800E+1          0          0         34         103025 1451    1
 0.0        0.0                 0          0          0          63025 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20023025 1451    3
 3.00000E+2 0.0                 1          0         42          43025 1451    4
 30-Zn- 64 IRK-VIENNA EVAL-APR90                                  3025 1451    5
                      DIST-Feb2004                                3025 1451    6
----IRDF-2002         MATERIAL 3025                               3025 1451    7
-----INCIDENT NEUTRON DATA                                        3025 1451    8
------ENDF-6 FORMAT                                               3025 1451    9
 *****************************************************************3025 1451   10
 30-ZN- 64 IRK-VIENNA EVAL-APR90                                  3025 1451   11
                      DIST-JUN90                                  3025 1451   12
    IRK-EVAL.NLIB 25  3025                                        3025 1451   13
 *****************************************************************3025 1451   14
  The Q value was updated prior to processing through the pre-    3025 1451   15
  processing codes to comply with the values obtained using the   3025 1451   16
  NNDC calculation program which is based on the 1995 Update to   3025 1451   17
  the Atomic mass Evaluation.                                     3025 1451   18
  Threshold value of 0.0 inserted at 1.0e-5 ev for MF/MT=3/103    3025 1451   19
  after processing using the pre-processing codes.                3025 1451   20
 *****************************************************************3025 1451   21
 ***************** Program LINEAR (VERSION 2002-1) ***************3025 1451   22
 For All Data Greater than 1.0000E-10 barns in Absolute Value     3025 1451   23
 Data Linearized to Within an Accuracy of .100000000 per-cent     3025 1451   24
 ***************** Program SIGMA1 (VERSION 2002-1) ***************3025 1451   25
 Data Doppler Broadened to 300.000000 Kelvin                      3025 1451   26
 for All Data Greater than 1.0000E-10 barns in Absolute Value     3025 1451   27
 Data Linearized to Within an Accuracy pf .100000000 per-cent     3025 1451   28
 ***************** Program FIXUP (Version 2002-1) ****************3025 1451   29
 Corrected ZA/AWR in All Sections-----------------------------Yes 3025 1451   30
 Corrected Thresholds-----------------------------------------Yes 3025 1451   31
 Extended Cross Sections to 20 MeV----------------------------No  3025 1451   32
 Allow Cross Section Deletion---------------------------------No  3025 1451   33
 Allow Cross Section Reconstruction---------------------------No  3025 1451   34
 Make All Cross Sections Non-Negative-------------------------Yes 3025 1451   35
 Delete Energies Not in Ascending Order-----------------------Yes 3025 1451   36
 Deleted Duplicate Points-------------------------------------Yes 3025 1451   37
 Check for Ascending MAT/MF/MT Order--------------------------Yes 3025 1451   38
 Check for Legal MF/MT Numbers--------------------------------Yes 3025 1451   39
 Allow Creation of Missing Sections---------------------------No  3025 1451   40
 Allow Insertion of Energy Points-----------------------------No  3025 1451   41
 Create Uniform Energy Grid-----------------------------------No  3025 1451   42
 Delete Section if Cross Section =0 at All Energies-----------Yes 3025 1451   43
 ***************** Program GROUPIE (VERSION 2002-1) **************3025 1451   44
 Unshielded Group Averages Using  640 Groups                      3025 1451   45
 Weighting Spectrum: Flat (Constant) Spectrum                     3025 1451   46
                                1        451         50          13025 1451   47
                                2        151          4          13025 1451   48
                                3        103         72          13025 1451   49
                               33        103        103          13025 1451   50
                                                                  3025 1  099999
                                                                  3025 0  0    0
 3.00640E+4 6.33800E+1          0          0          1          03025 2151    1
 3.00640E+4 1.00000E+0          0          0          1          03025 2151    2
 1.00000E+0 2.00000E+7          0          0          0          03025 2151    3
 0.0        6.70000E-1          0          0          0          03025 2151    4
                                                                  3025 2  099999
                                                                  3025 0  0    0
 3.00640E+4 6.33800E+1          0          0          0          03025 3103    1
 2.03600E+5 2.03600E+5          0          0          1        2063025 3103    2
        206          1                                            3025 3103    3
 500000.000 2.82258E-6 525000.000 8.46774E-6 550000.000 1.41129E-53025 3103    4
 575000.000 1.97581E-5 600000.000 2.59677E-5 630000.000 3.27419E-53025 3103    5
 660000.000 3.95161E-5 690000.000 4.62903E-5 720000.000 5.41935E-53025 3103    6
 760000.000 6.32258E-5 800000.000 7.22581E-5 840000.000 8.12903E-53025 3103    7
 880000.000 9.03226E-5 920000.000 9.93548E-5 960000.000 .0001083873025 3103    8
 1000000.00 .000124194 1100000.00 .000182215 1200000.00 .0003133333025 3103    9
 1300000.00 .000456625 1400000.00 .000819000 1500000.00 .0012710003025 3103   10
 1600000.00 .001886125 1700000.00 .002900000 1800000.00 .0039791253025 3103   11
 1900000.00 .006095000 2000000.00 .008635000 2100000.00 .0116475003025 3103   12
 2200000.00 .015815000 2300000.00 .020140000 2400000.00 .0267750003025 3103   13
 2500000.00 .034355000 2600000.00 .043101625 2700000.00 .0547000003025 3103   14
 2800000.00 .066454875 2900000.00 .078801000 3000000.00 .0913890003025 3103   15
 3100000.00 .101665125 3200000.00 .106290000 3300000.00 .1107457503025 3103   16
 3400000.00 .117132000 3500000.00 .124308000 3600000.00 .1297177503025 3103   17
 3700000.00 .130810000 3800000.00 .131846375 3900000.00 .1359710003025 3103   18
 4000000.00 .141359000 4100000.00 .146190125 4200000.00 .1496600003025 3103   19
 4300000.00 .153109375 4400000.00 .157469000 4500000.00 .1622010003025 3103   20
 4600000.00 .166793500 4700000.00 .171045000 4800000.00 .1752502503025 3103   21
 4900000.00 .178779000 5000000.00 .182031000 5100000.00 .1846305003025 3103   22
 5200000.00 .185635000 5300000.00 .186509125 5400000.00 .1861100003025 3103   23
 5500000.00 .185190000 5600000.00 .184270000 5700000.00 .1837981673025 3103   24
 5800000.00 .186015333 5900000.00 .188680667 6000000.00 .1913460003025 3103   25
 6100000.00 .194011333 6200000.00 .196676667 6300000.00 .1993420003025 3103   26
 6400000.00 .202007333 6500000.00 .203560000 6600000.00 .2040000003025 3103   27
 6700000.00 .204440000 6800000.00 .204880000 6900000.00 .2053200003025 3103   28
 7000000.00 .205760000 7100000.00 .206200000 7200000.00 .2066400003025 3103   29
 7300000.00 .207080000 7400000.00 .207520000 7500000.00 .2085860003025 3103   30
 7600000.00 .210278000 7700000.00 .211970000 7800000.00 .2136620003025 3103   31
 7900000.00 .215354000 8000000.00 .217046000 8100000.00 .2187380003025 3103   32
 8200000.00 .220430000 8300000.00 .222122000 8400000.00 .2238140003025 3103   33
 8500000.00 .225047333 8600000.00 .225822000 8700000.00 .2265966673025 3103   34
 8800000.00 .227371333 8900000.00 .228146000 9000000.00 .2289206673025 3103   35
 9100000.00 .229695333 9200000.00 .230470000 9300000.00 .2312446673025 3103   36
 9400000.00 .232019333 9500000.00 .232794000 9600000.00 .2335686673025 3103   37
 9700000.00 .234343333 9800000.00 .235118000 9900000.00 .2358926673025 3103   38
 10000000.0 .237326750 10100000.0 .239420250 10200000.0 .2415137503025 3103   39
 10300000.0 .243607250 10400000.0 .245700750 10500000.0 .2477942503025 3103   40
 10600000.0 .249887750 10700000.0 .251981250 10800000.0 .2540747503025 3103   41
 10900000.0 .256168250 11000000.0 .258261750 11100000.0 .2603552503025 3103   42
 11200000.0 .262448750 11300000.0 .264542250 11400000.0 .2666357503025 3103   43
 11500000.0 .268729250 11600000.0 .270822750 11700000.0 .2729162503025 3103   44
 11800000.0 .275009750 11900000.0 .277103250 12000000.0 .2756823333025 3103   45
 12100000.0 .270747000 12200000.0 .265811667 12300000.0 .2608763333025 3103   46
 12400000.0 .255941000 12500000.0 .251005667 12600000.0 .2460703333025 3103   47
 12700000.0 .241135000 12800000.0 .236199667 12900000.0 .2312643333025 3103   48
 13000000.0 .226329000 13100000.0 .221393667 13200000.0 .2164583333025 3103   49
 13300000.0 .211523000 13400000.0 .206587667 13500000.0 .2014446673025 3103   50
 13600000.0 .196094000 13700000.0 .190743333 13800000.0 .1853926673025 3103   51
 13900000.0 .180042000 14000000.0 .174691333 14100000.0 .1693406673025 3103   52
 14200000.0 .164595167 14300000.0 .163480667 14400000.0 .1629713333025 3103   53
 14500000.0 .162462000 14600000.0 .161564917 14700000.0 .1597200003025 3103   54
 14800000.0 .157882450 14900000.0 .157154800 15000000.0 .1568812003025 3103   55
 15100000.0 .156607600 15200000.0 .156334000 15300000.0 .1560604003025 3103   56
 15400000.0 .155786800 15500000.0 .153846000 15600000.0 .1502380003025 3103   57
 15700000.0 .146630000 15800000.0 .143022000 15900000.0 .1394140003025 3103   58
 16000000.0 .135806000 16100000.0 .132198000 16200000.0 .1285900003025 3103   59
 16300000.0 .124982000 16400000.0 .121374000 16500000.0 .1190220003025 3103   60
 16600000.0 .117926000 16700000.0 .116830000 16800000.0 .1157340003025 3103   61
 16900000.0 .114638000 17000000.0 .113542000 17100000.0 .1124460003025 3103   62
 17200000.0 .111350000 17300000.0 .110254000 17400000.0 .1091580003025 3103   63
 17500000.0 .108014000 17600000.0 .106822000 17700000.0 .1056300003025 3103   64
 17800000.0 .104438000 17900000.0 .103246000 18000000.0 .1020540003025 3103   65
 18100000.0 .100862000 18200000.0 .099670000 18300000.0 .0984780003025 3103   66
 18400000.0 .097286000 18500000.0 .096094000 18600000.0 .0949020003025 3103   67
 18700000.0 .093710000 18800000.0 .092518000 18900000.0 .0913260003025 3103   68
 19000000.0 .090134000 19100000.0 .088942000 19200000.0 .0877500003025 3103   69
 19300000.0 .086558000 19400000.0 .085366000 19500000.0 .0841740003025 3103   70
 19600000.0 .082982000 19700000.0 .081790000 19800000.0 .0805980003025 3103   71
 19900000.0 .079406000 20000000.0 0.0                             3025 3103   72
                                                                  3025 3  099999
                                                                  3025 0  0    0
 3.00640E+4 6.33800E+1          0          0          0          1302533103    1
 0.000000+0 0.000000+0          0        103          0          1302533103    2
 0.000000+0 0.000000+0          1          5        595         34302533103    3
 1.000000-5 5.000000+5 1.250000+6 1.500000+6 1.750000+6 2.000000+6302533103    4
 2.250000+6 2.500000+6 2.750000+6 3.000000+6 3.250000+6 3.500000+6302533103    5
 3.750000+6 4.000000+6 4.250000+6 4.500000+6 4.750000+6 5.000000+6302533103    6
 5.250000+6 5.500000+6 6.000000+6 7.000000+6 8.000000+6 9.000000+6302533103    7
 1.100000+7 1.300000+7 1.400000+7 1.450000+7 1.475000+7 1.500000+7302533103    8
 1.600000+7 1.700000+7 1.800000+7 2.000000+7 0.000000+0 0.000000+0302533103    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   13
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   14
 0.000000+0 2.758000-2 1.200000-2 4.857000-3 6.805000-3 4.971000-3302533103   15
 8.460000-3 4.433000-3 3.514000-3 1.692000-3 3.880000-3 3.062000-3302533103   16
 5.096000-3 2.596000-3 2.634000-3 2.421000-3 1.777000-3 1.526000-3302533103   17
 1.557000-3 7.218000-3 1.184000-2 7.041000-3 6.204000-3 7.538000-3302533103   18
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   19
 0.000000+0 0.000000+0 0.000000+0 1.615000-2 4.482000-3 6.411000-3302533103   20
 4.585000-3 5.210000-3 2.730000-3 2.164000-3 1.042000-3 2.389000-3302533103   21
 1.885000-3 3.138000-3 1.598000-3 1.622000-3 1.491000-3 1.094000-3302533103   22
 9.398000-4 9.590000-4 4.445000-3 7.290000-3 4.336000-3 3.820000-3302533103   23
 4.641000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   24
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 2.836000-3 2.774000-3302533103   25
 1.984000-3 2.060000-3 1.087000-3 8.945000-4 4.261000-4 9.489000-4302533103   26
 7.699000-4 1.188000-3 6.394000-4 6.142000-4 6.026000-4 4.510000-4302533103   27
 3.873000-4 4.072000-4 1.683000-3 2.760000-3 1.642000-3 1.446000-3302533103   28
 1.757000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   29
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 5.993000-3 2.889000-3302533103   30
 3.084000-3 1.693000-3 1.432000-3 6.238000-4 1.457000-3 1.193000-3302533103   31
 1.743000-3 9.765000-4 8.876000-4 9.231000-4 7.026000-4 5.713000-4302533103   32
 6.171000-4 2.276000-3 3.733000-3 2.221000-3 1.956000-3 2.377000-3302533103   33
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   34
 0.000000+0 0.000000+0 0.000000+0 3.267000-3 2.295000-3 1.580000-3302533103   35
 1.305000-3 6.053000-4 1.310000-3 1.084000-3 1.517000-3 8.736000-4302533103   36
 7.854000-4 8.454000-4 6.465000-4 4.638000-4 5.111000-4 1.723000-3302533103   37
 2.826000-3 1.681000-3 1.481000-3 1.799000-3 0.000000+0 0.000000+0302533103   38
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   39
 0.000000+0 1.350000-2 3.890000-3 3.412000-3 1.392000-3 3.312000-3302533103   40
 2.768000-3 3.732000-3 2.220000-3 1.877000-3 2.114000-3 1.643000-3302533103   41
 1.287000-3 1.437000-3 4.542000-3 7.450000-3 4.431000-3 3.904000-3302533103   42
 4.743000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   43
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 8.414000-3 4.098000-3302533103   44
 1.695000-3 4.151000-3 3.208000-3 4.880000-3 2.611000-3 2.491000-3302533103   45
 2.558000-3 1.920000-3 7.050000-4 7.961000-4 2.380000-3 3.903000-3302533103   46
 2.322000-3 2.045000-3 2.485000-3 0.000000+0 0.000000+0 0.000000+0302533103   47
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   48
 5.961000-3 1.333000-3 3.140000-3 2.527000-3 3.473000-3 2.009000-3302533103   49
 1.769000-3 1.981000-3 1.523000-3 6.798000-4 8.004000-4 1.887000-3302533103   50
 3.094000-3 1.841000-3 1.622000-3 1.970000-3 0.000000+0 0.000000+0302533103   51
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   52
 0.000000+0 1.119000-3 1.303000-3 1.064000-3 1.440000-3 8.430000-4302533103   53
 7.479000-4 8.387000-4 6.442000-4 3.101000-4 3.613000-4 9.086000-4302533103   54
 1.490000-3 8.864000-4 7.809000-4 9.488000-4 0.000000+0 0.000000+0302533103   55
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   56
 0.000000+0 5.087000-3 2.470000-3 3.722000-3 2.009000-3 1.899000-3302533103   57
 1.962000-3 1.477000-3 6.061000-4 6.814000-4 2.083000-3 3.417000-3302533103   58
 2.032000-3 1.790000-3 2.175000-3 0.000000+0 0.000000+0 0.000000+0302533103   59
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   60
 3.659000-3 2.758000-3 1.586000-3 1.410000-3 1.562000-3 1.198000-3302533103   61
 5.572000-4 6.482000-4 1.644000-3 2.696000-3 1.604000-3 1.413000-3302533103   62
 1.717000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   63
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 6.993000-3 2.319000-3302533103   64
 2.405000-3 2.231000-3 1.626000-3 5.785000-4 5.903000-4 2.736000-3302533103   65
 4.487000-3 2.669000-3 2.352000-3 2.857000-3 0.000000+0 0.000000+0302533103   66
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   67
 0.000000+0 2.175000-3 1.185000-3 1.254000-3 9.501000-4 4.225000-4302533103   68
 4.797000-4 1.394000-3 2.286000-3 1.359000-3 1.198000-3 1.455000-3302533103   69
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   70
 0.000000+0 0.000000+0 0.000000+0 1.832000-3 1.142000-3 8.323000-4302533103   71
 2.990000-4 3.052000-4 1.414000-3 2.320000-3 1.380000-3 1.216000-3302533103   72
 1.477000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   73
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 2.149000-3 9.390000-4302533103   74
 4.175000-4 4.802000-4 1.300000-3 2.132000-3 1.268000-3 1.117000-3302533103   75
 1.357000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   76
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.575000-3 4.662000-4302533103   77
 6.333000-4 1.395000-3 2.438000-3 1.427000-3 1.270000-3 1.525000-3302533103   78
 5.765000-4 1.114000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   79
 0.000000+0 0.000000+0 0.000000+0 8.956000-4 5.675000-4 1.243000-3302533103   80
 2.183000-3 1.276000-3 1.136000-3 1.364000-3 5.538000-4 1.070000-4302533103   81
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   82
 0.000000+0 1.740000-3 1.620000-3 2.923000-3 1.697000-3 1.518000-3302533103   83
 1.812000-3 1.024000-3 1.980000-4 0.000000+0 0.000000+0 0.000000+0302533103   84
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 9.308000-3 9.268000-3302533103   85
 5.435000-3 4.831000-3 5.810000-3 1.922000-3 3.715000-4 0.000000+0302533103   86
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   87
 2.783000-2 9.477000-3 8.434000-3 1.013000-2 3.808000-3 7.360000-4302533103   88
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   89
 0.000000+0 1.029000-2 5.352000-3 6.455000-3 2.163000-3 4.181000-4302533103   90
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   91
 0.000000+0 8.224000-3 5.780000-3 1.961000-3 3.791000-4 0.000000+0302533103   92
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0302533103   93
 1.200000-2 3.205000-3 4.455000-4 0.000000+0 0.000000+0 0.000000+0302533103   94
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.200000-2 1.649000-3302533103   95
 7.343000-4 2.925000-4 4.268000-4 1.552000-3 2.783000-3 3.330000-3302533103   96
 4.958000-3 1.162000-3 5.634000-4 2.219000-4 4.848000-4 3.209000-4302533103   97
 6.358000-4 7.888000-4 1.274000-3 1.183000-3 2.002000-4 5.519000-4302533103   98
 5.540000-4 6.012000-4 1.011000-3 2.382000-3 5.401000-4 1.775000-4302533103   99
 7.415000-5 1.623000-4 2.084000-4 3.578000-4 1.548000-3 6.073000-4302533103  100
 4.197000-4 7.127000-4 1.670000-3 2.862000-3 1.544000-3 2.636000-3302533103  101
 6.208000-3 3.103000-3 3.019000-3 6.528000-3 8.573000-3 1.380000-2302533103  102
 5.830000-2                                                       302533103  103
                                                                  302533  099999
                                                                  3025 0  0    0
                                                                     0 0  0    0
 3.30750E+4 7.42780E+1          0          0         34         103325 1451    1
 0.0        0.0                 0          0          0          63325 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20023325 1451    3
 3.00000E+2 0.0                 1          0        128          43325 1451    4
 33-As- 75 FEI        EVAL-Sep94  K.I.Zolotarev                   3325 1451    5
                      DIST-Feb2004                                3325 1451    6
----IRDF-2002         MATERIAL 3325                               3325 1451    7
-----INCIDENT NEUTRON DATA                                        3325 1451    8
------ENDF-6 FORMAT                                               3325 1451    9
***************************************************************** 3325 1451   10
 33-AS-75  FEI        EVAL-Sep94  K.I.Zolotarev                   3325 1451   11
                      DIST-May03                       20030504   3325 1451   12
----BROND-2           MATERIAL 3325                               3325 1451   13
------Russian Reactor Dosimetry File RRDF-2002                    3325 1451   14
***************************************************************** 3325 1451   15
Authors of evaluation: K.Zolotarev, V.Manokhin, A.Pashchenko      3325 1451   16
***************************************************************** 3325 1451   17
MF=3                                                              3325 1451   18
MT= 16  -  As-75(n,2n)As-74 reaction                              3325 1451   19
-------------------------------------                             3325 1451   20
    Evaluation was made on the base  of experimental data [1-18]. 3325 1451   21
Systematics of  (n,2n) excitation functions [19]  was taken into  3325 1451   22
account in the energy region 10.5 - 13.0 MeV and 19.0 - 20.0 MeV. 3325 1451   23
Cross section data of  E.Paul  and  R.Clarke [20]  were rejected  3325 1451   24
due to  inconsistency  with  main bulk  of experimental data and  3325 1451   25
systematics of (n,2n) excitation functions.                       3325 1451   26
    Statistical analysis of input cross section data was carried  3325 1451   27
out by means of PADE-2 code [21].  Rational function was used as  3325 1451   28
the model function [22].                                          3325 1451   29
    Integral experimental data for  U-235 thermal fission neutron 3325 1451   30
spectrum [23-24]  was used for testing evaluated As-75(n,2n)As-74 3325 1451   31
excitation function. The results of testing are given in Table 1. 3325 1451   32
    Data for  U-235 thermal fission neutron spectrum  and  Cf-252 3325 1451   33
spontaneous fission neutron spectrum were taken from ref.[25] and 3325 1451   34
[26],  respectively.                                              3325 1451   35
                                                        Table 1.  3325 1451   36
  3325 1451   37
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  3325 1451   38
  3325 1451   39
 U-235 neutron fission  0.30920           0.304 +- 0.036 [22]   3325 1451   40
                                          0.311 +- 0.023 [23]   3325 1451   41
  3325 1451   42
 Cf-252 spont. fission  0.61804                                 3325 1451   43
  3325 1451   44
                                                                  3325 1451   45
MT=33                                                             3325 1451   46
MT= 16 -(n,2n) cross section cov. matrix                          3325 1451   47
----------------------------------------                          3325 1451   48
    Uncertainties in the evaluated  excitation function  for the  3325 1451   49
reaction As-75(n,2n)As-74 are given in the form of relative cova- 3325 1451   50
riance matrix for the 19-neutron energy groups (LB=5). Covariance 3325 1451   51
matrix  of  uncertainties  was  calculated  simultaneously  with  3325 1451   52
recommended cross section data by means of PADE-2 code.           3325 1451   53
    Eigenvalues  of the  6-th digits  relative covariance matrix  3325 1451   54
given in the 33-file are the following:                           3325 1451   55
                                                                  3325 1451   56
    2.79921E-09    3.33401E-09    3.76284E-09    3.88107E-09      3325 1451   57
    4.19122E-09    4.53852E-09    4.91657E-09    5.52980E-09      3325 1451   58
    7.06444E-09    1.01577E-08    1.66580E-08    2.33017E-08      3325 1451   59
    1.49576E-07    8.86325E-04    3.07310E-03    3.70656E-03      3325 1451   60
    9.37209E-03    1.38518E-02    8.84386E-02                     3325 1451   61
                                                                  3325 1451   62
References :                                                      3325 1451   63
 1. R.J.Prestwood, B.P.Bayhurst  Phys. Rev., v.121, p.1438, 1961  3325 1451   64
 2. B.Granger, M.Longueve  Report EANDC(E)-49L, p.83, Oct. 1963   3325 1451   65
 3. P.Hille, H.Muenzer Acta Phys. Austriaca, v.23, p.44, May 1966 3325 1451   66
 4. J.Csikai, G.Peto  Acta Physica Hung., v.23, p.87, May 1967    3325 1451   67
 5. M.Bormann et al.  Nucl. Phys., v.A115, p.309, July 1968       3325 1451   68
    M.Bormann et al.  Progress Report EANDC(E)-76, January 1967   3325 1451   69
 6. P.R.Prasad et al.  Nucl. Phys., v.A138, p.85, November 1969   3325 1451   70
 7. P.Venugopala Rao et al.  Phys. Rev., v.C3, p.629, Feb. 1971   3325 1451   71
 8. M.Wagner, M.Uhl  Oesterr. Akad. Wiss., Math.+Naturw. Anzeiger,3325 1451   72
    v.108, p.185, November 1971                                   3325 1451   73
 9. S.M.Qaim  Nucl. Phys., Sec.A, v.185, p.614, May 1972          3325 1451   74
10. D.V.Viktorov, V.L.Sjablin Jadernaja Fizika, v.15,p.1099, 1972 3325 1451   75
11. C.T.Simpson et al. Inorg. Nucl. Chem., v.35, p.2085,June 1973 3325 1451   76
12. J.Araminowicz,J.Dresler Peport INR-1464, Warsaw,p.14,May 1973 3325 1451   77
13. W.Grochulski et al.  Acta Physica Polonica, v.B6,p.139, 1975  3325 1451   78
14. R.A.Sigg  Dissertation Abstract, sec.B, v.37,p.2237, Nov.1976 3325 1451   79
15. J.L.Casanova,M.L.Sanchez  Anales de Fisica y Quimica (Spain), 3325 1451   80
    v.72, n.3, p.186, July 1976                                   3325 1451   81
16. S.Sothras  Dissertation Abstract, sec.B,v.38,p.280, July 1978 3325 1451   82
17. C.Konno, Y.Ikeda, K.Oishi e.a.  Report JAERI-1329, Oct. 1993  3325 1451   83
18. I.Birn, S.M.Qaim  Nucl. Sci. Eng., v.116, p.125-137, 1994     3325 1451   84
19. V.N.Manokhin   VANT, Ser.:Yadernye Konstanty, 1994, No. 1,    3325 1451   85
    pp.18-22                                                      3325 1451   86
20. E.B.Paul, R.L.Clarke  Can. J. Phys., v.31, p.267, 1953        3325 1451   87
21. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          3325 1451   88
22. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 3325 1451   89
    st's Meeting on Evaluation and Processing of Covariance Data, 3325 1451   90
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  3325 1451   91
23. F.Nasyrov, B.D.Sciborskij   Atomnaja Energija, v.25, no.5,    3325 1451   92
    p.437, November 1968                                          3325 1451   93
24. E.Steinnes  Radiochimica Acta, v.13, p.169, June 1970         3325 1451   94
25. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 3325 1451   95
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              3325 1451   96
26. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        3325 1451   97
***************************************************************** 3325 1451   98
  The Q values and threshold energies were updated prior to pro-  3325 1451   99
  cessing through the codes to comply with the values obtained    3325 1451  100
  using the NNDC calculation program which is based on the 1995   3325 1451  101
  Update to the Atomic mass Evaluation.                           3325 1451  102
                                                                  3325 1451  103
 File 2 added to the pointwise file containing only the effective 3325 1451  104
 scattering radius with no resonance parameters given.            3325 1451  105
 Taken from ENDF/B-VI                                             3325 1451  106
***************************************************************** 3325 1451  107
 ***************** Program LINEAR (VERSION 2002-1) ***************3325 1451  108
 For All Data Greater than 1.0000E-10 barns in Absolute Value     3325 1451  109
 Data Linearized to Within an Accuracy of .100000000 per-cent     3325 1451  110
 ***************** Program SIGMA1 (VERSION 2002-1) ***************3325 1451  111
 Data Doppler Broadened to 300.000000 Kelvin                      3325 1451  112
 for All Data Greater than 1.0000E-10 barns in Absolute Value     3325 1451  113
 Data Linearized to Within an Accuracy pf .100000000 per-cent     3325 1451  114
 ***************** Program FIXUP (Version 2002-1) ****************3325 1451  115
 Corrected ZA/AWR in All Sections-----------------------------Yes 3325 1451  116
 Corrected Thresholds-----------------------------------------Yes 3325 1451  117
 Extended Cross Sections to 20 MeV----------------------------No  3325 1451  118
 Allow Cross Section Deletion---------------------------------No  3325 1451  119
 Allow Cross Section Reconstruction---------------------------No  3325 1451  120
 Make All Cross Sections Non-Negative-------------------------Yes 3325 1451  121
 Delete Energies Not in Ascending Order-----------------------Yes 3325 1451  122
 Deleted Duplicate Points-------------------------------------Yes 3325 1451  123
 Check for Ascending MAT/MF/MT Order--------------------------Yes 3325 1451  124
 Check for Legal MF/MT Numbers--------------------------------Yes 3325 1451  125
 Allow Creation of Missing Sections---------------------------No  3325 1451  126
 Allow Insertion of Energy Points-----------------------------No  3325 1451  127
 Create Uniform Energy Grid-----------------------------------No  3325 1451  128
 Delete Section if Cross Section =0 at All Energies-----------Yes 3325 1451  129
 ***************** Program GROUPIE (VERSION 2002-1) **************3325 1451  130
 Unshielded Group Averages Using  640 Groups                      3325 1451  131
 Weighting Spectrum: Flat (Constant) Spectrum                     3325 1451  132
                                1        451        136          13325 1451  133
                                2        151          4          13325 1451  134
                                3         16         36          13325 1451  135
                               33         16         42          13325 1451  136
                                                                  3325 1  099999
                                                                  3325 0  0    0
 3.30750E+4 7.42780E+1          0          0          1          03325 2151    1
 3.307500+4 1.000000+0          0          0          1          03325 2151    2
 1.000000-5 2.405300+3          0          0          0          03325 2151    3
 1.500000+0 0.508630+0          0          0          0          03325 2151    4
                                                                  3325 2  099999
                                                                  3325 0  0    0
 3.30750E+4 7.42780E+1          0          0          0          03325 3 16    1
-1.02442E+7-1.02442E+7          0          0          1         983325 3 16    2
         98          1                                            3325 3 16    3
 10300000.0 6.04805E-6 10400000.0 .000608735 10500000.0 .0052550503325 3 16    4
 10600000.0 .014392210 10700000.0 .028074850 10800000.0 .0460172503325 3 16    5
 10900000.0 .067864400 11000000.0 .093207450 11100000.0 .1216010003325 3 16    6
 11200000.0 .152580000 11300000.0 .185675000 11400000.0 .2204260003325 3 16    7
 11500000.0 .256394000 11600000.0 .293214625 11700000.0 .3303858753325 3 16    8
 11800000.0 .367557125 11900000.0 .404728375 12000000.0 .4413397503325 3 16    9
 12100000.0 .477391250 12200000.0 .512559250 12300000.0 .5468437503325 3 16   10
 12400000.0 .580032500 12500000.0 .612125500 12600000.0 .6430125003325 3 16   11
 12700000.0 .672693500 12800000.0 .701134000 12900000.0 .7283340003325 3 16   12
 13000000.0 .754310750 13100000.0 .779064250 13200000.0 .8026452503325 3 16   13
 13300000.0 .825053750 13400000.0 .846360250 13500000.0 .8665647503325 3 16   14
 13600000.0 .885747750 13700000.0 .903909250 13800000.0 .9209150003325 3 16   15
 13900000.0 .936765000 14000000.0 .952615000 14100000.0 .9672400003325 3 16   16
 14200000.0 .980640000 14300000.0 .994040000 14400000.0 1.006381673325 3 16   17
 14500000.0 1.01766500 14600000.0 1.02894833 14700000.0 1.039320003325 3 16   18
 14800000.0 1.04878000 14900000.0 1.05824000 15000000.0 1.066797503325 3 16   19
 15100000.0 1.07445250 15200000.0 1.08210750 15300000.0 1.089762503325 3 16   20
 15400000.0 1.09655125 15500000.0 1.10247375 15600000.0 1.108396253325 3 16   21
 15700000.0 1.11431875 15800000.0 1.11943900 15900000.0 1.123757003325 3 16   22
 16000000.0 1.12807500 16100000.0 1.13239300 16200000.0 1.136711003325 3 16   23
 16300000.0 1.14029100 16400000.0 1.14313300 16500000.0 1.145975003325 3 16   24
 16600000.0 1.14881700 16700000.0 1.15165900 16800000.0 1.153825003325 3 16   25
 16900000.0 1.15531500 17000000.0 1.15680500 17100000.0 1.158295003325 3 16   26
 17200000.0 1.15978500 17300000.0 1.16127500 17400000.0 1.162227503325 3 16   27
 17500000.0 1.16264250 17600000.0 1.16305750 17700000.0 1.163472503325 3 16   28
 17800000.0 1.16335214 17900000.0 1.16269643 18000000.0 1.162040713325 3 16   29
 18100000.0 1.16138500 18200000.0 1.16072929 18300000.0 1.160073573325 3 16   30
 18400000.0 1.15941786 18500000.0 1.15810500 18600000.0 1.156135003325 3 16   31
 18700000.0 1.15416500 18800000.0 1.15219500 18900000.0 1.150225003325 3 16   32
 19000000.0 1.14825500 19100000.0 1.14628500 19200000.0 1.143680003325 3 16   33
 19300000.0 1.14044000 19400000.0 1.13720000 19500000.0 1.133960003325 3 16   34
 19600000.0 1.13072000 19700000.0 1.12748000 19800000.0 1.123815003325 3 16   35
 19900000.0 1.11972500 20000000.0 0.0                             3325 3 16   36
                                                                  3325 3  099999
                                                                  3325 0  0    0
 3.30750E+4 7.42780E+1          0          0          0          1332533 16    1
 0.000000+0 0.000000+0          0         16          0          1332533 16    2
 0.000000+0 0.000000+0          1          5        231         21332533 16    3
 1.000000-5 1.030000+7 1.100000+7 1.150000+7 1.200000+7 1.250000+7332533 16    4
 1.300000+7 1.350000+7 1.400000+7 1.450000+7 1.500000+7 1.550000+7332533 16    5
 1.600000+7 1.650000+7 1.700000+7 1.750000+7 1.800000+7 1.850000+7332533 16    6
 1.900000+7 1.950000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0332533 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0332533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0332533 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 4.254080-2332533 16   10
 3.081380-2 1.931400-2 1.096210-2 5.721690-3 2.776080-3 1.317510-3332533 16   11
 7.548290-4 7.048850-4 9.349630-4 1.310960-3 1.762040-3 2.258760-3332533 16   12
 2.801620-3 3.416040-3 4.153410-3 5.097380-3 6.377610-3 8.194880-3332533 16   13
 2.503660-2 1.710970-2 1.053310-2 5.933080-3 3.031140-3 1.367320-3332533 16   14
 5.445340-4 2.757120-4 3.679670-4 6.958200-4 1.178950-3 1.766310-3332533 16   15
 2.425790-3 3.137300-3 3.888340-3 4.670750-3 5.478140-3 6.303300-3332533 16   16
 1.310600-2 9.036090-3 5.666770-3 3.182410-3 1.508880-3 4.972090-4332533 16   17
 1.198130-6-9.989140-5 9.961100-5 5.258840-4 1.118440-3 1.823060-3332533 16   18
 2.584600-3 3.338870-3 4.001790-3 4.453280-3 4.511120-3 6.875300-3332533 16   19
 4.696000-3 2.853540-3 1.466050-3 5.292000-4-8.635390-6-2.104130-4332533 16   20
-1.367730-4 1.569210-4 6.190120-4 1.197530-3 1.834630-3 2.458670-3332533 16   21
 2.972620-3 3.235810-3 3.033720-3 3.453490-3 2.266810-3 1.294430-3332533 16   22
 5.856670-4 1.362000-4-8.005410-5-9.600310-5 5.413750-5 3.357960-4332533 16   23
 7.122850-4 1.141420-3 1.569950-3 1.925150-3 2.101170-3 1.936260-3332533 16   24
 1.633900-3 1.073760-3 6.359020-4 3.318380-4 1.553350-4 9.295540-5332533 16   25
 1.286100-4 2.450480-4 4.234780-4 6.421240-4 8.735030-4 1.080130-3332533 16   26
 1.207510-3 1.172240-3 8.558900-4 6.667390-4 5.164420-4 4.069720-4332533 16   27
 3.365790-4 3.019830-4 2.993640-4 3.246310-4 3.733290-4 4.402050-4332533 16   28
 5.184400-4 5.983440-4 6.651090-4 6.747560-4 6.610070-4 6.283810-4332533 16   29
 5.803990-4 5.209130-4 4.541900-4 3.852600-4 3.205060-4 2.685700-4332533 16   30
 2.417760-4 2.584150-4 3.465920-4 7.554750-4 7.992770-4 7.962510-4332533 16   31
 7.522190-4 6.741240-4 5.700760-4 4.499610-4 3.267030-4 2.183230-4332533 16   32
 1.513670-4 1.667090-4 9.133160-4 9.708800-4 9.754440-4 9.318050-4332533 16   33
 8.455750-4 7.232610-4 5.729600-4 4.056160-4 2.372370-4 9.272540-5332533 16   34
 1.098580-3 1.177030-3 1.204940-3 1.180740-3 1.101790-3 9.636420-4332533 16   35
 7.593550-4 4.784870-4 1.055990-4 1.346410-3 1.473240-3 1.545330-3332533 16   36
 1.546490-3 1.454020-3 1.234990-3 8.406180-4 1.969000-4 1.715590-3332533 16   37
 1.907030-3 2.015320-3 1.996100-3 1.785820-3 1.290460-3 3.668920-4332533 16   38
 2.227810-3 2.458970-3 2.534180-3 2.358840-3 1.793140-3 6.238740-4332533 16   39
 2.814850-3 2.998200-3 2.888540-3 2.307930-3 9.846970-4 3.293890-3332533 16   40
 3.287670-3 2.782370-3 1.476680-3 3.433180-3 3.143590-3 2.141300-3332533 16   41
 3.284480-3 3.040640-3 4.268410-3                                 332533 16   42
                                                                  332533  099999
                                                                  3325 0  0    0
                                                                     0 0  0    0
 3.90890E+4 8.81421E+1          0          0         34         103925 1451    1
 0.0        0.0                 0          0          0          63925 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20023925 1451    3
 3.00000E+2 0.0                 1          0         91          43925 1451    4
 39-Y - 89 SRI        EVAL-JAN96 N.ODANO (SHIP RES. INST.)        3925 1451    5
                      DIST-Feb2004                                3925 1451    6
----IRDF-2002         MATERIAL 3925                               3925 1451    7
-----INCIDENT NEUTRON DATA                                        3925 1451    8
------ENDF-6 FORMAT                                               3925 1451    9
***************************************************************   3925 1451   10
 39- Y- 89 SRI        EVAL-JAN96 N.ODANO (SHIP RES. INST.)        3925 1451   11
                      DIST-JUL98                                  3925 1451   12
----JENDL/D-99        MATERIAL 3925                               3925 1451   13
***************************************************************   3925 1451   14
HISTORY                                                           3925 1451   15
96-01   EVALUATION FOR JENDL DOSIMETRY FILE VERSION 2 WAS MADE BY 3925 1451   16
        N.ODANO (SHIP RES. INST.).                                3925 1451   17
97-09   COMPILED TO JENDL DOSIMETRY FILE 99.                      3925 1451   18
                                                                  3925 1451   19
             ==== POINT-WISE DATA FILE ====                       3925 1451   20
                                                                  3925 1451   21
 <DOSIMETRY CROSS SECTION>                                        3925 1451   22
      Y-89 (N,2N) Y-88 (HALF-LIFE = 106.65D)                      3925 1451   23
                                                                  3925 1451   24
MF=1  GENERAL INFORMATION                                         3925 1451   25
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          3925 1451   26
                                                                  3925 1451   27
MF=2  RESONANCE PARAMETERS                                        3925 1451   28
 MT=151  PARAMETERS                                               3925 1451   29
     ONLY SPIN AND SCATTERING RADIUS ARE GIVEN.                   3925 1451   30
                                                                  3925 1451   31
MF=3 NEUTRON CROSS SECTIONS                                       3925 1451   32
 MT=16 (N,2N) CROSS SECTION                                       3925 1451   33
        EXPERIMENTAL DATA/1-17/ IN NESTOR-2/18/ WERE TAKEN FOR    3925 1451   34
        THE EVALUATION USING GMA CODE/19/.                        3925 1451   35
                                                                  3925 1451   36
MF=33 COVARIANCES OF NEUTRON CROSS SECTIONS                       3925 1451   37
 MT=16  GENERATED USING THE GMA CODE.                             3925 1451   38
                                                                  3925 1451   39
REFERENCES                                                        3925 1451   40
 1) O.M.HUDSON, JR.+ : BULLETIN OF THE AMERICAN PHYSICAL SOCIETY, 3925 1451   41
    6, 506(E9) (1961).                                            3925 1451   42
 2) R.RIEDER+ : EANDC(E)-49L, 83 (1965).                          3925 1451   43
 3) D.G.VALLIS : AWRE-O-76/66 (1966).                             3925 1451   44
 4) J.CSIKAI+ : ACTA PHYSICA HANGARIA, 23, 87 (1967).             3925 1451   45
 5) D.S.MATHER+ : AWRE-O-47/69 (1969).                            3925 1451   46
 6) D.R.NETHAWAY : NUCL. PHYS. A, 190, 635 (1972).                3925 1451   47
 7) S.M.QAIM+ : EUR-5182E, 939 (1974).                            3925 1451   48
 8) B.P.BAYHURST+ : PHYS. REV. C, 12, 451 (1975).                 3925 1451   49
 9) S.K.GHORAI+ : NUCL. PHYS. A, 266, 53 (1976).                  3925 1451   50
10) M.BORMANN+ : Z. PHYS. A, 277, 203 (1976).                     3925 1451   51
11) L.R.VEESER+ : PHYS. REV. C, 16, 1792 (1977).                  3925 1451   52
12) J.FREHAUT+ : PROC. SYMP. ON NEUTRON CROSS SECTIONS FROM 10-50 3925 1451   53
    MEV, UPTON, USA, 12-14, 1980, P.399 (1980).                   3925 1451   54
13) J.LAUREC+ : CEA-R-5109 (1981).                                3925 1451   55
14) P.RAICS+ : ATOMKI KOZLEMENYEK, 23, 45 (1981).                 3925 1451   56
15) L.R.GREENWOOD : ASTM-STP-956, 743 (1987).                     3925 1451   57
16) HUANG JIAN-ZHOU+ : INDC(CPR)-16 (189).                        3925 1451   58
17) C.KONNO+ : JAERI 1329 (1993).                                 3925 1451   59
18) T.NAKAGAWA : THE JAERI NUCLEAR DATA CENTER, UNPUBLISHED.      3925 1451   60
19) W.P.POENITZ : PROC. CONF. NUCLEAR DATA EVALUATION METHODS     3925 1451   61
    AND PROCEDURES, BROOKHAVEN NATIONAL LAB. 1980, BNL-NCS-       3925 1451   62
    51363, P.249 (1981).                                          3925 1451   63
***************************************************************   3925 1451   64
  The Q values and threshold energies were updated prior to pro-  3925 1451   65
  cessing through the codes to comply with the values obtained    3925 1451   66
  using the NNDC calculation program which is based on the 1995   3925 1451   67
  Update to the Atomic mass Evaluation.                           3925 1451   68
***************************************************************   3925 1451   69
                                                                  3925 1451   70
 ***************** Program LINEAR (VERSION 2002-1) ***************3925 1451   71
 For All Data Greater than 1.0000E-10 barns in Absolute Value     3925 1451   72
 Data Linearized to Within an Accuracy of .100000000 per-cent     3925 1451   73
 ***************** Program SIGMA1 (VERSION 2002-1) ***************3925 1451   74
 Data Doppler Broadened to 300.000000 Kelvin                      3925 1451   75
 for All Data Greater than 1.0000E-10 barns in Absolute Value     3925 1451   76
 Data Linearized to Within an Accuracy pf .100000000 per-cent     3925 1451   77
 ***************** Program FIXUP (Version 2002-1) ****************3925 1451   78
 Corrected ZA/AWR in All Sections-----------------------------Yes 3925 1451   79
 Corrected Thresholds-----------------------------------------Yes 3925 1451   80
 Extended Cross Sections to 20 MeV----------------------------No  3925 1451   81
 Allow Cross Section Deletion---------------------------------No  3925 1451   82
 Allow Cross Section Reconstruction---------------------------No  3925 1451   83
 Make All Cross Sections Non-Negative-------------------------Yes 3925 1451   84
 Delete Energies Not in Ascending Order-----------------------Yes 3925 1451   85
 Deleted Duplicate Points-------------------------------------Yes 3925 1451   86
 Check for Ascending MAT/MF/MT Order--------------------------Yes 3925 1451   87
 Check for Legal MF/MT Numbers--------------------------------Yes 3925 1451   88
 Allow Creation of Missing Sections---------------------------No  3925 1451   89
 Allow Insertion of Energy Points-----------------------------No  3925 1451   90
 Create Uniform Energy Grid-----------------------------------No  3925 1451   91
 Delete Section if Cross Section =0 at All Energies-----------Yes 3925 1451   92
 ***************** Program GROUPIE (VERSION 2002-1) **************3925 1451   93
 Unshielded Group Averages Using  640 Groups                      3925 1451   94
 Weighting Spectrum: Flat (Constant) Spectrum                     3925 1451   95
                                1        451         99          03925 1451   96
                                2        151          4          03925 1451   97
                                3         16         32          03925 1451   98
                               33         16         23          03925 1451   99
                                                                  3925 1  099999
                                                                  3925 0  0    0
 3.90890E+4 8.81421E+1          0          0          1          03925 2151    1
 3.90890E+4 1.00000E+0          0          0          1          03925 2151    2
 0.0        0.0                 0          0          0          03925 2151    3
 5.00000E-1 6.70000E-1          0          0          0          03925 2151    4
                                                                  3925 2  099999
                                                                  3925 0  0    0
 3.90890E+4 8.81421E+1          0          0          0          03925 3 16    1
-1.14760E+7-1.14760E+7          0          0          1         853925 3 16    2
         85          1                                            3925 3 16    3
 11600000.0 .008985210 11700000.0 .030140246 11800000.0 .0559560003925 3 16    4
 11900000.0 .082542000 12000000.0 .109128000 12100000.0 .1357140003925 3 16    5
 12200000.0 .163801750 12300000.0 .200900000 12400000.0 .2395000003925 3 16    6
 12500000.0 .278100000 12600000.0 .316700000 12700000.0 .3553000003925 3 16    7
 12800000.0 .393900000 12900000.0 .432500000 13000000.0 .4743200003925 3 16    8
 13100000.0 .519360000 13200000.0 .564400000 13300000.0 .6094400003925 3 16    9
 13400000.0 .654480000 13500000.0 .692660000 13600000.0 .7239800003925 3 16   10
 13700000.0 .755300000 13800000.0 .786620000 13900000.0 .8179400003925 3 16   11
 14000000.0 .847270000 14100000.0 .874610000 14200000.0 .9019500003925 3 16   12
 14300000.0 .929290000 14400000.0 .956630000 14500000.0 .9775700003925 3 16   13
 14600000.0 .992110000 14700000.0 1.00665000 14800000.0 1.021190003925 3 16   14
 14900000.0 1.03573000 15000000.0 1.04830000 15100000.0 1.058900003925 3 16   15
 15200000.0 1.06950000 15300000.0 1.08010000 15400000.0 1.090700003925 3 16   16
 15500000.0 1.10190000 15600000.0 1.11370000 15700000.0 1.125500003925 3 16   17
 15800000.0 1.13730000 15900000.0 1.14910000 16000000.0 1.158350003925 3 16   18
 16100000.0 1.16505000 16200000.0 1.17175000 16300000.0 1.178450003925 3 16   19
 16400000.0 1.18515000 16500000.0 1.19185000 16600000.0 1.198550003925 3 16   20
 16700000.0 1.20525000 16800000.0 1.21195000 16900000.0 1.218650003925 3 16   21
 17000000.0 1.22130000 17100000.0 1.21990000 17200000.0 1.218500003925 3 16   22
 17300000.0 1.21710000 17400000.0 1.21570000 17500000.0 1.214300003925 3 16   23
 17600000.0 1.21290000 17700000.0 1.21150000 17800000.0 1.210100003925 3 16   24
 17900000.0 1.20870000 18000000.0 1.20790000 18100000.0 1.207700003925 3 16   25
 18200000.0 1.20750000 18300000.0 1.20730000 18400000.0 1.207100003925 3 16   26
 18500000.0 1.20690000 18600000.0 1.20670000 18700000.0 1.206500003925 3 16   27
 18800000.0 1.20630000 18900000.0 1.20610000 19000000.0 1.205900003925 3 16   28
 19100000.0 1.20570000 19200000.0 1.20550000 19300000.0 1.205300003925 3 16   29
 19400000.0 1.20510000 19500000.0 1.20490000 19600000.0 1.204700003925 3 16   30
 19700000.0 1.20450000 19800000.0 1.20430000 19900000.0 1.204100003925 3 16   31
 20000000.0 0.0                                                   3925 3 16   32
                                                                  3925 3  099999
                                                                  3925 0  0    0
 3.90890E+4 8.81421E+1          0          0          0          1392533 16    1
 0.000000+0 0.000000+0          0         16          0          1392533 16    2
 0.000000+0 0.000000+0          1          5        120         15392533 16    3
 1.000000-5 1.160000+7 1.167980+7 1.200000+7 1.262500+7 1.325000+7392533 16    4
 1.375000+7 1.425000+7 1.475000+7 1.525000+7 1.575000+7 1.650000+7392533 16    5
 1.750000+7 1.900000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0392533 16    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0392533 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 2.614690-2392533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0392533 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0392533 16   10
 2.614690-2 2.351680-4 2.278630-4 9.042900-5 9.259900-5 8.525630-5392533 16   11
 8.299090-5 7.707100-5 4.918100-5 5.777220-5 5.017710-5 4.334530-5392533 16   12
 2.515020-3 1.482340-4 7.056710-5 6.952990-5 6.360270-5 6.802450-5392533 16   13
 5.867100-5 4.991930-5 5.263290-5 5.027740-5 3.826150-5 1.181300-3392533 16   14
 1.041660-4 9.116020-5 1.023620-4 8.883020-5 1.176510-4 7.032450-5392533 16   15
 8.058560-5 7.055540-5 5.527930-5 3.254420-4 1.149980-4 1.205660-4392533 16   16
 1.177200-4 1.281940-4 7.931010-5 9.144310-5 8.052500-5 6.472540-5392533 16   17
 2.271050-4 1.022200-4 1.102170-4 9.664150-5 6.583630-5 8.648390-5392533 16   18
 7.769970-5 7.830730-5 2.030630-4 1.065710-4 1.315170-4 8.313670-5392533 16   19
 9.450610-5 8.571720-5 6.963890-5 3.359890-4 1.032510-4 6.690090-5392533 16   20
 7.735940-5 6.913090-5 5.707270-5 1.877490-3 1.006380-4 1.132040-4392533 16   21
 9.722290-5 7.147720-5 7.645230-4 9.817050-5 1.108810-4 1.009150-4392533 16   22
 4.986290-4 1.343200-4 1.551700-4 5.697770-4 1.678400-4 4.251840-4392533 16   23
                                                                  392533  099999
                                                                  3925 0  0    0
                                                                     0 0  0    0
 4.00900E+4 8.91324E+1          0          0         34         104025 1451    1
 0.0        0.0                 0          0          0          64025 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20024025 1451    3
 3.00000E+2 0.0                 1          0         40          44025 1451    4
 40-Zr- 90 IRK-VIENNA EVAL-APR90                                  4025 1451    5
                      DIST-Feb2004                                4025 1451    6
----IRDF-2002         MATERIAL 4025                               4025 1451    7
-----INCIDENT NEUTRON DATA                                        4025 1451    8
------ENDF-6 FORMAT                                               4025 1451    9
 *****************************************************************4025 1451   10
 40-ZR- 90 IRK-VIENNA EVAL-APR90                                  4025 1451   11
                      DIST-JUN90                                  4025 1451   12
    IRK-EVAL.NLIB 25  4025                                        4025 1451   13
 *****************************************************************4025 1451   14
  The Q values and threshold energies were updated prior to pro-  4025 1451   15
  cessing through the codes to comply with the values obtained    4025 1451   16
  using the NNDC calculation program which is based on the 1995   4025 1451   17
  Update to the Atomic mass Evaluation.                           4025 1451   18
 *****************************************************************4025 1451   19
 ***************** Program LINEAR (VERSION 2002-1) ***************4025 1451   20
 For All Data Greater than 1.0000E-10 barns in Absolute Value     4025 1451   21
 Data Linearized to Within an Accuracy of .100000000 per-cent     4025 1451   22
 ***************** Program SIGMA1 (VERSION 2002-1) ***************4025 1451   23
 Data Doppler Broadened to 300.000000 Kelvin                      4025 1451   24
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4025 1451   25
 Data Linearized to Within an Accuracy pf .100000000 per-cent     4025 1451   26
 ***************** Program FIXUP (Version 2002-1) ****************4025 1451   27
 Corrected ZA/AWR in All Sections-----------------------------Yes 4025 1451   28
 Corrected Thresholds-----------------------------------------Yes 4025 1451   29
 Extended Cross Sections to 20 MeV----------------------------No  4025 1451   30
 Allow Cross Section Deletion---------------------------------No  4025 1451   31
 Allow Cross Section Reconstruction---------------------------No  4025 1451   32
 Make All Cross Sections Non-Negative-------------------------Yes 4025 1451   33
 Delete Energies Not in Ascending Order-----------------------Yes 4025 1451   34
 Deleted Duplicate Points-------------------------------------Yes 4025 1451   35
 Check for Ascending MAT/MF/MT Order--------------------------Yes 4025 1451   36
 Check for Legal MF/MT Numbers--------------------------------Yes 4025 1451   37
 Allow Creation of Missing Sections---------------------------No  4025 1451   38
 Allow Insertion of Energy Points-----------------------------No  4025 1451   39
 Create Uniform Energy Grid-----------------------------------No  4025 1451   40
 Delete Section if Cross Section =0 at All Energies-----------Yes 4025 1451   41
 ***************** Program GROUPIE (VERSION 2002-1) **************4025 1451   42
 Unshielded Group Averages Using  640 Groups                      4025 1451   43
 Weighting Spectrum: Flat (Constant) Spectrum                     4025 1451   44
                                1        451         48          14025 1451   45
                                2        151          4          14025 1451   46
                                3         16         30          14025 1451   47
                               33         16         46          14025 1451   48
                                                                  4025 1  099999
                                                                  4025 0  0    0
 4.00900E+4 8.91324E+1          0          0          1          04025 2151    1
 4.00900E+4 1.00000E+0          0          0          1          04025 2151    2
 1.00000E+0 2.00000E+7          0          0          0          04025 2151    3
 0.0        7.10000E-1          0          0          0          04025 2151    4
                                                                  4025 2  099999
                                                                  4025 0  0    0
 4.00900E+4 8.91324E+1          0          0          0          04025 3 16    1
-1.19700E+7-1.19700E+7          0          0          1         804025 3 16    2
         80          1                                            4025 3 16    3
 12100000.0 .005470824 12200000.0 .017333776 12300000.0 .0342925004025 3 16    4
 12400000.0 .056337500 12500000.0 .081985000 12600000.0 .1112350004025 3 16    5
 12700000.0 .144872500 12800000.0 .182897500 12900000.0 .2225200004025 3 16    6
 13000000.0 .263740000 13100000.0 .303092500 13200000.0 .3405775004025 3 16    7
 13300000.0 .376913750 13400000.0 .412101250 13500000.0 .4472887504025 3 16    8
 13600000.0 .482476250 13700000.0 .516977500 13800000.0 .5507925004025 3 16    9
 13900000.0 .582510000 14000000.0 .612130000 14100000.0 .6424475004025 3 16   10
 14200000.0 .673462500 14300000.0 .703267500 14400000.0 .7318625004025 3 16   11
 14500000.0 .757600000 14600000.0 .780480000 14700000.0 .8009275004025 3 16   12
 14800000.0 .818942500 14900000.0 .837701429 15000000.0 .8572042864025 3 16   13
 15100000.0 .876707143 15200000.0 .895960893 15300000.0 .9137200004025 3 16   14
 15400000.0 .931230000 15500000.0 .948740000 15600000.0 .9662500004025 3 16   15
 15700000.0 .983260583 15800000.0 .997274667 15900000.0 1.010789334025 3 16   16
 16000000.0 1.02430400 16100000.0 1.03781867 16200000.0 1.051333334025 3 16   17
 16300000.0 1.06484800 16400000.0 1.07836267 16500000.0 1.088679004025 3 16   18
 16600000.0 1.09579700 16700000.0 1.10291500 16800000.0 1.110033004025 3 16   19
 16900000.0 1.11715100 17000000.0 1.12426900 17100000.0 1.131387004025 3 16   20
 17200000.0 1.13850500 17300000.0 1.14562300 17400000.0 1.152741004025 3 16   21
 17500000.0 1.15859150 17600000.0 1.16317450 17700000.0 1.167757504025 3 16   22
 17800000.0 1.17234050 17900000.0 1.17692350 18000000.0 1.181506504025 3 16   23
 18100000.0 1.18608950 18200000.0 1.19067250 18300000.0 1.195255504025 3 16   24
 18400000.0 1.19983850 18500000.0 1.20193100 18600000.0 1.201533004025 3 16   25
 18700000.0 1.20113500 18800000.0 1.20073700 18900000.0 1.200339004025 3 16   26
 19000000.0 1.19994100 19100000.0 1.19954300 19200000.0 1.199145004025 3 16   27
 19300000.0 1.19874700 19400000.0 1.19834900 19500000.0 1.197951004025 3 16   28
 19600000.0 1.19755300 19700000.0 1.19715500 19800000.0 1.196757004025 3 16   29
 19900000.0 1.19635900 20000000.0 0.0                             4025 3 16   30
                                                                  4025 3  099999
                                                                  4025 0  0    0
 4.00900E+4 8.91324E+1          0          0          0          1402533 16    1
 0.000000+0 0.000000+0          0         16          0          1402533 16    2
 0.000000+0 0.000000+0          1          5        253         22402533 16    3
 1.000000-5 1.210000+7 1.240000+7 1.260000+7 1.280000+7 1.300000+7402533 16    4
 1.320000+7 1.340000+7 1.360000+7 1.380000+7 1.400000+7 1.420000+7402533 16    5
 1.440000+7 1.460000+7 1.480000+7 1.500000+7 1.550000+7 1.600000+7402533 16    6
 1.700000+7 1.800000+7 1.900000+7 2.000000+7 0.000000+0 0.000000+0402533 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0402533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0402533 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0402533 16   10
 0.000000+0 1.159000-2 4.915000-3 2.591000-3 2.281000-3 3.480000-3402533 16   11
 6.788000-4 1.381000-4 1.958000-4 5.803000-5 5.767000-5 2.137000-4402533 16   12
 6.431000-5 5.829000-5 5.247000-5 1.721000-3 1.796000-3 1.230000-3402533 16   13
 1.225000-3 1.489000-3 1.297000-3 4.873000-3 2.573000-3 2.266000-3402533 16   14
 1.893000-3 6.741000-4 1.371000-4 1.066000-4 5.763000-5 5.727000-5402533 16   15
 1.392000-4 6.387000-5 5.789000-5 5.211000-5 1.130000-3 1.177000-3402533 16   16
 7.987000-4 7.954000-4 9.667000-4 7.058000-4 8.925000-3 4.716000-3402533 16   17
 0.000000+0 1.403000-3 2.854000-4 0.000000+0 1.199000-4 1.192000-4402533 16   18
 1.055000-4 1.329000-4 1.205000-4 1.085000-4 8.939000-4 9.207000-4402533 16   19
 5.961000-4 5.941000-4 7.214000-4 0.000000+0 6.922000-3 0.000000+0402533 16   20
 1.236000-3 2.513000-4 0.000000+0 1.056000-4 1.050000-4 9.288000-5402533 16   21
 1.171000-4 1.061000-4 9.551000-5 7.873000-4 8.108000-4 5.250000-4402533 16   22
 5.232000-4 6.353000-4 0.000000+0 2.527000-3 0.000000+0 0.000000+0402533 16   23
 1.010000-4 0.000000+0 0.000000+0 8.392000-5 0.000000+0 0.000000+0402533 16   24
 0.000000+0 6.644000-4 6.964000-4 4.856000-4 4.834000-4 5.878000-4402533 16   25
 6.691000-4 1.279000-3 1.354000-4 3.023000-5 5.849000-5 3.123000-5402533 16   26
 5.003000-5 5.378000-5 5.446000-5 5.173000-5 2.342000-4 2.412000-4402533 16   27
 1.562000-4 1.557000-4 1.890000-4 0.000000+0 3.077000-4 8.119000-5402533 16   28
 7.922000-5 7.440000-5 7.199000-5 5.936000-5 7.322000-5 7.150000-5402533 16   29
 5.648000-5 5.854000-5 3.739000-5 3.784000-5 4.510000-5 0.000000+0402533 16   30
 1.171000-4 4.644000-5 4.378000-5 4.618000-5 3.271000-5 4.260000-5402533 16   31
 4.095000-5 3.739000-5 3.920000-5 2.733000-5 2.721000-5 3.308000-5402533 16   32
 3.766000-5 9.605000-5 4.489000-5 4.244000-5 3.238000-5 4.414000-5402533 16   33
 3.926000-5 2.002000-5 2.062000-5 1.335000-5 1.331000-5 1.616000-5402533 16   34
 0.000000+0 1.114000-4 4.042000-5 3.070000-5 4.347000-5 3.718000-5402533 16   35
 1.990000-5 2.050000-5 2.254000-5 2.203000-5 2.717000-5 1.259000-5402533 16   36
 8.344000-5 2.932000-5 3.968000-5 3.557000-5 5.268000-5 5.499000-5402533 16   37
 3.700000-5 3.711000-5 4.471000-5 3.129000-5 6.920000-5 3.915000-5402533 16   38
 3.852000-5 2.559000-5 2.649000-5 1.696000-5 1.712000-5 2.046000-5402533 16   39
 0.000000+0 1.115000-4 4.736000-5 2.011000-5 2.072000-5 1.341000-5402533 16   40
 1.337000-5 1.623000-5 0.000000+0 1.118000-4 2.243000-5 2.328000-5402533 16   41
 1.482000-5 1.505000-5 1.786000-5 0.000000+0 6.550000-4 4.446000-4402533 16   42
 2.989000-4 2.997000-4 3.613000-4 2.477000-4 6.887000-4 3.120000-4402533 16   43
 3.128000-4 3.770000-4 2.596000-4 4.461000-4 3.007000-4 2.902000-4402533 16   44
 3.123000-4 4.453000-4 2.888000-4 3.121000-4 5.414000-4 2.681000-4402533 16   45
 6.335000-4                                                       402533 16   46
                                                                  402533  099999
                                                                  4025 0  0    0
                                                                     0 0  0    0
 4.10930E+4 9.21083E+1          0          0         34         104125 1451    1
 0.0        0.0                 0          0          0          64125 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20024125 1451    3
 3.00000E+2 0.0                 1          0        408         104125 1451    4
 41-Nb- 93 FEI/LANL   EVAL-Aug96 Zolotarev et al.,Chadwick et al. 4125 1451    5
                      DIST-Feb2004                                4125 1451    6
----IRDF-2002         MATERIAL 4125                               4125 1451    7
-----INCIDENT NEUTRON DATA                                        4125 1451    8
------ENDF-6 FORMAT                                               4125 1451    9
***************************************************************** 4125 1451   10
-----RUSSIAN DOSIMETRY FILE RRDF-98                 Rev.2         4125 1451   11
                    ----- MF=3 MT=16  -----                       4125 1451   12
                    ----- MF=3 MT=51  -----                       4125 1451   13
  For the IRDF-2002 file these two reactions were converted at    4125 1451   14
  IAEA/NDS.                                                       4125 1451   15
  The reaction MF/MT=3/16 was converted to MF/MT=10/16            4125 1451   16
  The reaction MF/MT=3/51 was converted to MF/MT=10/ 4            4125 1451   17
  The corresponding co-variance files were also converted         4125 1451   18
  The reaction MF/MT=33/16 was converted to MF/MT=40/16           4125 1451   19
  The reaction MF/MT=33/51 was converted to MF/MT=40/ 4           4125 1451   20
***************************************************************** 4125 1451   21
 41-NB-93  FEI        EVAL-Aug96 K.Zolotarev and G.Badikov        4125 1451   22
                      DIST-Aug96                                  4125 1451   23
---BROND-3            MATERIAL 4112                               4125 1451   24
----INCIDENT NEUTRON DATA                                         4125 1451   25
-----ENDF-6 FORMAT                                                4125 1451   26
AUTHORS OF EVALUATION: K.Zolotarev and S.Badikov                  4125 1451   27
***************************************************************** 4125 1451   28
  41-NB- 93 LANL,ANL  EVAL-DEC97 M.CHADWICK,P.YOUNG,D.L.SMITH     4125 1451   29
 Ch97,Ch99            DIST-AUG99 REV2-                 19990803   4125 1451   30
----ENDF/B-VI         MATERIAL 4125         REVISION 2            4125 1451   31
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4125 1451   32
DOSIMETRY                                                         4125 1451   33
******************************************************************4125 1451   34
****************************************************************  4125 1451   35
******** Start of (N,2N),(N,N') bibliographical component ******* 4125 1451   36
***************************************************************** 4125 1451   37
                                                                  4125 1451   38
                    ----- MF=3 MT=16  -----                       4125 1451   39
                                                                  4125 1451   40
    The  evaluation  Nb93(n,2n)Nb92m  excitation  function  from  4125 1451   41
9.20 MeV to 20 MeV  has been carried out within the framework of  4125 1451   42
generalized least squares method , rational function was used as  4125 1451   43
model function [1].The experimental data base covers the results  4125 1451   44
of measurements [2-37].                                           4125 1451   45
    Below  9.2 MeV  the evaluation  has been  carried out by      4125 1451   46
means of linear interpolation.  Experimental data [38-43] were    4125 1451   47
rejectected due to large discrepancy with the main bulk of the    4125 1451   48
experimental data.                                                4125 1451   49
    The evaluated  Nb93(n,2n)Nb92m  excitation function averaged  4125 1451   50
on  U-235  neutron fission spectrum [44] and  Cf-252 spontaneous  4125 1451   51
fission neutron spectrum [45] gives the next values :             4125 1451   52
                                                                  4125 1451   53
 ---------------------------------------------------------------  4125 1451   54
    TYPE OF SPECTRUM   I <CS>,MB (calc.) I   <CS>, MB (measured)  4125 1451   55
 ----------------------I-----------------I----------------------  4125 1451   56
                       I                 I                        4125 1451   57
 U-235 neutron fission I   0.4416        I  0.4796+-0.0293 [46]   4125 1451   58
                       I                 I                        4125 1451   59
 ----------------------I-----------------I----------------------  4125 1451   60
                       I                 I                        4125 1451   61
 CF-252 spont. fission I   0.7701        I  0.749 +- 0.038 [65]   4125 1451   62
                       I                 I                        4125 1451   63
                                                                  4125 1451   64
                                                                  4125 1451   65
                    ----- MF=3 MT=51  -----                       4125 1451   66
                                                                  4125 1451   67
    Evaluation  Nb93(n,n')Nb93m  excitation function from 30 keV  4125 1451   68
to  20 MeV  was performed  by  the  same method.  Evaluation  is  4125 1451   69
based on :                                                        4125 1451   70
from  170 keV to  680 keV on theoretical model calculations [47], 4125 1451   71
from  680 keV to  7.9 MeV on the  experimental  data  [48-51] ,   4125 1451   72
from 7.9 MeV to 20.0 MeV on theoretical model calculations [47]   4125 1451   73
and experimental data [52,53].  Below 170 keV the evaluation has  4125 1451   74
been carried out by means of linear interpolation.  Experimental  4125 1451   75
data [48] and [52] were renormalized , respectively , to the new  4125 1451   76
monitor cross-sections data  U235(n,f) [54] and  Nb93(n,2n)Nb92m  4125 1451   77
[55].                                                             4125 1451   78
Re-evaluated  experimental data  of M.Wagner e.a.  [49-50]  were  4125 1451   79
taken from ref. [56].                                             4125 1451   80
    The evaluated  Nb93(n,n')Nb93m  excitation function averaged  4125 1451   81
on  U-235  neutron fission spectrum [44] and  Cf-252 spontaneous  4125 1451   82
fission neutron spectrum [45] gives the next values :             4125 1451   83
                                                                  4125 1451   84
 ---------------------------------------------------------------  4125 1451   85
    TYPE OF SPECTRUM   I <CS>,MB (calc.) I   <CS>, MB (measured)  4125 1451   86
 ----------------------I-----------------I----------------------  4125 1451   87
                       I                 I  150.0 +- 13.0  [57]   4125 1451   88
 U-235 neutron fission I     143.47      I  147.0 +- 11.0  [58]   4125 1451   89
                       I                 I  146.2 +- 12.5  [59]   4125 1451   90
 ----------------------I-----------------I----------------------  4125 1451   91
                       I                 I  144.9 +-  4.8  [60]   4125 1451   92
 CF-252 spont. fission I     146.04      I  144.0 +-  5.0  [61]   4125 1451   93
                       I                 I  150.6 +-  3.6  [62]   4125 1451   94
                                                                  4125 1451   95
    The integal cross-section data [57 - 59], measured in  U-235  4125 1451   96
neutron fission spectrum, were renormalized to the  Nb93m  half-  4125 1451   97
life (16.1 +- 0.2) Year [63] , new values of  K X-rays branching  4125 1451   98
and  new monitor cross-section data.                              4125 1451   99
    The full description  of the cross sections data  evaluation  4125 1451  100
for the both reactions is given in [64].                          4125 1451  101
                                                                  4125 1451  102
References :                                                      4125 1451  103
 1. S.Badikov, K.Zolotarev  Proc. of NEANSC Specialist's. Meeting 4125 1451  104
    on Evaluation and Processing of Covariance Data, Oar Ridge ,  4125 1451  105
    USA, 1992, OECD, Paris, 1993, p.105                           4125 1451  106
 2. H.Vonach,H.Muenzer  J,OSA, v.96, p.120, Mar.1959              4125 1451  107
 3. H.A.Tewes e.a.  Report UCRL-6028-T, June 1960                 4125 1451  108
 4. R.J.Prestwood,B.P.Bayhurst  Phys.Rev., v.121, p.1438,Mar.1961 4125 1451  109
 5. V.L.Glagolev,P.A.Jampol'skij  J,JET, v.13, p.520, 1961        4125 1451  110
 6. D.G.Vallis  Report AWRE-O-76/66, Dec.1966                     4125 1451  111
 7. L.Husain e.a. Phys.Rev./C, v.1, p.1233, Apr.1970              4125 1451  112
12. A.Paulsen, R.Widera  Z.Physik, v.238, p.23, Sep.1970          4125 1451  113
13. M.Bormann e.a.  Progress Rep. EANDC(E)-127, p.38, Mar.1970    4125 1451  114
14. S.M.Qaim e.a.  Proc. of Conf.on Chemical Nuclear Data, Measur.4125 1451  115
    and Applicat., Univ.of Kent, Canterbury, 20-22 Sep.1971,p.121 4125 1451  116
15. D.R.Nethaway  Nucl.Phys./A, v.190, p.635, 1972                4125 1451  117
16. E.Holub,N.Cindro  J.of Phys./G, v.2, p.405, June 1976         4125 1451  118
17. D.R.Nethaway  J. of Inorg. and Nucl.Chem., v.40, p.1285, 1978 4125 1451  119
18. C.G.Hudson e.a.  J.Annals of Nucl.Energy, v.5, p.589, 1978    4125 1451  120
19. J.Laurec e.a.  Report CEA-R-5109, June 1981                   4125 1451  121
20. T.B.Ryves,P.Kolkowski  J.Phys.G, v.7, n.4, p.529, 1981        4125 1451  122
21. R.C.Harper,W.L.Alford  J,JP/G, v.8, p.153, Jan.1982           4125 1451  123
22. J.Csikai  Proc. of Int.Conf. Nuclear Data for Science  and    4125 1451  124
    Technology, Antverp., 6-10 Sept.1982, p.414                   4125 1451  125
23. A.Chiadli,G.Paic  Progress Report MOH-5, p.13, 1982           4125 1451  126
24. S.Daroczy e.a.  Conf.,83KIEV, v.3, p.191, Nov.1983            4125 1451  127
25. Y.Ikeda e.a  EXFOR 21945, 1984                                4125 1451  128
26. Lu Han-Lin e.a.  Chinese J.Nucl.Phys., v.6,n.1,p.76, Feb.1984 4125 1451  129
27. I.Garlea e.a.  J,RRP, v.29, p.421, 1984                       4125 1451  130
28. I.Garlea e.a.  Proc.of the 14-th Intern. Symp.on Nucl.Phys.,  4125 1451  131
    Gaussig,GDR,19-23 Nov.1984, ZFK-562, p.126, 1985              4125 1451  132
29. Y.S.Kim e.a.  J.of the Korean Nucl.Soc., v.18, n.2,p.92,1986  4125 1451  133
30. Y.Ikeda e.a.  Report  JAERI-1312, 1988                        4125 1451  134
31. K.Kobayashi,I.Kimura  Proc.of Int. Conf.on Nuclear Data for   4125 1451  135
    Science and Technology, Mito, Japan 30 May - 3 June 1988      4125 1451  136
32. R.Woelfle e.a. Appl.Radiat.and Isotopes, v.39, p.407, 1988    4125 1451  137
33. Lu Hanlin e.a.  Report INDC(CPR)-16, Aug.1989                 4125 1451  138
34. Wang Xiuyuan e.a.  EXFOR 30935, 1989                          4125 1451  139
35. D.C.Santry,R.D.Werner  Can.J.Phys., v.68, p.582, 1990         4125 1451  140
36. Y.Ikeda e.a. Progress Report INDC(JPN)-162/U, p.16, Aug.1992  4125 1451  141
37  D.L.Smith e.a. Proc.Int.Conf. Nuclear Data for Science and    4125 1451  142
    Technology, Julich, FRG, 13-17 May 1991. Springer Verlag,     4125 1451  143
    Berlin - Heidelberg, 1992, p.282-284                          4125 1451  144
38. D.R.Koehler,W.L.Alford  Report NP-11667, 1962                 4125 1451  145
39. F.Strohal e.a.  Nucl.Phys., v.30, p.49, Feb.1962              4125 1451  146
40. G.T.Western e.a.  Report AFWL-TR-65-216, p.2, June 1966       4125 1451  147
41. W.D.Lu e.a.  Phys.Rev.C, v.1, p.350, Jan.1970                 4125 1451  148
42. A.Mannan,S.M.Qaim  Phys.Rev./C, v.38, n.2, p.630, Aug.1988    4125 1451  149
43. S.I.Bhuiyan  EXFOR 30936, 1989                                4125 1451  150
44. L.W.Weston e.a. Evaluated Neutron Data for U-235, ENDF/B-VI   4125 1451  151
    Library, MAT=9228, MF=5, MT=18, eval.apr. 1989                4125 1451  152
45. W.Mannhart  IAEA-TECDOC-410, p.158, 1987                      4125 1451  153
46. K.Kobayashi, T.Kobayashi  Progress Report NEANDC(J)-155U,     4125 1451  154
    P.52, 1990                                                    4125 1451  155
47. B.Strohmaier  Ann. nucl. Energy, v.16, n.9, p.461, 1989       4125 1451  156
48. D.B.Gayther e.a. Rep. AERE-R-12612, MAY 1987                  4125 1451  157
49. M.Wagner e.a. J.Annals of Nucl.Energy, v.15, n.7, p.363, 1988 4125 1451  158
50. M.Wagner e.a. Proc.Int.Conf. Nucl.Data for Sci.Tec.,Mito,     4125 1451  159
    Japan,1988,p.1049                                             4125 1451  160
51. M.Wagner e.a. Measurement of the activation cross section for 4125 1451  161
    the reaction 93Nb(n,n')93mNb in the neutron energy range      4125 1451  162
    6 - 9 MeV. Progress Report 1991                               4125 1451  163
52. T.B.Ryves,P.Kolkowski  J. of Physics G, v.7, n.4, p.529, 1981 4125 1451  164
53. Y.Ikeda e.a. Progress Report INDC(JPN)-162/U, p.16, Aug.1992  4125 1451  165
54. L.W.Weston e.a. Evaluated Neutron Data for U-235, ENDF/B-VI   4125 1451  166
    Library, MAT=9228, MF=5, MT=18, eval.apr. 1989                4125 1451  167
55. M.Wagner e.a. Physics Data Nr.13-5, p.175, Karlsruhe 1990     4125 1451  168
56. M.Wagner e.a. Physics Data Nr.13-5, p.135, Karlsruhe 1990     4125 1451  169
57. K.Sakurai, I.Kondo  Nucl.Instr.and Meth., v.187, p.649, 1981  4125 1451  170
58. K.Kobayashi, I.Kimura  Rep. NEANDC(J)-61U, p.78, sep.1979     4125 1451  171
59. F.Hegedues  Proc. of the 1 st ASTM-EURATOM Symposium on Reac- 4125 1451  172
    tor Dosimetry, Petten 1975. EUR 5667e, Part 1, p.757, 1976    4125 1451  173
60. W.G.Alberts e.a. Proc. of the 6 th ASTM-EURATOM Symposium on  4125 1451  174
    Reactor Dosimetry, ASTM-STP-1OO1, p.223, 1989                 4125 1451  175
61. T.G.Williamson e.a. Proc. of the 6 th ASTM-EURATOM Symposium  4125 1451  176
    on Reactor Dosimetry, ASTM-STP-1OO1, p.229, 1989              4125 1451  177
62. J.G.Williams e.a. Proc.of the 6 th ASTM-EURATOM Symposium on  4125 1451  178
    Reactor Dosimetry, ASTM-STP-1OO1, p.235, 1989                 4125 1451  179
63. U.Schotzig,H.Schrader R.PTB-RA-16/2, 2 ed.,Braunschweig,1986  4125 1451  180
64. S.Badikov, K.Zolotarev  Proc.of the 8-th ASTM-EURATOM Sympos. 4125 1451  181
    on Reactor Dosimetry, Vail, Colorado, USA,29 Aug.-3 Sep. 1993 4125 1451  182
65. W.Mannhart Private communication, 1990                        4125 1451  183
******************************************************************4125 1451  184
********  End of (N,2N),(N,N') bibliographical component ******** 4125 1451  185
***************************************************************** 4125 1451  186
******************************************************************4125 1451  187
********     Start of (N,G) bibliographical component    ******** 4125 1451  188
***************************************************************** 4125 1451  189
                                                                  4125 1451  190
 ENDF/B-VI MOD 3 Evaluation, December 1997, M.B. Chadwick and     4125 1451  191
                 P.G. Young (LANL)                                4125 1451  192
                                                                  4125 1451  193
 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code     4125 1451  194
   in cooperation with ECN Petten.                                4125 1451  195
                                                                  4125 1451  196
  This evaluation provides a complete representation of the       4125 1451  197
nuclear data needed for transport, damage, heating, radioactivity,4125 1451  198
and shielding applications over the incident proton energy range  4125 1451  199
from 1 to 150 MeV.  The evaluation utilizes MF=6, MT=5 to         4125 1451  200
represent all reaction data.  Production cross sections and       4125 1451  201
emission spectra are given for neutrons, protons, deuterons,      4125 1451  202
tritons, alpha particles, gamma rays, and all residual nuclides   4125 1451  203
produced (A>5) in the reaction chains. To summarize, the ENDF     4125 1451  204
sections with non-zero data above are:                            4125 1451  205
                                                                  4125 1451  206
  MF=3 MT=  2  Integral of nuclear plus interference components   4125 1451  207
               of the elastic scattering cross section            4125 1451  208
                                                                  4125 1451  209
       MT=  5  Sum of binary (p,n') and (p,x) reactions           4125 1451  210
                                                                  4125 1451  211
  MF=6 MT=  2  Elastic (p,p) angular distributions given as       4125 1451  212
               ratios of the differential nuclear-plus-           4125 1451  213
               interference to the integrated value.              4125 1451  214
                                                                  4125 1451  215
       MT=  5  Production cross sections and energy-angle         4125 1451  216
               distributions for emission neutrons, protons,      4125 1451  217
               deuterons, and alphas; and angle-integrated        4125 1451  218
               spectra for gamma rays and residual nuclei that    4125 1451  219
               are stable against particle emission               4125 1451  220
                                                                  4125 1451  221
  The evaluation is based on nuclear model calculations that have 4125 1451  222
been benchmarked to experimental data, especially for n +93Nb and 4125 1451  223
n +93Nb reactions [Ch98]. We use the GNASH code system [Yo92],    4125 1451  224
which utilizes Hauser-Feshbach statistical, preequilibrium and    4125 1451  225
direct-reaction theories. Spherical optical model calculations are4125 1451  226
used to obtain particle transmission coefficients for the Hauser- 4125 1451  227
Feshbach calculations, as well as for the elastic proton angular  4125 1451  228
distributions.                                                    4125 1451  229
  Cross sections and spectra for producing individual residual    4125 1451  230
nuclei are included for reactions. The energy-angle-correlations  4125 1451  231
for all outgoing particles are based on Kalbach systematics       4125 1451  232
[Ka88].                                                           4125 1451  233
  A model was developed to calculate the energy distributions of  4125 1451  234
all recoil nuclei in the GNASH calculations [Ch96a]. The recoil   4125 1451  235
energy distributions are represented in the laboratory system in  4125 1451  236
MT=5, MF=6, and are given as isotropic in the lab system. All     4125 1451  237
other data in MT=5,MF=6 are given in the center-of-mass system.   4125 1451  238
This method of representation utilizes the LCT=3 option approved  4125 1451  239
at the November, 1996, CSEWG meeting.                             4125 1451  240
  Preequilibrium corrections were performed in the course of the  4125 1451  241
GNASH calculations using the exciton model of Kalbach [Ka77,      4125 1451  242
Ka85], validated by comparison with calculations using Feshbach,  4125 1451  243
Kerman, Koonin (FKK) theory [Ch93].  Discrete level data from     4125 1451  244
nuclear data sheets were matched to continuum level densities     4125 1451  245
using the formulation of Ignatyuk et al. [Ig75] and pairing and   4125 1451  246
shell parameters from the Cook [Co67] analysis. Neutron and       4125 1451  247
charged- particle transmission coefficients were obtained from the4125 1451  248
optical potentials, as discussed below.  Gamma-ray transmission   4125 1451  249
coefficients were calculated using the Kopecky-Uhl model [Ko90].  4125 1451  250
                                                                  4125 1451  251
SPECIFIC INFORMATION CONCERNING THE 93Nb EVALUATION               4125 1451  252
                                                                  4125 1451  253
The total neutron cross section was obtained from the Finlay[Fi93]4125 1451  254
measurements.                                                     4125 1451  255
                                                                  4125 1451  256
The following optical potentials were used in the GNASH           4125 1451  257
calculations.  For incident neutrons, the Wilmore-Hodgson         4125 1451  258
potential was used below 15 MeV, and the Madland potential [Ma88] 4125 1451  259
was used at higher energies. For incident protons, the            4125 1451  260
Becchetti-Greenlees [Be69] potential was used up to 50 MeV, above 4125 1451  261
which the Madland potential [Ma88] was used. In both cases, the   4125 1451  262
matching energy between the potentials was chosen to result in    4125 1451  263
continuity of the reaction cross section. For protons at 50 MeV   4125 1451  264
the reaction cross section (and transmission coefficients) was    4125 1451  265
renormalized slightly to smoothen the transition between the      4125 1451  266
potentials. The Perey [Pe63] potential was used for indident      4125 1451  267
deuterons. For tritons, the Becchetti-Greenlees [Be71] was used   4125 1451  268
up to 80 MeV, above which the Watanabe potential was used. The    4125 1451  269
Moyen (McFadden Satchler) [Mc66] potential was used for alpha     4125 1451  270
particles over the whole energy range.                            4125 1451  271
                                                                  4125 1451  272
Direct inelastic scattering to low-lying states in Nb93 was       4125 1451  273
determined as follows. Coherent excitation of 2+ and 3-           4125 1451  274
vibrations were assumed to be fragmented over Nb93 states, after  4125 1451  275
coupling these excitations with the 4.5+ core. The magnitudes of  4125 1451  276
the deformation lengths of 2+ and 3- excitations was obtained by  4125 1451  277
fitting values of 34 and 46 mb respectively at 14 MeV, obtained   4125 1451  278
in ref. [Ch93] and accounting for measurements well. This         4125 1451  279
strength was then fragmented over Nb states.  For the 3-          4125 1451  280
excitation, the 7 states are in the "continuum" region of the     4125 1451  281
GNASH calculation at approximately 2.5 MeV, with spins 1.5-,2.5-, 4125 1451  282
..,7.5-.  For the 2+, the 5 states (2.5+,3.5+,...6.5+) near 1 MeV 4125 1451  283
were assumed to be those whose inelastic cross section in the     4125 1451  284
existing ENDF <20 MeV file are significant (note that the ENDF    4125 1451  285
file below 20 MeV appears to incorporate inelastic information    4125 1451  286
only up to 5 MeV for many states, after which a value of zero at  4125 1451  287
20 MeV was inserted).                                             4125 1451  288
                                                                  4125 1451  289
Experimental data is used to benchmark the calculations. For      4125 1451  290
incident neutrons, experimental neutron emission spectra data     4125 1451  291
exist at 20 and 26 MeV by Marcinkowski [Ma83]. For incident       4125 1451  292
protons, spectra data exist at 14 and 26 MeV by Watanabe et       4125 1451  293
al. [Wa97], and at 65 MeV by Sakai et al [Sa80]. Our evaluation   4125 1451  294
agrees reasonably well with these measurements.                   4125 1451  295
                                                                  4125 1451  296
****************************************************************  4125 1451  297
                                                                  4125 1451  298
REFERENCES                                                        4125 1451  299
                                                                  4125 1451  300
[Be69]  F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182,   4125 1451  301
  1190 (1969)                                                     4125 1451  302
[Be71]  F.D. Becchetti, Jr., and G.W. Greenlees in Polarization   4125 1451  303
  Phenomena in Nuclear Reactions (Ed: H.H. Barschall and W.       4125 1451  304
  Haeberli, The University of Wisconsin Press, 1971) p.682        4125 1451  305
[Ch93]  M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 4125 1451  306
[Ch96a] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J.      4125 1451  307
  Koning, "High-Energy Nuclear Data Libraries for Accelerator-    4125 1451  308
  Driven Technologies:  Calculational Method for Heavy Recoils,"  4125 1451  309
  Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation     4125 1451  310
  Technology and Applications, Kalmar, Sweden, 3-7 June 1996.     4125 1451  311
[Ch98]  M.B. Chadwick and P.G. Young, "Model Calculations of      4125 1451  312
  n,p + 93Nb" in APT PROGRESS REPORT: 1 November 1997 - 1 January 4125 1451  313
  1998, internal Los Alamos National Laboratory memo              4125 1451  314
  January 1998 from R.E. MacFarlane to L. Waters.                 4125 1451  315
[Ch99]  M.B. Chadwick, P.G. Young, G.M. Hale et al., Los Alamos   4125 1451  316
  National Laboratory report, LA-UR-99-1222 (1999)                4125 1451  317
[Co67]  J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J.    4125 1451  318
  Phys. 20, 477 (1967)                                            4125 1451  319
[Fi93]  R. W. Finlay, W. P. Abfalterer, G. Fink et al., Phys. Rev 4125 1451  320
  C 47, 237 (1993)                                                4125 1451  321
[Ig75]  A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J.    4125 1451  322
   Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485     4125 1451  323
   (1975)                                                         4125 1451  324
[Ka77]  C. Kalbach, Z.Phys.A  283, 401 (1977)                     4125 1451  325
[Ka85]  C. Kalbach, Los Alamos National Laboratory report         4125 1451  326
  LA-10248-MS (1985)                                              4125 1451  327
[Ka88]  C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also          4125 1451  328
  C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981)            4125 1451  329
[Ko90]  J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990)         4125 1451  330
[Lo74]  J.M. Lohr and W. Haeberli, Nucl.Phys. A232, 381 (1974)    4125 1451  331
[Ma88]  D.G. Madland, "Recent Results in the Development of a     4125 1451  332
  Global Medium-Energy Nucleon-Nucleus Optical-Model Potential,"  4125 1451  333
  Proc. OECD/NEANDC Specialist's Mtg. on Preequilibrium Nuclear   4125 1451  334
  Reactions, Semmering, Austria, 10-12 Feb. 1988, NEANDC-245 'U'  4125 1451  335
  (1988).                                                         4125 1451  336
[Ma83]  A. Marcinkowski, R.W. Finlay, G. Randers-Pehrson et al.,  4125 1451  337
  Nucl.Phys. A402, 220 (1983)                                     4125 1451  338
[Mc66]  L. McFadden and G. R. Satchler, Nucl. Phys. 84, 177       4125 1451  339
  (1966).                                                         4125 1451  340
[Pe63]  C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963)      4125 1451  341
[Sa80]  H. Sakai, K. Hosono, N. Matsuoka et al., Nucl.Phys. A344, 4125 1451  342
  41 (1980)                                                       4125 1451  343
[We96]  H.P. Wellisch and D. Axen, Phys.Rev. C 54, 1329(1996)     4125 1451  344
[Wa97]  Y. Watanabe, S. Yoshioka, M. Harada et al, Nuclear Data   4125 1451  345
  for Science and Technology, Proc. Conf. Trieste, May, 1997,     4125 1451  346
  G. Reffo, Ed. (Editrice Compositori, 1997) p.580                4125 1451  347
[Wi64]  D. Wilmore and P.E. Hodgson, Nucl.Phys. 55, 673 (1964)    4125 1451  348
[Yo92]  P.G. Young, E.D. Arthur, and M.B. Chadwick, report        4125 1451  349
  LA-12343-MS (1992)                                              4125 1451  350
                                                                  4125 1451  351
***************************************************************** 4125 1451  352
                                                                  4125 1451  353
 ENDF/B-VI MOD 2 Revision, August 1991, NNDC                      4125 1451  354
                                                                  4125 1451  355
 Only the section MOD numbers have been corrected in the          4125 1451  356
 directory.                                                       4125 1451  357
                                                                  4125 1451  358
***************************************************************** 4125 1451  359
                                                                  4125 1451  360
 ENDF/B-VI MOD 1 Evaluation, March 1990, A.B. Smith, D.L. Smith   4125 1451  361
                 L.P. Geraldo (ANL), and R. Howerton (LLNL)       4125 1451  362
                                                                  4125 1451  363
 Original evaluation fully documented in Smith et al. [1]         4125 1451  364
                                                                  4125 1451  365
 ---------------------------------------------------------------- 4125 1451  366
REFERENCES                                                        4125 1451  367
                                                                  4125 1451  368
[1.] A.B. Smith, D.L. Smith and R.J. Howerton, Argonne report     4125 1451  369
     ANL/NDM-88 (1985)                                            4125 1451  370
[2.] D.L. Smith and L.P. Geraldo, Argonne report ANL/NDM-117      4125 1451  371
     (1990)                                                       4125 1451  372
                                                                  4125 1451  373
******************************************************************4125 1451  374
********      End of (N,G) bibliographical component     ******** 4125 1451  375
***************************************************************** 4125 1451  376
 The Q values and threshold energies were updated prior to pro-   4125 1451  377
 cessing through the codes to comply with the values obtained     4125 1451  378
 using the NNDC calculation program which is based on the 1995    4125 1451  379
 Update to the Atomic mass Evaluation.                            4125 1451  380
                                                                  4125 1451  381
 File 2 taken from ENDF/B-VI                                      4125 1451  382
 ************************ C O N T E N T S *********************** 4125 1451  383
                                                                  4125 1451  384
 ***************** Program LINEAR (VERSION 2002-1) ***************4125 1451  385
 For All Data Greater than 1.0000E-10 barns in Absolute Value     4125 1451  386
 Data Linearized to Within an Accuracy of .100000000 per-cent     4125 1451  387
 ***************** Program RECENT (VERSION 2002-1) ***************4125 1451  388
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4125 1451  389
 Data Linearized to within an Accuracy of .100000000 per-cent     4125 1451  390
 ***************** Program SIGMA1 (VERSION 2002-1) ***************4125 1451  391
 Data Doppler Broadened to 300.000000 Kelvin                      4125 1451  392
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4125 1451  393
 Data Linearized to Within an Accuracy pf .100000000 per-cent     4125 1451  394
 ***************** Program FIXUP (Version 2002-1) ****************4125 1451  395
 Corrected ZA/AWR in All Sections-----------------------------Yes 4125 1451  396
 Corrected Thresholds-----------------------------------------Yes 4125 1451  397
 Extended Cross Sections to 20 MeV----------------------------No  4125 1451  398
 Allow Cross Section Deletion---------------------------------No  4125 1451  399
 Allow Cross Section Reconstruction---------------------------No  4125 1451  400
 Make All Cross Sections Non-Negative-------------------------Yes 4125 1451  401
 Delete Energies Not in Ascending Order-----------------------Yes 4125 1451  402
 Deleted Duplicate Points-------------------------------------Yes 4125 1451  403
 Check for Ascending MAT/MF/MT Order--------------------------Yes 4125 1451  404
 Check for Legal MF/MT Numbers--------------------------------Yes 4125 1451  405
 Allow Creation of Missing Sections---------------------------No  4125 1451  406
 Allow Insertion of Energy Points-----------------------------No  4125 1451  407
 Create Uniform Energy Grid-----------------------------------No  4125 1451  408
 Delete Section if Cross Section =0 at All Energies-----------Yes 4125 1451  409
 ***************** Program GROUPIE (VERSION 2002-1) **************4125 1451  410
 Unshielded Group Averages Using  640 Groups                      4125 1451  411
 Weighting Spectrum: Flat (Constant) Spectrum                     4125 1451  412
                                1        451        422          14125 1451  413
                                2        151          4          14125 1451  414
                                3        102        217          14125 1451  415
                                8          4          2          14125 1451  416
                                8         16          2          14125 1451  417
                               10          4         90          14125 1451  418
                               10         16         41          14125 1451  419
                               33        102          9          14125 1451  420
                               40          4        104          14125 1451  421
                               40         16         39          14125 1451  422
                                                                  4125 1  099999
                                                                  4125 0  0    0
 4.10930E+4 9.21083E+1          0          0          1          04125 2151    1
 4.10930E+4 1.00000E+0          0          0          1          04125 2151    2
 1.00000E-5 7.35000E+3          0          0          0          04125 2151    3
 4.50000E+0 6.90000E-1          0          0          0          04125 2151    4
                                                                  4125 2  099999
                                                                  4125 0  0    0
 4.10930E+4 9.21083E+1          0          0          0          04125 3102    1
 7.22747E+6 7.22747E+6          0          0          1        6414125 3102    2
        641          1                                            4125 3102    3
 .000100000 18.0213007 .000105000 17.6011498 .000110000 17.20200384125 3102    4
 .000115000 16.8342057 .000120000 16.4042406 .000127500 15.92720694125 3102    5
 .000135000 15.4913843 .000142500 15.0908610 .000150000 14.65737964125 3102    6
 .000160000 14.2058190 .000170000 13.7949650 .000180000 13.41782814125 3102    7
 .000190000 13.0669303 .000200000 12.7465657 .000210000 12.44515734125 3102    8
 .000220000 12.1651963 .000230000 11.9050847 .000240000 11.59977434125 3102    9
 .000255000 11.2642942 .000270000 11.0054074 .000280000 10.71720284125 3102   10
 .000300000 10.3657565 .000320000 10.0475333 .000340000 9.756094094125 3102   11
 .000360000 9.48766816 .000380000 9.24263675 .000400000 8.987176444125 3102   12
 .000425000 8.72576587 .000450000 8.48693672 .000475000 8.267962614125 3102   13
 .000500000 8.06202911 .000525000 7.87383007 .000550000 7.696048704125 3102   14
 .000575000 7.53070746 .000600000 7.36124432 .000630000 7.186911624125 3102   15
 .000660000 7.02739729 .000690000 6.87437954 .000720000 6.711564314125 3102   16
 .000760000 6.53699045 .000800000 6.37490446 .000840000 6.226363634125 3102   17
 .000880000 6.08518481 .000920000 5.95576328 .000960000 5.831819854125 3102   18
 .001000000 5.70335266 .001050000 5.56924720 .001100000 5.443531344125 3102   19
 .001150000 5.32768145 .001200000 5.19101925 .001275000 5.040835304125 3102   20
 .001350000 4.90352207 .001425000 4.77537192 .001500000 4.639231264125 3102   21
 .001600000 4.49688317 .001700000 4.36693655 .001800000 4.246754304125 3102   22
 .001900000 4.13696432 .002000000 4.03517330 .002100000 3.939658444125 3102   23
 .002200000 3.85218040 .002300000 3.76853368 .002400000 3.673114994125 3102   24
 .002550000 3.56708007 .002700000 3.48413693 .002800000 3.394028254125 3102   25
 .003000000 3.28311047 .003200000 3.18218089 .003400000 3.089889654125 3102   26
 .003600000 3.00571857 .003800000 2.92800045 .004000000 2.846995734125 3102   27
 .004250000 2.76475415 .004500000 2.68968605 .004750000 2.619526324125 3102   28
 .005000000 2.55514441 .005250000 2.49546942 .005500000 2.439062994125 3102   29
 .005750000 2.38736888 .006000000 2.33308297 .006300000 2.278836274125 3102   30
 .006600000 2.22751075 .006900000 2.17992067 .007200000 2.128184914125 3102   31
 .007600000 2.07287015 .008000000 2.02229362 .008400000 1.974836684125 3102   32
 .008800000 1.93068724 .009200000 1.88965925 .009600000 1.850618324125 3102   33
 .010000000 1.81018797 .010500000 1.76743310 .011000000 1.728284414125 3102   34
 .011500000 1.69092729 .012000000 1.64810317 .012750000 1.600693434125 3102   35
 .013500000 1.55678814 .014250000 1.51653646 .015000000 1.473662134125 3102   36
 .016000001 1.42869772 .017000001 1.38751152 .017999999 1.349987664125 3102   37
 .018999999 1.31541292 .020000000 1.28292398 .021000000 1.253192614125 3102   38
 .022000000 1.22518032 .023000000 1.19908065 .024000000 1.168416244125 3102   39
 .025500000 1.13534352 .027000001 1.10913958 .028000001 1.080676714125 3102   40
 .029999999 1.04563566 .032000002 1.01370832 .034000002 .9845640514125 3102   41
 .035999998 .957974892 .037999999 .933469317 .039999999 .9079185714125 3102   42
 .042500000 .882001933 .045000002 .858314863 .047499999 .8362348154125 3102   43
 .050000001 .815903693 .052499998 .797076973 .055000000 .7792451944125 3102   44
 .057500001 .762920918 .059999999 .745757234 .063000001 .7285945024125 3102   45
 .066000000 .712422526 .068999998 .697360082 .071999997 .6810306544125 3102   46
 .075999998 .663545193 .079999998 .647586836 .083999999 .6326033124125 3102   47
 .088000000 .618689959 .092000000 .605799476 .096000001 .5934841284125 3102   48
 .100000001 .580740692 .104999997 .567238550 .109999999 .5548929024125 3102   49
 .115000002 .543099907 .119999997 .529595519 .127499998 .5146728974125 3102   50
 .135000005 .500837179 .142499998 .488141351 .150000006 .4746142334125 3102   51
 .159999996 .460419968 .170000002 .447512045 .180000007 .4358671434125 3102   52
 .189999998 .424682446 .200000003 .414537148 .209999993 .4051062834125 3102   53
 .219999999 .396226892 .230000004 .388071824 .239999995 .3784338824125 3102   54
 .254999995 .367847380 .270000011 .359748630 .280000001 .3506513334125 3102   55
 .300000012 .339586358 .319999993 .329572955 .340000004 .3204548804125 3102   56
 .360000014 .312085870 .379999995 .304512822 .400000006 .2963389924125 3102   57
 .425000012 .288129965 .449999988 .280647711 .474999994 .2736699674125 3102   58
 .500000000 .267249196 .524999976 .261324591 .550000012 .2557032224125 3102   59
 .574999988 .250569355 .600000024 .245164713 .629999995 .2397563244125 3102   60
 .660000026 .234629738 .689999998 .229956081 .720000029 .2249389214125 3102   61
 .759999990 .219377641 .800000012 .214412077 .839999974 .2095743734125 3102   62
 .879999995 .205287449 .920000017 .201117331 .959999979 .1972194084125 3102   63
 1.00000000 .193144171 1.04999995 .188952517 1.10000002 .1849860024125 3102   64
 1.14999998 .181411664 1.20000005 .177069478 1.27499998 .1722936074125 3102   65
 1.35000002 .168067132 1.42499995 .163992345 1.50000000 .1598027644125 3102   66
 1.60000002 .155279789 1.70000005 .151227126 1.79999995 .1473994314125 3102   67
 1.89999998 .143982571 2.00000000 .140708632 2.09999990 .1377903334125 3102   68
 2.20000005 .134930277 2.29999995 .132383342 2.40000010 .1293041244125 3102   69
 2.54999995 .125954380 2.70000005 .123359271 2.79999995 .1205590374125 3102   70
 3.00000000 .117003541 3.20000005 .113818356 3.40000010 .1109472904125 3102   71
 3.59999990 .108223278 3.79999995 .105805012 4.00000000 .1031868124125 3102   72
 4.25000000 .100605679 4.50000000 .098236392 4.75000000 .0960118974125 3102   73
 5.00000000 .093988893 5.25000000 .092041920 5.50000000 .0902770754125 3102   74
 5.75000000 .088613386 6.00000000 .086909289 6.30000019 .0851493054125 3102   75
 6.59999990 .083560185 6.90000010 .082063272 7.19999981 .0803861634125 3102   76
 7.59999990 .078663891 8.00000000 .077001855 8.39999962 .0755136994125 3102   77
 8.80000019 .074118084 9.19999981 .072831750 9.60000038 .0715604124125 3102   78
 10.0000000 .070273917 10.5000000 .068923387 11.0000000 .0677183804125 3102   79
 11.5000000 .066530440 12.0000000 .065212677 12.7500000 .0637066964125 3102   80
 13.5000000 .062376173 14.2500000 .061106755 15.0000000 .0598156094125 3102   81
 16.0000000 .058434376 17.0000000 .057233258 18.0000000 .0561099024125 3102   82
 19.0000000 .055122657 20.0000000 .054279032 21.0000000 .0534859204125 3102   83
 22.0000000 .052806123 23.0000000 .052221292 24.0000000 .0516809544125 3102   84
 25.5000000 .051321727 27.0000000 .051340932 28.0000000 .0521454644125 3102   85
 30.0000000 .056070388 32.0000000 .075305021 34.0000000 2.145136594125 3102   86
 36.0000000 1.09955184 38.0000000 .084352271 40.0000000 1.343405374125 3102   87
 42.5000000 .413498725 45.0000000 .054923719 47.5000000 .0464178864125 3102   88
 50.0000000 .043601210 52.5000000 .042150748 55.0000000 .0412323614125 3102   89
 57.5000000 .040589832 60.0000000 .040061649 63.0000000 .0396397084125 3102   90
 66.0000000 .039357775 69.0000000 .039188537 72.0000000 .0391362604125 3102   91
 76.0000000 .039334796 80.0000000 .040032723 84.0000000 .0421793534125 3102   92
 88.0000000 .054697646 92.0000000 1.90564800 96.0000000 .0679057414125 3102   93
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 14900000.0 .456363000 15000000.0 .455369400 15100000.0 .454375800412510 16   24
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 20000000.0 0.0                                                   412510 16   41
                                                                  412510  099999
                                                                  4125 0  0    0
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 0.000000+0 0.000000+0          0        102          0          1412533102    2
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 1.000000-5 1.000000-2 1.000000+5 1.440000-2 1.000000+6 2.690000-2412533102    4
 1.200000+6 4.380000-2 1.400000+6 5.490000-2 1.600000+6 6.200000-2412533102    5
 1.800000+6 5.460000-2 2.000000+6 6.980000-2 2.500000+6 8.610000-2412533102    6
 3.000000+6 9.340000-2 4.000000+6 9.880000-2 5.000000+6 9.700000-2412533102    7
 6.000000+6 9.850000-2 8.000000+6 1.170000-1 1.000000+7 2.380000-1412533102    8
 1.500000+7 4.010000-1 2.000000+7 0.000000+0                      412533102    9
                                                                  412533  099999
                                                                  4125 0  0    0
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 1.190000+7 1.291000+7 1.392000+7 1.493000+7 1.595000+7 1.696000+7412540  4    9
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 1.733040-4 5.996550-5 5.103040-5 1.537080-4 2.570930-4 3.252750-4412540  4   18
 4.301880-4 6.094740-4 8.649130-4 1.238930-3 1.849700-3 2.245100-3412540  4   19
 1.994000-3 1.491610-3 1.155480-3 1.083730-3 1.239220-3 1.566990-3412540  4   20
 2.029290-3 2.603240-3 3.276500-3 6.639730-3 2.160160-3 8.345460-4412540  4   21
 8.651430-4 1.122380-3 1.110790-3 7.625850-4 1.679710-4-3.139040-4412540  4   22
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 2.269550-3 1.878770-3 1.441630-3 1.242290-3 1.275590-3 1.471790-3412540  4   25
 1.775120-3 2.154770-3 2.594280-3 3.085800-3 4.299820-3 2.742730-3412540  4   26
 1.180930-3 1.280130-4-3.168090-4-2.543180-4 7.409000-5 3.345940-4412540  4   27
 3.825920-4 3.142290-4 1.609680-4 2.449690-5-3.732750-7 1.189920-4412540  4   28
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 1.701720-3 2.038410-3 2.416280-3 2.830230-3 3.739540-3 2.931830-3412540  4   31
 1.975360-3 9.708180-4 2.607860-4-1.289430-4-1.991930-4-1.253310-4412540  4   32
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 4.943660-4 6.188340-4 8.343450-4 1.445800-3 2.255780-3 2.340310-3412540  4   34
 1.812270-3 1.393220-3 1.288600-3 1.406360-3 1.643830-3 1.941020-3412540  4   35
 2.271680-3 2.624370-3 2.995240-3 4.189860-3 4.024500-3 3.001730-3412540  4   36
 1.587020-3 1.163030-4-7.682270-4-9.377610-4-7.640760-4-3.258930-4412540  4   37
 1.361950-4 4.330750-4 4.873220-4 4.737090-4 5.292500-4 6.730000-4412540  4   38
 9.466770-4 1.469850-3 2.166400-3 2.392460-3 2.003120-3 1.541370-3412540  4   39
 1.319370-3 1.343650-3 1.544520-3 1.863190-3 2.266260-3 2.735490-3412540  4   40
 3.261940-3 4.832140-3 4.170460-3 2.692670-3 7.597480-4-6.585320-4412540  4   41
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 5.269830-4 4.840870-4 6.322520-4 9.308430-4 1.273820-3 1.747660-3412540  4   43
 2.124950-3 1.958180-3 1.500440-3 1.156890-3 1.057590-3 1.184700-3412540  4   44
 1.489730-3 1.935410-3 2.497770-3 3.163020-3 4.224790-3 3.275700-3412540  4   45
 1.671830-3 2.421390-4-4.249880-4-5.514110-4-2.532550-4 2.647080-4412540  4   46
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 6.754560-4 7.348610-4 9.717540-4 1.354640-3 1.861410-3 2.478470-3412540  4   49
 3.208690-3 2.497910-3 1.568480-3 8.938470-4 5.088300-4 2.969030-4412540  4   50
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 3.943180-4 5.024480-4 6.618280-4 8.588960-4 8.344860-4 6.329920-4412540  4   52
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 8.313390-5 2.047000-4 2.735460-4 2.799000-4 2.281380-4 1.243990-4412540  4   57
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 1.713330-4-1.194240-4-5.940800-4-1.236840-3 3.024700-3 1.979160-3412540  4   65
 6.198180-4-5.468580-4-8.162870-4-4.210970-4-7.927620-5-4.459820-5412540  4   66
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 2.023790-5 6.288820-5-5.324670-5-1.128010-4 1.700120-5-1.352280-5412540  4   70
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 3.687750-4 2.173250-4 1.617690-4 1.801080-4 1.731640-4 1.128680-4412540  4   73
 1.272130-4 1.622410-4 1.361040-4 8.193220-5 4.170310-5 3.197990-5412540  4   74
 5.464590-5 1.071850-4 1.868000-4 2.913430-4 1.498880-3 1.563970-3412540  4   75
 1.101200-3 5.840080-4 2.460810-4 3.079820-4 6.610820-4 5.719550-4412540  4   76
 1.665180-4 8.307930-5 1.960700-4 2.782050-4 2.985300-4 2.911380-4412540  4   77
 2.866040-4 3.023290-4 3.471610-4 4.254630-4 2.001620-3 1.691700-3412540  4   78
 1.072030-3 4.653810-4 3.758190-4 1.095520-3 1.243450-3 2.902860-4412540  4   79
-2.099260-4 2.380500-5 4.151040-4 6.759070-4 7.690700-4 7.312200-4412540  4   80
 6.021400-4 4.096400-4 1.714420-4 1.771930-3 1.478280-3 9.917070-4412540  4   81
 7.028490-4 1.145510-3 1.437010-3 6.735220-4 3.739970-5 1.022170-4412540  4   82
 4.508550-4 7.565960-4 9.219840-4 9.481760-4 8.597130-4 6.784300-4412540  4   83
 4.202460-4 1.724780-3 1.753300-3 1.451070-3 1.021880-3 1.000000-3412540  4   84
 1.083020-3 8.507040-4 5.878650-4 4.902150-4 5.328860-4 6.521400-4412540  4   85
 8.050520-4 9.709980-4 1.140600-3 1.310290-3 2.544470-3 2.659500-3412540  4   86
 1.351230-3 4.060560-4 1.165450-3 1.653720-3 1.245440-3 6.684260-4412540  4   87
 3.383700-4 3.185210-4 5.577470-4 9.980400-4 1.597830-3 2.330860-3412540  4   88
 3.877570-3 3.510400-3 1.743520-3 1.068090-3 1.293590-3 1.293280-3412540  4   89
 1.085130-3 9.278740-4 9.323140-4 1.111090-3 1.447670-3 1.923320-3412540  4   90
 2.523750-3 7.414390-3 7.906620-3 3.667750-3 6.525600-4 4.905720-4412540  4   91
 1.438910-3 2.364500-3 2.948770-3 3.187050-3 3.146430-3 2.886070-3412540  4   92
 2.448850-3 1.358160-2 1.079440-2 4.940620-3 1.974820-3 1.624540-3412540  4   93
 2.340620-3 3.263720-3 4.071640-3 4.684760-3 5.098500-3 5.330850-3412540  4   94
 1.467980-2 1.129750-2 6.032760-3 2.540470-3 1.127810-3 1.190650-3412540  4   95
 2.185420-3 3.781260-3 5.796800-3 8.136660-3 1.172610-2 7.841660-3412540  4   96
 3.961550-3 1.607330-3 7.717680-4 1.097320-3 2.271930-3 4.092850-3412540  4   97
 6.436120-3 6.765760-3 4.842440-3 3.296060-3 2.373560-3 2.015210-3412540  4   98
 2.102290-3 2.542480-3 3.271550-3 5.031110-3 4.728170-3 4.240230-3412540  4   99
 3.664830-3 3.050690-3 2.416420-3 1.766290-3 5.484480-3 5.547470-3412540  4  100
 5.182140-3 4.486210-3 3.539640-3 2.388760-3 6.241640-3 6.330080-3412540  4  101
 6.059800-3 5.483720-3 4.660630-3 7.169080-3 7.640690-3 7.944700-3412540  4  102
 8.083190-3 9.263750-3 1.077760-2 1.235910-2 1.397320-2 1.732040-2412540  4  103
 2.295720-2                                                       412540  4  104
                                                                  412540  099999
 4.10930E+4 9.21083E+1          0          0          1          0412540 16    1
 0.0       -8.83110E+6          0          0          0          1412540 16    2
 1.000000+1 0.000000+0          0         16          0          1412540 16    3
 0.000000+0 0.000000+0          1          5        210         20412540 16    4
 1.000000-5 8.900000+6 9.250000+6 9.500000+6 9.750000+6 1.000000+7412540 16    5
 1.050000+7 1.100000+7 1.150000+7 1.200000+7 1.250000+7 1.340000+7412540 16    6
 1.400000+7 1.450000+7 1.500000+7 1.600000+7 1.700000+7 1.800000+7412540 16    7
 1.900000+7 2.000000+7 1.841580-2 0.000000+0 0.000000+0 0.000000+0412540 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0412540 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0412540 16   10
 0.000000+0 0.000000+0 0.000000+0 1.841580-2-5.728770-4 1.657170-3412540 16   11
 1.455050-3 7.578240-4 1.487120-4-1.526500-4-2.597930-4-2.584590-4412540 16   12
-1.688160-4-4.368440-5 4.388290-5 1.098510-4 1.738450-4 1.938990-4412540 16   13
 1.316680-4-1.410550-5-2.449450-4 6.395990-4 2.205000-4 1.633780-4412540 16   14
 1.415700-4 1.287930-4 1.149910-4 9.899660-5 8.228950-5 6.007320-5412540 16   15
 3.972790-5 2.775870-5 1.927900-5 1.116450-5 7.840190-6 1.330400-5412540 16   16
 2.737810-5 5.011810-5 3.976950-4 3.423270-4 2.498580-4 1.613170-4412540 16   17
 1.040950-4 6.832150-5 4.629340-5 2.983180-5 2.172710-5 1.964290-5412540 16   18
 1.926420-5 2.007100-5 2.179040-5 2.296730-5 2.277950-5 2.077240-5412540 16   19
 3.336790-4 2.640930-4 1.907400-4 1.363570-4 9.741720-5 6.961210-5412540 16   20
 4.395540-5 2.694600-5 1.961410-5 1.563060-5 1.332480-5 1.463850-5412540 16   21
 1.974150-5 2.763930-5 3.782410-5 2.460430-4 2.058710-4 1.660420-4412540 16   22
 1.300130-4 9.897580-5 6.427630-5 3.669500-5 2.240070-5 1.326570-5412540 16   23
 5.943540-6 5.400590-6 1.459300-5 3.254010-5 5.881020-5 1.976580-4412540 16   24
 1.728470-4 1.435010-4 1.139590-4 7.680860-5 4.462290-5 2.671640-5412540 16   25
 1.464250-5 4.062820-6 1.535500-6 1.188640-5 3.429400-5 6.845130-5412540 16   26
 1.599410-4 1.373640-4 1.124330-4 7.886480-5 4.844590-5 3.090580-5412540 16   27
 1.874320-5 7.548880-6 3.762390-6 1.263450-5 3.354330-5 6.628720-5412540 16   28
 1.220450-4 1.025030-4 7.522960-5 4.970570-5 3.459520-5 2.388300-5412540 16   29
 1.360900-5 9.229420-6 1.558390-5 3.223920-5 5.907260-5 8.921230-5412540 16   30
 6.886480-5 4.947110-5 3.769610-5 2.916110-5 2.062300-5 1.620220-5412540 16   31
 1.989420-5 3.142810-5 5.073680-5 5.863580-5 4.779660-5 4.103260-5412540 16   32
 3.592850-5 3.043560-5 2.674340-5 2.736810-5 3.221500-5 4.126730-5412540 16   33
 4.558070-5 4.353010-5 4.191100-5 3.978220-5 3.756860-5 3.619940-5412540 16   34
 3.571340-5 3.612990-5 4.487720-5 4.532580-5 4.556720-5 4.487230-5412540 16   35
 4.310650-5 4.037530-5 3.671940-5 4.788290-5 4.994220-5 5.089690-5412540 16   36
 4.958410-5 4.615120-5 4.065950-5 5.501730-5 5.869390-5 5.956310-5412540 16   37
 5.761910-5 5.296130-5 6.734270-5 7.336690-5 7.759760-5 7.999730-5412540 16   38
 8.807950-5 1.031920-4 1.196930-4 1.348650-4 1.722210-4 2.385330-4412540 16   39
                                                                  412540  099999
                                                                  4125 0  0    0
                                                                     0 0  0    0
 4.51030E+4 1.02021E+2          0          0         34         104525 1451    1
 0.0        0.0                 0          0          0          64525 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20024525 1451    3
 3.00000E+2 0.0                 1          0        179          54525 1451    4
 45-Rh-103 FEI        EVAL-Mar03 K.I.Zolotarev                    4525 1451    5
                      DIST-Feb2004                                4525 1451    6
----IRDF-2002         MATERIAL 4525                               4525 1451    7
-----INCIDENT NEUTRON DATA                                        4525 1451    8
------ENDF-6 FORMAT                                               4525 1451    9
***************************************************************** 4525 1451   10
 45-Rh-103 FEI        EVAL-Mar03 K.I.Zolotarev                    4525 1451   11
                      DIST-Apr03                                  4525 1451   12
----BROND-2           MATERIAL 4525                               4525 1451   13
-----INCIDENT NEUTRON DATA                                        4525 1451   14
------ENDF-6 FORMAT                                               4525 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    4525 1451   16
***************************************************************** 4525 1451   17
                    ----- MF=3 MT=51  -----                       4525 1451   18
  For the IRDF-2002 file this reaction was converted at IAEA/NDS  4525 1451   19
  The reaction MF/MT=3/51 was converted to MF/MT=10/ 4            4525 1451   20
  The corresponding co-variance files were also converted         4525 1451   21
  The reaction MF/MT=33/51 was converted to MF/MT=40/ 4           4525 1451   22
***************************************************************** 4525 1451   23
Authors of evaluation: K.I.Zolotarev and P.K.Zolotarev            4525 1451   24
***************************************************************** 4525 1451   25
MF=3                                                              4525 1451   26
MT= 51 - Rh103(n,n')Rh103m  reaction                              4525 1451   27
-------------------------------------                             4525 1451   28
    In the section MT= 51 are given evaluated  cross section data 4525 1451   29
of neutron inelastic excitation of the  56.12-min  isomeric state 4525 1451   30
in the rhodium-103  in the energy range from threshold to 20 MeV. 4525 1451   31
The isomeric level has energy  39.756 keV  with spin  and  parity 4525 1451   32
7/2+ [1].                                                         4525 1451   33
    Microscopic experimental data  [4-13]  were  analyzed in  the 4525 1451   34
process of preparation  of input data base  for the evaluation of 4525 1451   35
cross sections and their uncertainty  for the Rh-103(n,n')Rh-103m 4525 1451   36
reaction.  During this procedure all experimental data  if it was 4525 1451   37
possible were corrected to the new recommended cross section data 4525 1451   38
for monitor reactions used in the measurements and to the new re- 4525 1451   39
commended decay data.  Decay data for the rhodium-103m were taken 4525 1451   40
from  ref. [2].   Recommended  cross sections  for  the  reaction 4525 1451   41
In-115(n,n')In-115m  used as a monitor  in  the measurements [4], 4525 1451   42
[5] and [7] were taken from ref. [3].                             4525 1451   43
    Special correction was done with experimental data [4], [6].  4525 1451   44
    Data  of Cross [4]  for the neutron energies  2.20 - 2.86 MeV 4525 1451   45
were renormalized to the measured by Paulsen et al. cross section 4525 1451   46
value (994.0+-45.7) mb at 2.60 MeV [8].                           4525 1451   47
    Data of  Santry and Butler [6]  obtained  in the measurements 4525 1451   48
with D(d,n)He3 source in the energy range 5.00-13.58 MeV were re- 4525 1451   49
normalized to the integral of Miach et al. experimental data [10] 4525 1451   50
in the energy interval 6.0-12.0 MeV, Fc= 0.90190 . Cross sections 4525 1451   51
measured by Santry and Butler  with using  Li7(p,n)Be7, T(p,n)He3 4525 1451   52
and T(d,n)He4 neutron sources were not corrected.                 4525 1451   53
    Excitation function for the Rh-103(n,n')Rh-103m  reaction  in 4525 1451   54
the energy region from threshold to 20 MeV was evaluated by means 4525 1451   55
of statistical analysis of experimental cross section data [4-10].4525 1451   56
    Experimental cross section data [11-13] were rejected  due to 4525 1451   57
their discrepancy with the main bulk of experimental data [4-10]. 4525 1451   58
In the rejected experiment [11] the cross section value was deter-4525 1451   59
mined only in a one energy point 14.20 MeV.                       4525 1451   60
    Statistical analysis of input cross section data was carried  4525 1451   61
out by means of PADE-2 code [14].  Rational function was used as  4525 1451   62
the model function [15].                                          4525 1451   63
    U-235 thermal fission [16]  and  Cf-252 spontaneous  fission  4525 1451   64
neutron spectra [17] averaged cross sections calculated from the  4525 1451   65
the evaluated Rh-103(n,n')Rh-103m  excitation function  are  the  4525 1451   66
following:                                                        4525 1451   67
  4525 1451   68
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  4525 1451   69
  4525 1451   70
 U-235 neutron fission     715.85         702.16+-28.08   [18]  4525 1451   71
                                          721.16+-38.65   [19]  4525 1451   72
                                          670.73+-52.05   [20]  4525 1451   73
  4525 1451   74
 Cf-252 spont. fission     724.83         620.82+-67.17   [21]  4525 1451   75
                                          813.29+-24.24   [22]  4525 1451   76
                                          813.22+-24.15   [22]  4525 1451   77
  4525 1451   78
    Integral experimental data [18-22]  were corrected to the new 4525 1451   79
recommended cross sections  for monitor reactions  from ref. [23] 4525 1451   80
and [24].                                                         4525 1451   81
                                                                  4525 1451   82
MT=33                                                             4525 1451   83
MT= 51 -(n,n') cross section cov. matrix                          4525 1451   84
----------------------------------------                          4525 1451   85
    Uncertainties in the evaluated  excitation function  for  the 4525 1451   86
reaction  Rh-103(n,n')Rh-103m  are given  in the form of relative 4525 1451   87
covariance matrix for the 35-neutron energy groups (LB=5).  Cova- 4525 1451   88
riance matrix of uncertainties was calculated simultaneously with 4525 1451   89
recommended cross section data by means of PADE-2 code.           4525 1451   90
    Eigenvalues  of the  6-th digits  relative covariance matrix  4525 1451   91
given in the 33-file are the following:                           4525 1451   92
                                                                  4525 1451   93
    4.63337E-06    4.70345E-06    4.81607E-06    4.97060E-06      4525 1451   94
    5.13303E-06    5.31401E-06    5.53768E-06    5.79915E-06      4525 1451   95
    6.08110E-06    6.37403E-06    6.83267E-06    7.59079E-06      4525 1451   96
    8.42883E-06    9.54383E-06    1.23066E-05    1.44930E-05      4525 1451   97
    2.21073E-05    4.79767E-05    9.57950E-05    1.42110E-04      4525 1451   98
    1.77925E-04    2.06906E-04    5.62715E-04    1.57661E-03      4525 1451   99
    1.64672E-03    1.73445E-03    2.10901E-03    2.41391E-03      4525 1451  100
    2.81682E-03    8.17990E-03    1.45397E-02    1.82324E-02      4525 1451  101
    5.39402E-02    1.07397E-01    1.22586E-01                     4525 1451  102
                                                                  4525 1451  103
References:                                                       4525 1451  104
 1. R.B.Firestone   Table of Isotopes, Eighth edition, Vol. 1,    4525 1451  105
    John Wiley & Sons, Inc., New York, 1995                       4525 1451  106
 2. H.Vonach et al.    Proc. Inter. Conf. on Nuclear Data for     4525 1451  107
    Science and Technology Gatlinburg, Tennessee, USA May 9-13,   4525 1451  108
    1994, v.1, pp.278-280 ;                                       4525 1451  109
    U.Schotzig   PTB, Braunschweig, FRG, 1994                     4525 1451  110
 3. K.I.Zolotarev, F.K.Zolotarev  RRDF-2002, MAT=4921, IPPE,      4525 1451  111
    Obninsk, evaluated March 2003                                 4525 1451  112
 4. W.G.Cross     Physics in Canada, v.19, p.39, June 1963        4525 1451  113
 5. A.Pazsit, J.Csikai  Sov. Journal of Nuclear Physics, v.15,    4525 1451  114
    p.232, 1972.                                                  4525 1451  115
 6. D.C.Santry, J.P.Butler  Canadian Journal of Physics, v.52,    4525 1451  116
    p.1421, August 1974                                           4525 1451  117
 7. A.Pazsit, G.Peto, J.Csikai, I.Jozsa, J.Bacso                  4525 1451  118
    J. of Applied Radiation and Isotopes, v.26, p.621, Oct. 1975  4525 1451  119
 8. A.Paulsen et al.   Nucl. Sci. Eng., v.76, p.331, 1980         4525 1451  120
 9. Li Jianwei et al.  Proc. of an Int. Conf. on Nuclear Data for 4525 1451  121
    Science and Technology, 30 May - 3 June 1988, Mito, Japan,    4525 1451  122
    Saikon Publishing Co., LTD, p.315, 1988                       4525 1451  123
10. M.M.H.Miah, B.Strohmaier, H.Vonach, W.Mannhart, D.Schmidt     4525 1451  124
    Phys. Rev., pt. C, v.54, No.1, p.222, July 1996               4525 1451  125
11. W.Nagel    J. Nucl. Energ., v.20, p.475, June 1966            4525 1451  126
12. I.Kimura et al.    Journal of Nucl. Science and Technology,   4525 1451  127
    v.6, p.485, September 1969                                    4525 1451  128
13. E.Barnard, D.Reitmann  Nucl. Phys., v.A303, p.27, June 1978   4525 1451  129
14. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          4525 1451  130
15. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 4525 1451  131
    st's Meeting on Evaluation and Processing of Covariance Data, 4525 1451  132
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  4525 1451  133
16. L.W.Weston et al.  Evaluated Neutron Data  for  Uranium-235,  4525 1451  134
    ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989    4525 1451  135
17. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        4525 1451  136
18. E.I.Grigor'ev et al.  6th All Union Conference on Neutron     4525 1451  137
    Physics, Kiev, 2-6 October 1983, v.3, p.187, Moscow 1984      4525 1451  138
19. O.Horibe et al. Proc. of Conf.: 50 Years with Nuclear Fission,4525 1451  139
    Washington D.C., 25-28 April 1989, v.2, p.923 ;               4525 1451  140
    O.Horibe, H.Chatani  Proc. of Int. Conf. Nuclear Data for Sci.4525 1451  141
    and Technology, Julich, FRG, 13-17 May 1991, Springer-Verlag, 4525 1451  142
    Berlin Heidelberg, 1992, p.68                                 4525 1451  143
20. K.Kobayashi, T.Kobayashi   Progress Report NEANDC(J)-155/U,   4525 1451  144
    p.52, August 1990                                             4525 1451  145
21. G.J.Kirouac et al.  Report - 4005, Knolls Atomic Power Lab.,  4525 1451  146
    January 1974                                                  4525 1451  147
22. G.P.Lamaze et al.  Nucl. Sci. Eng., v.100, p.43, Sept. 1988   4525 1451  148
23. W.Mannhart  Prog. Report INDC(Ger)-045, pp.40-43, June 1999   4525 1451  149
24. W.Mannhart  Validation of Differential Cross Sections with    4525 1451  150
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 4525 1451  151
    September 2002                                                4525 1451  152
***************************************************************** 4525 1451  153
 File 2 added to the pointwise file containing only the effective 4525 1451  154
 scattering radius with no resonance parameters given.            4525 1451  155
 Taken from ENDF/B-VI                                             4525 1451  156
                                                                  4525 1451  157
***************************************************************** 4525 1451  158
 ***************** Program LINEAR (VERSION 2002-1) ***************4525 1451  159
 For All Data Greater than 1.0000E-10 barns in Absolute Value     4525 1451  160
 Data Linearized to Within an Accuracy of .100000000 per-cent     4525 1451  161
 ***************** Program SIGMA1 (VERSION 2002-1) ***************4525 1451  162
 Data Doppler Broadened to 300.000000 Kelvin                      4525 1451  163
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4525 1451  164
 Data Linearized to Within an Accuracy pf .100000000 per-cent     4525 1451  165
 ***************** Program FIXUP (Version 2002-1) ****************4525 1451  166
 Corrected ZA/AWR in All Sections-----------------------------Yes 4525 1451  167
 Corrected Thresholds-----------------------------------------Yes 4525 1451  168
 Extended Cross Sections to 20 MeV----------------------------No  4525 1451  169
 Allow Cross Section Deletion---------------------------------No  4525 1451  170
 Allow Cross Section Reconstruction---------------------------No  4525 1451  171
 Make All Cross Sections Non-Negative-------------------------Yes 4525 1451  172
 Delete Energies Not in Ascending Order-----------------------Yes 4525 1451  173
 Deleted Duplicate Points-------------------------------------Yes 4525 1451  174
 Check for Ascending MAT/MF/MT Order--------------------------Yes 4525 1451  175
 Check for Legal MF/MT Numbers--------------------------------Yes 4525 1451  176
 Allow Creation of Missing Sections---------------------------No  4525 1451  177
 Allow Insertion of Energy Points-----------------------------No  4525 1451  178
 Create Uniform Energy Grid-----------------------------------No  4525 1451  179
 Delete Section if Cross Section =0 at All Energies-----------Yes 4525 1451  180
 ***************** Program GROUPIE (VERSION 2002-1) **************4525 1451  181
 Unshielded Group Averages Using  640 Groups                      4525 1451  182
 Weighting Spectrum: Flat (Constant) Spectrum                     4525 1451  183
                                1        451        188          14525 1451  184
                                2        151          4          14525 1451  185
                                8          4          2          14525 1451  186
                               10          4         88          14525 1451  187
                               40          4        122          14525 1451  188
                                                                  4525 1  099999
                                                                  4525 0  0    0
 4.51030E+4 1.02021E+2          0          0          1          04525 2151    1
 4.510300+4 1.000000+0          0          0          1          04525 2151    2
 1.000000-5 4.115900+3          0          0          0          04525 2151    3
 5.000000-1 6.560000-1          0          0          0          04525 2151    4
                                                                  4525 2  099999
                                                                  4525 0  0    0
 4.51030E+4 1.02021E+2          0          0          1          14525 8  4    1
 4.51030E+4 0.000000+0         10          0          0          04525 8  4    2
                                                                  4525 8  099999
                                                                  4525 0  0    0
 4.51030E+4 1.02021E+2          0          0          1          0452510  4    1
 0.0       -3.97560E+4      45103          0          1        255452510  4    2
        255          1                                            452510  4    3
 40000.0000 .000131876 42500.0000 .000427871 45000.0000 .000724345452510  4    4
 47500.0000 .001020819 50000.0000 .001317294 52500.0000 .001613768452510  4    5
 55000.0000 .001910242 57500.0000 .002206716 60000.0000 .002532837452510  4    6
 63000.0000 .002888606 66000.0000 .003244375 69000.0000 .003600144452510  4    7
 72000.0000 .004015207 76000.0000 .004489566 80000.0000 .004963924452510  4    8
 84000.0000 .005438283 88000.0000 .005912641 92000.0000 .006387000452510  4    9
 96000.0000 .006861358 100000.000 .007395012 105000.000 .007987960452510  4   10
 110000.000 .008580908 115000.000 .009173856 120000.000 .011379589452510  4   11
 127500.000 .015198106 135000.000 .019016624 142500.000 .022835141452510  4   12
 150000.000 .027155800 160000.000 .031978600 170000.000 .036801400452510  4   13
 180000.000 .041624200 190000.000 .046447000 200000.000 .051090690452510  4   14
 210000.000 .055555270 220000.000 .060019850 230000.000 .064484430452510  4   15
 240000.000 .070033483 255000.000 .076286950 270000.000 .081392600452510  4   16
 280000.000 .087519380 300000.000 .095305320 320000.000 .102708160452510  4   17
 340000.000 .110028295 360000.000 .116852200 380000.000 .123593400452510  4   18
 400000.000 .131003000 425000.000 .139081000 450000.000 .147617250452510  4   19
 475000.000 .156611750 500000.000 .167446250 525000.000 .180120750452510  4   20
 550000.000 .196934000 575000.000 .217886000 600000.000 .248218100452510  4   21
 630000.000 .288511267 660000.000 .336357000 690000.000 .385875133452510  4   22
 720000.000 .440636700 760000.000 .491837800 800000.000 .530516200452510  4   23
 840000.000 .558433425 880000.000 .578712300 920000.000 .594550300452510  4   24
 960000.000 .607908400 1000000.00 .628120500 1100000.00 .654950833452510  4   25
 1200000.00 .680806500 1300000.00 .706662167 1400000.00 .731736500452510  4   26
 1500000.00 .756029500 1600000.00 .779401000 1700000.00 .801851000452510  4   27
 1800000.00 .823285500 1900000.00 .843704500 2000000.00 .863116000452510  4   28
 2100000.00 .881520000 2200000.00 .898753833 2300000.00 .914817500452510  4   29
 2400000.00 .930881167 2500000.00 .945705167 2600000.00 .959289500452510  4   30
 2700000.00 .972873833 2800000.00 .985413333 2900000.00 .996908000452510  4   31
 3000000.00 1.00840267 3100000.00 1.01891625 3200000.00 1.02844875452510  4   32
 3300000.00 1.03798125 3400000.00 1.04751375 3500000.00 1.05618625452510  4   33
 3600000.00 1.06399875 3700000.00 1.07181125 3800000.00 1.07962375452510  4   34
 3900000.00 1.08670417 4000000.00 1.09305250 4100000.00 1.09940083452510  4   35
 4200000.00 1.10574917 4300000.00 1.11209750 4400000.00 1.11844583452510  4   36
 4500000.00 1.12419500 4600000.00 1.12934500 4700000.00 1.13449500452510  4   37
 4800000.00 1.13964500 4900000.00 1.14479500 5000000.00 1.14994500452510  4   38
 5100000.00 1.15509500 5200000.00 1.16024500 5300000.00 1.16539500452510  4   39
 5400000.00 1.17054500 5500000.00 1.17544306 5600000.00 1.18008917452510  4   40
 5700000.00 1.18473528 5800000.00 1.18938139 5900000.00 1.19402750452510  4   41
 6000000.00 1.19867361 6100000.00 1.20331972 6200000.00 1.20796583452510  4   42
 6300000.00 1.21261194 6400000.00 1.21725806 6500000.00 1.22190417452510  4   43
 6600000.00 1.22655028 6700000.00 1.23119639 6800000.00 1.23584250452510  4   44
 6900000.00 1.24048861 7000000.00 1.24513472 7100000.00 1.24978083452510  4   45
 7200000.00 1.25442694 7300000.00 1.25850604 7400000.00 1.26201811452510  4   46
 7500000.00 1.26553018 7600000.00 1.26904225 7700000.00 1.27255432452510  4   47
 7800000.00 1.27521141 7900000.00 1.27701386 8000000.00 1.27881632452510  4   48
 8100000.00 1.28061877 8200000.00 1.28169500 8300000.00 1.28126333452510  4   49
 8400000.00 1.28005000 8500000.00 1.27883667 8600000.00 1.27616167452510  4   50
 8700000.00 1.27202500 8800000.00 1.26788833 8900000.00 1.26225250452510  4   51
 9000000.00 1.25511750 9100000.00 1.24661250 9200000.00 1.23673750452510  4   52
 9300000.00 1.22537250 9400000.00 1.21251750 9500000.00 1.19811000452510  4   53
 9600000.00 1.18215000 9700000.00 1.16464500 9800000.00 1.14559500452510  4   54
 9900000.00 1.12508000 10000000.0 1.10310000 10100000.0 1.07982250452510  4   55
 10200000.0 1.05524750 10300000.0 1.02941133 10400000.0 1.00231400452510  4   56
 10500000.0 .975216667 10600000.0 .947189214 10700000.0 .918231643452510  4   57
 10800000.0 .889274071 10900000.0 .860316500 11000000.0 .831358929452510  4   58
 11100000.0 .802401357 11200000.0 .773443786 11300000.0 .745237500452510  4   59
 11400000.0 .717782500 11500000.0 .690327500 11600000.0 .663834250452510  4   60
 11700000.0 .638302750 11800000.0 .613694250 11900000.0 .590008750452510  4   61
 12000000.0 .567314500 12100000.0 .545611500 12200000.0 .524919500452510  4   62
 12300000.0 .505238500 12400000.0 .486307000 12500000.0 .468613000452510  4   63
 12600000.0 .451881500 12700000.0 .436085000 12800000.0 .421192000452510  4   64
 12900000.0 .407167500 13000000.0 .394168750 13100000.0 .381770250452510  4   65
 13200000.0 .370108000 13300000.0 .359182000 13400000.0 .348914750452510  4   66
 13500000.0 .339306250 13600000.0 .330282250 13700000.0 .321842750452510  4   67
 13800000.0 .313918750 13900000.0 .306510250 14000000.0 .299553500452510  4   68
 14100000.0 .293048500 14200000.0 .286937500 14300000.0 .281220500452510  4   69
 14400000.0 .275846750 14500000.0 .270816250 14600000.0 .266083250452510  4   70
 14700000.0 .261647750 14800000.0 .257527167 14900000.0 .253721500452510  4   71
 15000000.0 .249915833 15100000.0 .246422000 15200000.0 .243240000452510  4   72
 15300000.0 .240058000 15400000.0 .237126500 15500000.0 .234445500452510  4   73
 15600000.0 .231764500 15700000.0 .229284167 15800000.0 .227004500452510  4   74
 15900000.0 .224724833 16000000.0 .222629125 16100000.0 .220717375452510  4   75
 16200000.0 .218805625 16300000.0 .216893875 16400000.0 .215159000452510  4   76
 16500000.0 .213601000 16600000.0 .212043000 16700000.0 .210485000452510  4   77
 16800000.0 .208927000 16900000.0 .207520000 17000000.0 .206264000452510  4   78
 17100000.0 .205008000 17200000.0 .203752000 17300000.0 .202496000452510  4   79
 17400000.0 .201240000 17500000.0 .200100429 17600000.0 .199077286452510  4   80
 17700000.0 .198054143 17800000.0 .197031000 17900000.0 .196007857452510  4   81
 18000000.0 .194984714 18100000.0 .193961571 18200000.0 .193024167452510  4   82
 18300000.0 .192172500 18400000.0 .191320833 18500000.0 .190469167452510  4   83
 18600000.0 .189617500 18700000.0 .188765833 18800000.0 .187914167452510  4   84
 18900000.0 .187062500 19000000.0 .186210833 19100000.0 .185413667452510  4   85
 19200000.0 .184671000 19300000.0 .183928333 19400000.0 .183185667452510  4   86
 19500000.0 .182443000 19600000.0 .181700333 19700000.0 .180957667452510  4   87
 19800000.0 .180215000 19900000.0 .179472333 20000000.0 0.0       452510  4   88
                                                                  452510  099999
                                                                  4525 0  0    0
 4.51030E+4 1.02021E+2          0          0          1          0452540  4    1
 0.000000+0-3.975600+4          0          0          0          1452540  4    2
 1.000000+1 0.000000+0          0          4          0          1452540  4    3
 0.000000+0 0.000000+0          1          5        703         37452540  4    4
 1.000000-5 4.000000+4 2.000000+5 4.000000+5 6.000000+5 8.000000+5452540  4    5
 1.000000+6 1.500000+6 2.000000+6 2.500000+6 3.000000+6 3.500000+6452540  4    6
 4.000000+6 4.500000+6 5.000000+6 5.500000+6 6.000000+6 6.500000+6452540  4    7
 7.000000+6 7.500000+6 8.000000+6 8.500000+6 9.000000+6 9.500000+6452540  4    8
 1.000000+7 1.050000+7 1.100000+7 1.150000+7 1.200000+7 1.300000+7452540  4    9
 1.400000+7 1.500000+7 1.600000+7 1.700000+7 1.800000+7 1.900000+7452540  4   10
 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0452540  4   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0452540  4   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0452540  4   13
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0452540  4   14
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0452540  4   15
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0452540  4   16
 0.000000+0 1.201660-1 3.626120-3 5.830250-3 2.406510-3 3.829450-3452540  4   17
 9.421320-4 1.744590-3 2.795830-3 3.312800-3 3.411860-3 3.250220-3452540  4   18
 2.951990-3 2.607590-3 2.280380-3 2.013300-3 1.832210-3 1.747890-3452540  4   19
 1.754810-3 1.828740-3 1.924420-3 1.979780-3 1.934180-3 1.764500-3452540  4   20
 1.522800-3 1.330280-3 1.305230-3 1.474590-3 1.853920-3 1.977210-3452540  4   21
 1.349570-3 4.168760-4-3.002750-4-5.661320-4-3.496380-4 3.015310-4452540  4   22
 4.977370-3 2.720970-3 2.068350-3 1.881520-3 1.983850-3 1.918150-3452540  4   23
 1.869060-3 1.891870-3 1.958280-3 2.036100-3 2.099860-3 2.130840-3452540  4   24
 2.116050-3 2.047420-3 1.922130-3 1.743840-3 1.525610-3 1.293820-3452540  4   25
 1.091910-3 9.788930-4 1.014690-3 1.226060-3 1.564980-3 1.899910-3452540  4   26
 2.072300-3 1.986420-3 1.447110-3 5.347710-4 3.983250-6-8.023330-5452540  4   27
 2.977010-5 1.266280-4 1.141860-4-3.476890-5 3.978040-3 1.824830-3452540  4   28
 1.835480-3 1.643210-3 1.509900-3 1.548560-3 1.631550-3 1.715330-3452540  4   29
 1.779860-3 1.814290-3 1.812430-3 1.770950-3 1.688910-3 1.568090-3452540  4   30
 1.414200-3 1.238960-3 1.062830-3 9.173610-4 8.435190-4 8.807400-4452540  4   31
 1.042860-3 1.290290-3 1.526610-3 1.640340-3 1.567330-3 1.166990-3452540  4   32
 4.944710-4 8.494070-5-1.223270-5 3.449800-5 8.571080-5 7.622970-5452540  4   33
-1.302230-5 3.335450-3 1.865850-3 1.320780-3 1.334180-3 1.390290-3452540  4   34
 1.451910-3 1.509870-3 1.554570-3 1.578240-3 1.575150-3 1.541460-3452540  4   35
 1.475190-3 1.376710-3 1.249730-3 1.103140-3 9.534420-4 8.269430-4452540  4   36
 7.587760-4 7.840130-4 9.172220-4 1.127730-3 1.334760-3 1.441390-3452540  4   37
 1.388440-3 1.050250-3 4.598470-4 8.317440-5-1.962000-5 1.285200-5452540  4   38
 5.886810-5 5.874010-5-6.850400-6 2.935500-3 1.948970-3 1.404000-3452540  4   39
 1.306000-3 1.344960-3 1.428310-3 1.513750-3 1.577960-3 1.607040-3452540  4   40
 1.592890-3 1.531610-3 1.423490-3 1.273950-3 1.095770-3 9.119690-4452540  4   41
 7.582380-4 6.808130-4 7.237980-4 9.020240-4 1.170360-3 1.421600-3452540  4   42
 1.534730-3 1.444670-3 1.011040-3 3.314790-4-2.048830-5-3.774030-5452540  4   43
 6.704390-5 1.361820-4 1.034210-4-4.532930-5 2.185350-3 1.745000-3452540  4   44
 1.484750-3 1.385400-3 1.380060-3 1.419750-3 1.470620-3 1.509200-3452540  4   45
 1.519370-3 1.490590-3 1.417430-3 1.300150-3 1.146670-3 9.756850-4452540  4   46
 8.197340-4 7.246800-4 7.391190-4 8.883700-4 1.141090-3 1.399790-3452540  4   47
 1.541910-3 1.489490-3 1.091420-3 4.000170-4-6.305970-6-6.918640-5452540  4   48
 1.719700-5 8.992070-5 7.228520-5-5.799610-5 1.705580-3 1.595370-3452540  4   49
 1.530820-3 1.492930-3 1.468820-3 1.447610-3 1.420890-3 1.382350-3452540  4   50
 1.327560-3 1.254000-3 1.161690-3 1.054450-3 9.418340-4 8.412030-4452540  4   51
 7.780520-4 7.807980-4 8.663420-4 1.019870-3 1.186120-3 1.289640-3452540  4   52
 1.274940-3 1.030670-3 5.329380-4 1.499900-4-1.318120-5-3.406270-5452540  4   53
-5.586790-6 1.728610-5 1.067630-5 1.634360-3 1.625160-3 1.607390-3452540  4   54
 1.574910-3 1.528640-3 1.468740-3 1.395220-3 1.308330-3 1.209170-3452540  4   55
 1.100440-3 9.876960-4 8.808630-4 7.955860-4 7.526840-4 7.727340-4452540  4   56
 8.635330-4 1.004710-3 1.144140-3 1.218310-3 1.185790-3 9.517920-4452540  4   57
 5.073870-4 1.702880-4 1.966640-5-9.743300-6 7.648470-6 2.860580-5452540  4   58
 3.445390-5 1.686590-3 1.698690-3 1.689110-3 1.652020-3 1.589090-3452540  4   59
 1.501910-3 1.392580-3 1.264400-3 1.123050-3 9.780430-4 8.445670-4452540  4   60
 7.445890-4 7.049900-4 7.491080-4 8.799410-4 1.062630-3 1.225610-3452540  4   61
 1.292150-3 1.222690-3 9.173280-4 4.205910-4 1.117470-4 2.198870-5452540  4   62
 3.810570-5 6.754520-5 6.709010-5 2.377900-5 1.767300-3 1.787600-3452540  4   63
 1.778600-3 1.732110-3 1.648380-3 1.529190-3 1.378700-3 1.204750-3452540  4   64
 1.020930-3 8.488400-4 7.195540-4 6.705770-4 7.337420-4 9.118860-4452540  4   65
 1.155540-3 1.366660-3 1.444020-3 1.340990-3 9.399110-4 3.401500-4452540  4   66
 3.115010-5 3.701460-6 7.870690-5 1.295250-4 1.052400-4-3.667290-6452540  4   67
 1.861870-3 1.882680-3 1.864080-3 1.796830-3 1.681110-3 1.520660-3452540  4   68
 1.324290-3 1.108380-3 8.998800-4 7.381710-4 6.716550-4 7.426720-4452540  4   69
 9.579980-4 1.258590-3 1.523090-3 1.624410-3 1.503210-3 1.018640-3452540  4   70
 3.048970-4-3.417320-5-2.491860-5 9.680240-5 1.687500-4 1.281170-4452540  4   71
-3.466650-5 1.953700-3 1.962510-3 1.921520-3 1.822400-3 1.667480-3452540  4   72
 1.465140-3 1.232610-3 9.995790-4 8.107960-4 7.228870-4 7.879580-4452540  4   73
 1.019900-3 1.357890-3 1.666730-3 1.798970-3 1.680060-3 1.145900-3452540  4   74
 3.346320-4-6.084060-5-5.413060-5 8.742170-5 1.740050-4 1.296000-4452540  4   75
-5.921130-5 2.018400-3 2.004860-3 1.934740-3 1.802360-3 1.614240-3452540  4   76
 1.386200-3 1.147330-3 9.433540-4 8.345250-4 8.798450-4 1.102280-3452540  4   77
 1.448040-3 1.781360-3 1.944550-3 1.848350-3 1.309570-3 4.359200-4452540  4   78
-3.516650-5-7.449720-5 5.289760-5 1.437700-4 1.099710-4-6.921970-5452540  4   79
 2.040740-3 2.005170-3 1.912560-3 1.760710-3 1.561740-3 1.340470-3452540  4   80
 1.138540-3 1.013920-3 1.027960-3 1.213110-3 1.531140-3 1.860530-3452540  4   81
 2.046820-3 1.989450-3 1.493570-3 6.047000-4 4.891560-5-7.673680-5452540  4   82
 1.371240-6 8.420380-5 7.466270-5-5.785160-5 2.030060-3 1.988070-3452540  4   83
 1.894760-3 1.751080-3 1.574090-3 1.396040-3 1.266060-3 1.241910-3452540  4   84
 1.364030-3 1.616560-3 1.907010-3 2.099450-3 2.088640-3 1.678040-3452540  4   85
 8.271910-4 1.904990-4-5.195030-5-5.417730-5 7.952040-6 3.346140-5452540  4   86
-1.934510-5 2.026430-3 2.007020-3 1.944500-3 1.840030-3 1.711650-3452540  4   87
 1.592980-3 1.531150-3 1.570710-3 1.721980-3 1.934050-3 2.105380-3452540  4   88
 2.136050-3 1.839400-3 1.079100-3 3.806240-4 7.422110-6-9.667630-5452540  4   89
-6.646090-5-7.827400-8 5.032560-5 2.093200-3 2.129750-3 2.125450-3452540  4   90
 2.075490-3 1.991990-3 1.903760-3 1.852790-3 1.874580-3 1.967840-3452540  4   91
 2.079970-3 2.129570-3 1.951850-3 1.324730-3 6.001410-4 1.053960-4452540  4   92
-1.067670-4-1.161000-4-1.004330-5 1.517680-4 2.296170-3 2.410830-3452540  4   93
 2.468920-3 2.452110-3 2.363350-3 2.232360-3 2.112150-3 2.051350-3452540  4   94
 2.056640-3 2.080990-3 1.991540-3 1.516680-3 8.163850-4 2.383610-4452540  4   95
-6.646880-5-1.167200-4 1.891140-5 2.788530-4 2.672770-3 2.860640-3452540  4   96
 2.948500-3 2.902960-3 2.729070-3 2.481360-3 2.246960-3 2.093980-3452540  4   97
 2.025970-3 1.946320-3 1.600080-3 9.808020-4 3.887410-4 3.325860-5452540  4   98
-4.995920-5 9.539570-5 4.136770-4 3.207960-3 3.435520-3 3.495000-3452540  4   99
 3.349050-3 3.028830-3 2.633510-3 2.280710-3 2.036640-3 1.834010-3452540  4  100
 1.526700-3 1.031610-3 5.177390-4 1.802330-4 8.386130-5 2.111010-4452540  4  101
 5.209780-4 3.846890-3 4.078820-3 4.065070-3 3.778340-3 3.287360-3452540  4  102
 2.728170-3 2.229490-3 1.728800-3 1.286970-3 9.106850-4 5.629970-4452540  4  103
 3.263650-4 2.481130-4 3.284120-4 5.472190-4 4.558340-3 4.791720-3452540  4  104
 4.690670-3 4.237160-3 3.533920-3 2.750150-3 1.782710-3 9.594800-4452540  4  105
 6.041830-4 4.544830-4 3.836850-4 3.591780-4 3.767060-4 4.355290-4452540  4  106
 5.379550-3 5.621120-3 5.396270-3 4.706480-3 3.711170-3 2.207740-3452540  4  107
 7.515130-4 2.027880-4 1.638560-4 2.563050-4 3.091530-4 2.787680-4452540  4  108
 1.688620-4 6.326250-3 6.518650-3 6.081040-3 5.085380-3 3.181080-3452540  4  109
 9.695790-4-6.047840-5-2.210550-4-7.551840-5 4.549650-5 2.181970-5452540  4  110
-1.665760-4 7.262800-3 7.312700-3 6.627790-3 4.695680-3 1.873840-3452540  4  111
 1.345200-4-4.562920-4-4.594530-4-3.217850-4-2.598870-4-3.491170-4452540  4  112
 8.021830-3 7.929730-3 6.477870-3 3.489070-3 1.036030-3-2.102110-4452540  4  113
-5.656340-4-4.887160-4-2.780690-4-8.214510-5 8.624160-3 8.079560-3452540  4  114
 5.538600-3 2.666940-3 7.744250-4-2.478930-5-7.501780-5 2.929000-4452540  4  115
 8.666250-4 9.222250-3 8.299370-3 5.838530-3 3.614610-3 2.386360-3452540  4  116
 2.132820-3 2.604510-3 3.570530-3 1.032610-2 9.947210-3 8.723800-3452540  4  117
 7.726450-3 7.373060-3 7.680650-3 8.542170-3 1.246280-2 1.317360-2452540  4  118
 1.318840-2 1.302470-2 1.298030-2 1.315830-2 1.597610-2 1.695770-2452540  4  119
 1.713040-2 1.683090-2 1.633520-2 1.899860-2 1.933620-2 1.899850-2452540  4  120
 1.818580-2 2.027880-2 1.992020-2 1.919880-2 2.027840-2 1.978060-2452540  4  121
 2.040580-2                                                       452540  4  122
                                                                  452540  099999
                                                                  4525 0  0    0
                                                                     0 0  0    0
 4.71090E+4 1.07969E+2          0          0         34         104731 1451    1
 0.0        0.0                 0          0          0          64731 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20024731 1451    3
 3.00000E+2 0.0                 1          0        138          54731 1451    4
 47-Ag-109 CNDC       EVAL-JUN91 Z.X.ZHAO                         4731 1451    5
                      DIST-FEB2004                                4731 1451    6
----IRDF-2002         MATERIAL 4731                               4731 1451    7
-----INCIDENT NEUTRON DATA                                        4731 1451    8
------ENDF-6 FORMAT                                               4731 1451    9
 ================================================================ 4731 1451   10
 47-AG-109 CNDC       EVAL-JUN91 Z.X.ZHAO                         4731 1451   11
                      DIST-                                       4731 1451   12
----ENDF/A-6          MATERIAL 4731                               4731 1451   13
-----INCIDENT NEUTRON DATA                                        4731 1451   14
------ENDF-6 FORMAT                                               4731 1451   15
 *         *          *          *          *          *         *4731 1451   16
  THIS  EVALUATION WAS PERFORMED BASED ON THE MEASURED DATA       4731 1451   17
  AVAILABLE AND THE CALCULATIONS OF THE SYSTEMATICS AND THEORY.   4731 1451   18
     FILE 2    RESONANCE PARAMETER                                4731 1451   19
       ONLY POTENTIAL SCATTERING RADIUS R' OF REF.[1] IS GIVEN.   4731 1451   20
     FILE 10   PRODUCTION CROSS SECTION OF RADIOACTIVE NUCLIDE    4731 1451   21
       MT=102   109-AG(N,GAMMA)110M-AG REACTION                   4731 1451   22
          THE PRODUCTION CROSS SECTION OF ISOMER STATE OF 110-AG  4731 1451   23
       ARE OBTAINED BY                                            4731 1451   24
                    C.S.(M) = C.S.(M+G)*R                         4731 1451   25
       WHERE C.S.(M+G) REPRESENTS THE TOTAL CAPTURE CROSS SECTION 4731 1451   26
       AND R IS THE RATIO OF THE CAPTURE CROSS SECTION TO ISOMER  4731 1451   27
       STATE AND THE TOTAL CAPTURE CROSS SECTION. THE VALUES OF   4731 1451   28
       R WERE CALCULATED BY USING UNIFY2[2] AND NORMALIZED TO     4731 1451   29
       THE LIMITED DATA FOR C.S.(M) MEASURED AT THERMAL CROSS     4731 1451   30
       SECTION [3-5] AND AROUND 25 KEV [6-7].                     4731 1451   31
          C.S.(M+G) WAS RE-EVALUATED IN THE FOLLOWING WAY:        4731 1451   32
          BELOW 2.5 KEV, C.S.(M+G) WAS CALCULATED FROM A SET      4731 1451   33
       OF RESONANCE PARAMETERS OF JENDL-3 AND AVERAGED IN         4731 1451   34
       SMALL ENERGY INTERVALS.                                    4731 1451   35
          FROM 2.5 KEV TO 20 MEV, THE SYSTEMATICS OF ZHAO [8]     4731 1451   36
       WAS USED TO FIT THE MEASURED DATA OF REFS.[9-10] IN THE    4731 1451   37
       ENERGY RANGE FROM 2.5 KEV TO 2 MEV.                        4731 1451   38
     FILE 8  RADIOACTIVE DECAY DATA                               4731 1451   39
       THE RADIOACTIVE DECAY DATA FOR 110M-AG ARE TAKEN FROM      4731 1451   40
       REFS.[11] AND [12].                                        4731 1451   41
     FILE 40  COVARIANCE DATA FOR FILE 10                         4731 1451   42
       COVARIANCE DATA OF FILE 10 CONSISTES OF TWO COMPONENTS.    4731 1451   43
       ONE OF THEM COME FROM THE UNCERTAINTY OF TOTAL CAPTURE     4731 1451   44
       CROSS SECTION. ANOTHER COME FROM THE NORMALIZATION ERROR   4731 1451   45
       OF R=C.S.(M)/C.S.(M+G).                                    4731 1451   46
 ================================================================ 4731 1451   47
 =========== Processing done at IAEA/NDS for IRDF-2002 ========== 4731 1451   48
 ================================================================ 4731 1451   49
 The original file was calculated from a set of resonance         4731 1451   50
 parameters taken from JENDL-3.                                   4731 1451   51
 The JENDL-3.2 file for Ag109 was processed as follows to produce 4731 1451   52
 a pointwise file.                                                4731 1451   53
 ***************** Program LINEAR (VERSION 2002-1) ***************4731 1451   54
 For All Data Greater than 1.0000E-10 barns in Absolute Value     4731 1451   55
 Data Linearized to Within an Accuracy of .100000000 per-cent     4731 1451   56
 ***************** Program RECENT (VERSION 2002-1) ***************4731 1451   57
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4731 1451   58
 Data Linearized to within an Accuracy of .100000000 per-cent     4731 1451   59
 ***************** Program SIGMA1 (VERSION 2002-1) ***************4731 1451   60
 Data Doppler Broadened to 300.000000 Kelvin                      4731 1451   61
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4731 1451   62
 Data Linearized to Within an Accuracy pf 1.00000000 per-cent     4731 1451   63
 ***************** Program FIXUP (Version 2002-1) ****************4731 1451   64
 Corrected ZA/AWR in All Sections-----------------------------Yes 4731 1451   65
 Corrected Thresholds-----------------------------------------No  4731 1451   66
 Extended Cross Sections to 20 MeV----------------------------No  4731 1451   67
 Allow Cross Section Deletion---------------------------------No  4731 1451   68
 Allow Cross Section Reconstruction---------------------------No  4731 1451   69
 Make All Cross Sections Non-Negative-------------------------Yes 4731 1451   70
 Delete Energies Not in Ascending Order-----------------------Yes 4731 1451   71
 Deleted Duplicate Points-------------------------------------Yes 4731 1451   72
 Check for Ascending MAT/MF/MT Order--------------------------Yes 4731 1451   73
 Check for Legal MF/MT Numbers--------------------------------Yes 4731 1451   74
 Allow Creation of Missing Sections---------------------------No  4731 1451   75
 Allow Insertion of Energy Points-----------------------------No  4731 1451   76
 Create Uniform Energy Grid-----------------------------------No  4731 1451   77
 Delete Section if Cross Section =0 at All Energies-----------Yes 4731 1451   78
                                                                  4731 1451   79
 The branching ratio of 0.0465 was applied to the Ag109 total     4731 1451   80
 capture cross section data of the JENDL-3.2 file in the energy   4731 1451   81
 range 1.0E-5 to 7.1E+3. The scaled data with the above energy    4731 1451   82
 range was then edited into the original data file as used for    4731 1451   83
 IRDF-90                                                          4731 1451   84
 ================================================================ 4731 1451   85
                                                                  4731 1451   86
       REFERENCES                                                 4731 1451   87
    [1]  S. F. Mughabghab et al., BNL-325, 4th ed., Vol.(1981)    4731 1451   88
                                                                  4731 1451   89
    [2]  Zhang Jinshang, " Semi-classical Theory Code UNIFY of    4731 1451   90
                 Multi-step Nuclear Reaction", to be published    4731 1451   91
                                                                  4731 1451   92
    [3]  T. B. Ryves et al., J. Nucl. Energy, 25(1971)129         4731 1451   93
                                                                  4731 1451   94
    [4]  J. K. Aaldijk et al., RCN-176,1972                       4731 1451   95
                                                                  4731 1451   96
    [5]  A. Simonits et al., JRN, 81(1984)369                     4731 1451   97
                                                                  4731 1451   98
    [6]  M. Sriramachandra et al., JP/A,5(1972)877                4731 1451   99
                                                                  4731 1451  100
    [7]  W. Poenitz, EANDC(E0-66,6(1966)                          4731 1451  101
                                                                  4731 1451  102
    [8]  Zhao Zhixiang et al., Chinese Nucl. Phys., 11(1989)71    4731 1451  103
                                                                  4731 1451  104
    [9]  R. L. Macklin, Nucl. Sci. and Eng., 82(1982)400          4731 1451  105
                                                                  4731 1451  106
    [10] M. Mizumoto et al., "Neutron Radiative Capture and Transm4731 1451  107
         Measurements of 107-Ag and 109-Ag", Proc. Int. Conf. Nucl4731 1451  108
         for Sci. and Tech., Antwerp, 1982, p.226(1983)           4731 1451  109
                                                                  4731 1451  110
    [11] J. K. Tuli, Nuclear Wallet Cards ,1990                   4731 1451  111
                                                                  4731 1451  112
    [12] C. M. Lederer and V. S. shirley, Table of Isotopes,      4731 1451  113
                              Seventh Edition(1978)               4731 1451  114
                                                                  4731 1451  115
 *****************************************************************4731 1451  116
                                                                  4731 1451  117
                                                                  4731 1451  118
                                                                  4731 1451  119
                                                                  4731 1451  120
 ***************** PROGRAM LINEAR (VERSION 96-1) *************    4731 1451  121
 FOR ALL DATA GREATER THAN 1.00000-10 BARNS IN ABSOLUTE VALUE     4731 1451  122
 DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.10000000 PER-CENT     4731 1451  123
 ***************** Program FIXUP (Version 2002-1) ****************4731 1451  124
 Corrected ZA/AWR in All Sections-----------------------------Yes 4731 1451  125
 Corrected Thresholds-----------------------------------------Yes 4731 1451  126
 Extended Cross Sections to 20 MeV----------------------------No  4731 1451  127
 Allow Cross Section Deletion---------------------------------No  4731 1451  128
 Allow Cross Section Reconstruction---------------------------No  4731 1451  129
 Make All Cross Sections Non-Negative-------------------------Yes 4731 1451  130
 Delete Energies Not in Ascending Order-----------------------Yes 4731 1451  131
 Deleted Duplicate Points-------------------------------------Yes 4731 1451  132
 Check for Ascending MAT/MF/MT Order--------------------------Yes 4731 1451  133
 Check for Legal MF/MT Numbers--------------------------------Yes 4731 1451  134
 Allow Creation of Missing Sections---------------------------No  4731 1451  135
 Allow Insertion of Energy Points-----------------------------No  4731 1451  136
 Create Uniform Energy Grid-----------------------------------No  4731 1451  137
 Delete Section if Cross Section =0 at All Energies-----------Yes 4731 1451  138
 *****************************************************************4731 1451  139
 ***************** Program GROUPIE (VERSION 2002-1) **************4731 1451  140
 Unshielded Group Averages Using  640 Groups                      4731 1451  141
 Weighting Spectrum: Flat (Constant) Spectrum                     4731 1451  142
                                1        451        147          14731 1451  143
                                2        151          4          14731 1451  144
                                8        102          2          14731 1451  145
                               10        102        217          14731 1451  146
                               40        102         10          14731 1451  147
                                                                  4731 1  099999
                                                                  4731 0  0    0
 4.71090E+4 1.07969E+2          0          0          1          04731 2151    1
 4.710900+4 1.000000+0          0          0          1          04731 2151    2
 1.000000-5 2.500000+3          0          0          0          04731 2151    3
 5.000000-1 6.600000-1          0          0          0          04731 2151    4
                                                                  4731 2  099999
                                                                  4731 0  0    0
 4.71090E+4 1.07969E+2          0          0          1          14731 8102    1
 4.711000+4 0.0                10          2          0          04731 8102    2
                                                                  4731 8  099999
                                                                  4731 0  0    0
 4.71090E+4 1.07969E+2          0          0          1          0473110102    1
 6.80570E+6 6.68810E+6      47110          2          1        641473110102    2
        641          1                                            473110102    3
 .000100000 65.8829137 .000105000 64.3718842 .000110000 62.8608547473110102    4
 .000115000 61.3498263 .000120000 59.7673282 .000127500 58.2032108473110102    5
 .000135000 56.6406830 .000142500 55.0781536 .000150000 53.3719172473110102    6
 .000160000 51.8716541 .000170000 50.4199466 .000180000 48.9682391473110102    7
 .000190000 47.5717224 .000200000 46.5123774 .000210000 45.5102445473110102    8
 .000220000 44.5081115 .000230000 43.5059794 .000240000 42.2613097473110102    9
 .000255000 41.0758325 .000270000 40.2204986 .000280000 39.1940977473110102   10
 .000300000 37.8255648 .000320000 36.5868623 .000340000 35.6335300473110102   11
 .000360000 34.6903705 .000380000 33.7472116 .000400000 32.7187027473110102   12
 .000425000 31.8382357 .000450000 31.0164125 .000475000 30.1945889473110102   13
 .000500000 29.3727662 .000525000 28.6779698 .000550000 28.1107284473110102   14
 .000575000 27.5434871 .000600000 26.9195219 .000630000 26.2388329473110102   15
 .000660000 25.5726206 .000690000 25.0645516 .000720000 24.5224400473110102   16
 .000760000 23.9028841 .000800000 23.2833283 .000840000 22.6665876473110102   17
 .000880000 22.1733049 .000920000 21.7461036 .000960000 21.3189020473110102   18
 .001000000 20.8383005 .001050000 20.3042989 .001100000 19.8093341473110102   19
 .001150000 19.4297664 .001200000 18.9647759 .001275000 18.4067875473110102   20
 .001350000 17.8509108 .001425000 17.4043156 .001500000 16.9551107473110102   21
 .001600000 16.4417334 .001700000 15.9283562 .001800000 15.4574255473110102   22
 .001900000 15.1005702 .002000000 14.7500021 .002100000 14.3994339473110102   23
 .002200000 14.0488654 .002300000 13.7117119 .002400000 13.3958410473110102   24
 .002550000 13.0333777 .002700000 12.7313251 .002800000 12.3688618473110102   25
 .003000000 11.9573379 .003200000 11.6207172 .003400000 11.2841050473110102   26
 .003600000 10.9474928 .003800000 10.6608505 .004000000 10.3995298473110102   27
 .004250000 10.1092003 .004500000 9.81887067 .004750000 9.53324534473110102   28
 .005000000 9.31366335 .005250000 9.11538011 .005500000 8.91709686473110102   29
 .005750000 8.71881361 .006000000 8.50070207 .006300000 8.29350107473110102   30
 .006600000 8.12938064 .006900000 7.96555528 .007200000 7.77442561473110102   31
 .007600000 7.55599162 .008000000 7.35868335 .008400000 7.20541658473110102   32
 .008800000 7.05352267 .009200000 6.90162877 .009600000 6.74973504473110102   33
 .010000000 6.58673552 .010500000 6.44858051 .011000000 6.31718378473110102   34
 .011500000 6.18578706 .012000000 6.02154121 .012750000 5.82813424473110102   35
 .013500000 5.68058330 .014250000 5.54674958 .015000000 5.39061010473110102   36
 .016000001 5.21216495 .017000001 5.06131471 .017999999 4.94155886473110102   37
 .018999999 4.82183021 .020000000 4.70210156 .021000000 4.58237291473110102   38
 .022000000 4.46564013 .023000000 4.37180633 .024000000 4.26077658473110102   39
 .025500000 4.14784660 .027000001 4.06409209 .028000001 3.96358678473110102   40
 .029999999 3.82957962 .032000002 3.70540709 .034000002 3.61633992473110102   41
 .035999998 3.53039126 .037999999 3.44444251 .039999999 3.34775015473110102   42
 .042500000 3.24031417 .045000002 3.14491372 .047499999 3.07490080473110102   43
 .050000001 3.00570398 .052499998 2.93650715 .055000000 2.86731028473110102   44
 .057500001 2.80242435 .059999999 2.75162507 .063000001 2.69851727473110102   45
 .066000000 2.64540951 .068999998 2.59230175 .071999997 2.53034268473110102   46
 .075999998 2.45953229 .079999998 2.39456404 .083999999 2.35005872473110102   47
 .088000000 2.30732082 .092000000 2.26458293 .096000001 2.22184503473110102   48
 .100000001 2.17376493 .104999997 2.12034258 .109999999 2.06822125473110102   49
 .115000002 2.03171845 .119999997 1.99179873 .127499998 1.94389502473110102   50
 .135000005 1.89599133 .142499998 1.84808765 .150000006 1.79298122473110102   51
 .159999996 1.74774667 .170000002 1.70994680 .180000007 1.67214696473110102   52
 .189999998 1.63434712 .200000003 1.59654728 .209999993 1.55880204473110102   53
 .219999999 1.53010801 .230000004 1.50800998 .239999995 1.48038745473110102   54
 .254999995 1.44724039 .270000011 1.41961785 .280000001 1.38647080473110102   55
 .300000012 1.34778961 .319999993 1.32230623 .340000004 1.29739575473110102   56
 .360000014 1.27248529 .379999995 1.24757483 .400000006 1.21955998473110102   57
 .425000012 1.19624620 .449999988 1.17972545 .474999994 1.16320469473110102   58
 .500000000 1.14668395 .524999976 1.13016319 .550000012 1.11364243473110102   59
 .574999988 1.09786761 .600000024 1.08820482 .629999995 1.07946669473110102   60
 .660000026 1.07072857 .689999998 1.06199044 .720000029 1.05179595473110102   61
 .759999990 1.04014512 .800000012 1.02949480 .839999974 1.02526660473110102   62
 .879999995 1.02218176 .920000017 1.01909693 .959999979 1.01601209473110102   63
 1.00000000 1.01258668 1.04999995 1.01406959 1.10000002 1.01918386473110102   64
 1.14999998 1.02429814 1.20000005 1.03069099 1.27499998 1.03836240473110102   65
 1.35000002 1.04603381 1.42499995 1.05634426 1.50000000 1.08040889473110102   66
 1.60000002 1.10906368 1.70000005 1.13771845 1.79999995 1.16798398473110102   67
 1.89999998 1.21190394 2.00000000 1.25892606 2.09999990 1.30640427473110102   68
 2.20000005 1.36744349 2.29999995 1.43479879 2.40000010 1.52661189473110102   69
 2.54999995 1.66486967 2.70000005 1.79066902 2.79999995 1.98948174473110102   70
 3.00000000 2.30330077 3.20000005 2.72493186 3.40000010 3.31687339473110102   71
 3.59999990 4.15243584 3.79999995 5.40661480 4.00000000 7.76722306473110102   72
 4.25000000 13.0174447 4.50000000 27.1024049 4.75000000 96.8806427473110102   73
 5.00000000 725.872816 5.25000000 308.558951 5.50000000 43.4722576473110102   74
 5.75000000 16.1345931 6.00000000 7.94958909 6.30000019 4.45517067473110102   75
 6.59999990 2.82372470 6.90000010 1.94246590 7.19999981 1.34770933473110102   76
 7.59999990 .939412905 8.00000000 .689954724 8.39999962 .524834406473110102   77
 8.80000019 .412945385 9.19999981 .331773722 9.60000038 .272591177473110102   78
 10.0000000 .222468516 10.5000000 .181194952 11.0000000 .150276129473110102   79
 11.5000000 .126562773 12.0000000 .104511803 12.7500000 .084725848473110102   80
 13.5000000 .070440364 14.2500000 .059786029 15.0000000 .050501133473110102   81
 16.0000000 .042824923 17.0000000 .037420544 18.0000000 .033690204473110102   82
 19.0000000 .031168806 20.0000000 .029716841 21.0000000 .029477727473110102   83
 22.0000000 .030441135 23.0000000 .032962909 24.0000000 .039841551473110102   84
 25.5000000 .059888636 27.0000000 .105620350 28.0000000 .869990197473110102   85
 30.0000000 15.2751085 32.0000000 .138692160 34.0000000 .060706890473110102   86
 36.0000000 .079835222 38.0000000 3.23543961 40.0000000 5.83855465473110102   87
 42.5000000 .052164789 45.0000000 .027849228 47.5000000 .028598179473110102   88
 50.0000000 .050652422 52.5000000 .354832624 55.0000000 9.53771324473110102   89
 57.5000000 .102404270 60.0000000 .037831276 63.0000000 .040193422473110102   90
 66.0000000 .129269498 69.0000000 14.2435132 72.0000000 .170194501473110102   91
 76.0000000 .025944830 80.0000000 .018358104 84.0000000 2.09023706473110102   92
 88.0000000 .354015421 92.0000000 .010773369 96.0000000 .005944080473110102   93
 100.000000 .005223153 105.000000 .031651345 110.000000 .024353107473110102   94
 115.000000 .008734952 120.000000 .021522423 127.500000 6.79472054473110102   95
 135.000000 .412661156 142.500000 .015144510 150.000000 .007670525473110102   96
 160.000000 .042359786 170.000000 2.99459687 180.000000 .008937011473110102   97
 190.000000 .004496820 200.000000 1.18874814 210.000000 .216723543473110102   98
 220.000000 .002685375 230.000000 .002016628 240.000000 .414107359473110102   99
 255.000000 .074072058 270.000000 .070369378 280.000000 .236487181473110102  100
 300.000000 1.59099734 320.000000 .123750237 340.000000 .004074392473110102  101
 360.000000 .003670073 380.000000 .980494669 400.000000 .390043367473110102  102
 425.000000 .133332857 450.000000 .288156933 475.000000 .273321054473110102  103
 500.000000 .769591133 525.000000 .010301960 550.000000 .979745770473110102  104
 575.000000 .003933997 600.000000 .409036749 630.000000 .006776781473110102  105
 660.000000 .147393373 690.000000 .007641197 720.000000 .309290888473110102  106
 760.000000 .194711821 800.000000 .062692150 840.000000 .059375173473110102  107
 880.000000 .158772525 920.000000 .154912223 960.000000 .173830665473110102  108
 1000.00000 .137231276 1050.00000 .196444584 1100.00000 .122067456473110102  109
 1150.00000 .020582762 1200.00000 .350942078 1275.00000 .166135629473110102  110
 1350.00000 .257040498 1425.00000 .180871517 1500.00000 .205707746473110102  111
 1600.00000 .088162424 1700.00000 .139195318 1800.00000 .102583714473110102  112
 1900.00000 .136826314 2000.00000 .102542574 2100.00000 .150111305473110102  113
 2200.00000 .065128230 2300.00000 .199188779 2400.00000 .095919576473110102  114
 2550.00000 .126391554 2700.00000 .136546956 2800.00000 .098000766473110102  115
 3000.00000 .130069272 3200.00000 .121252881 3400.00000 .065273210473110102  116
 3600.00000 .075219147 3800.00000 .106302348 4000.00000 .096733025473110102  117
 4250.00000 .055626501 4500.00000 .070037029 4750.00000 .077316529473110102  118
 5000.00000 .074751017 5250.00000 .085971376 5500.00000 .074456255473110102  119
 5750.00000 .058042135 6000.00000 .070744369 6300.00000 .087049406473110102  120
 6600.00000 .067582619 6900.00000 .069959010 7200.00000 .074791652473110102  121
 7600.00000 .074231182 8000.00000 .073148724 8400.00000 .072129979473110102  122
 8800.00000 .071140112 9200.00000 .070250536 9600.00000 .069369512473110102  123
 10000.0000 .068723633 10500.0000 .068312899 11000.0000 .067902165473110102  124
 11500.0000 .067492934 12000.0000 .067040371 12750.0000 .066521119473110102  125
 13500.0000 .066040832 14250.0000 .065609035 15000.0000 .065105437473110102  126
 16000.0000 .064546652 17000.0000 .064073090 18000.0000 .063611454473110102  127
 19000.0000 .063149818 20000.0000 .062644853 21000.0000 .062096559473110102  128
 22000.0000 .061548265 23000.0000 .061002080 24000.0000 .060402040473110102  129
 25500.0000 .059715384 27000.0000 .059167431 28000.0000 .058567786473110102  130
 30000.0000 .057829890 32000.0000 .057138859 34000.0000 .056476541473110102  131
 36000.0000 .055891812 38000.0000 .055311404 40000.0000 .054710090473110102  132
 42500.0000 .054088351 45000.0000 .053513049 47500.0000 .052968350473110102  133
 50000.0000 .052104461 52500.0000 .050922003 55000.0000 .049826586473110102  134
 57500.0000 .048792862 60000.0000 .047730372 63000.0000 .046648408473110102  135
 66000.0000 .045653395 69000.0000 .044709909 72000.0000 .043729299473110102  136
 76000.0000 .042689774 80000.0000 .041756772 84000.0000 .040925517473110102  137
 88000.0000 .040159895 92000.0000 .039515200 96000.0000 .038890400473110102  138
 100000.000 .038201172 105000.000 .037447516 110000.000 .036727304473110102  139
 115000.000 .036062543 120000.000 .035304204 127500.000 .034434989473110102  140
 135000.000 .033647943 142500.000 .032907314 150000.000 .032171454473110102  141
 160000.000 .031472932 170000.000 .030825191 180000.000 .030225850473110102  142
 190000.000 .029666617 200000.000 .029075555 210000.000 .028452664473110102  143
 220000.000 .027858101 230000.000 .027310364 240000.000 .026670332473110102  144
 255000.000 .025971561 270000.000 .025417209 280000.000 .024816413473110102  145
 300000.000 .024019543 320000.000 .023245088 340000.000 .022549689473110102  146
 360000.000 .021902956 380000.000 .021313132 400000.000 .020672390473110102  147
 425000.000 .020014329 450000.000 .019400632 475000.000 .018843556473110102  148
 500000.000 .018260961 525000.000 .017678470 550000.000 .017130937473110102  149
 575000.000 .016628575 600000.000 .016110634 630000.000 .015577142473110102  150
 660000.000 .015092685 690000.000 .014631422 720000.000 .014138641473110102  151
 760000.000 .013621142 800000.000 .013143615 840000.000 .012704298473110102  152
 880000.000 .012298597 920000.000 .011922757 960000.000 .011574158473110102  153
 1000000.00 .010950648 1100000.00 .010136679 1200000.00 .009441398473110102  154
 1300000.00 .008843603 1400000.00 .008322346 1500000.00 .007841400473110102  155
 1600000.00 .007396664 1700000.00 .006998287 1800000.00 .006644745473110102  156
 1900000.00 .006325335 2000000.00 .005946862 2100000.00 .005529209473110102  157
 2200000.00 .005155062 2300000.00 .004821228 2400000.00 .004521367473110102  158
 2500000.00 .004251876 2600000.00 .004008317 2700000.00 .003786530473110102  159
 2800000.00 .003584598 2900000.00 .003399992 3000000.00 .003112378473110102  160
 3100000.00 .002752170 3200000.00 .002443123 3300000.00 .002176727473110102  161
 3400000.00 .001946699 3500000.00 .001745744 3600000.00 .001570306473110102  162
 3700000.00 .001417183 3800000.00 .001281677 3900000.00 .001162612473110102  163
 4000000.00 .001026912 4100000.00 .000883232 4200000.00 .000762175473110102  164
 4300000.00 .000660025 4400000.00 .000573415 4500000.00 .000499941473110102  165
 4600000.00 .000436975 4700000.00 .000383144 4800000.00 .000336762473110102  166
 4900000.00 .000296892 5000000.00 .000267552 5100000.00 .000246674473110102  167
 5200000.00 .000227835 5300000.00 .000210658 5400000.00 .000195050473110102  168
 5500000.00 .000180905 5600000.00 .000168025 5700000.00 .000156192473110102  169
 5800000.00 .000145436 5900000.00 .000135566 6000000.00 .000131655473110102  170
 6100000.00 .000133265 6200000.00 .000134875 6300000.00 .000136485473110102  171
 6400000.00 .000138095 6500000.00 .000139705 6600000.00 .000141315473110102  172
 6700000.00 .000142925 6800000.00 .000144535 6900000.00 .000146145473110102  173
 7000000.00 .000149313 7100000.00 .000154038 7200000.00 .000158812473110102  174
 7300000.00 .000163765 7400000.00 .000168735 7500000.00 .000173705473110102  175
 7600000.00 .000178803 7700000.00 .000184081 7800000.00 .000189361473110102  176
 7900000.00 .000194640 8000000.00 .000199311 8100000.00 .000203372473110102  177
 8200000.00 .000207434 8300000.00 .000211496 8400000.00 .000215559473110102  178
 8500000.00 .000219716 8600000.00 .000223928 8700000.00 .000228140473110102  179
 8800000.00 .000232352 8900000.00 .000236564 9000000.00 .000239633473110102  180
 9100000.00 .000241558 9200000.00 .000243483 9300000.00 .000245408473110102  181
 9400000.00 .000247333 9500000.00 .000249258 9600000.00 .000251183473110102  182
 9700000.00 .000253108 9800000.00 .000255033 9900000.00 .000256958473110102  183
 10000000.0 .000257529 10100000.0 .000256747 10200000.0 .000255965473110102  184
 10300000.0 .000255183 10400000.0 .000254401 10500000.0 .000253619473110102  185
 10600000.0 .000252837 10700000.0 .000252055 10800000.0 .000251273473110102  186
 10900000.0 .000250491 11000000.0 .000249258 11100000.0 .000247574473110102  187
 11200000.0 .000245890 11300000.0 .000244206 11400000.0 .000242523473110102  188
 11500000.0 .000240915 11600000.0 .000239356 11700000.0 .000237797473110102  189
 11800000.0 .000236238 11900000.0 .000234679 12000000.0 .000232899473110102  190
 12100000.0 .000230898 12200000.0 .000228897 12300000.0 .000226896473110102  191
 12400000.0 .000224896 12500000.0 .000222990 12600000.0 .000221148473110102  192
 12700000.0 .000219305 12800000.0 .000217463 12900000.0 .000215621473110102  193
 13000000.0 .000213685 13100000.0 .000211655 13200000.0 .000209625473110102  194
 13300000.0 .000207595 13400000.0 .000205566 13500000.0 .000203633473110102  195
 13600000.0 .000201768 13700000.0 .000199903 13800000.0 .000198038473110102  196
 13900000.0 .000196173 14000000.0 .000194206 14100000.0 .000192139473110102  197
 14200000.0 .000190072 14300000.0 .000188004 14400000.0 .000185938473110102  198
 14500000.0 .000183971 14600000.0 .000182078 14700000.0 .000180184473110102  199
 14800000.0 .000178290 14900000.0 .000176397 15000000.0 .000174507473110102  200
 15100000.0 .000172620 15200000.0 .000170734 15300000.0 .000168847473110102  201
 15400000.0 .000166961 15500000.0 .000165165 15600000.0 .000163435473110102  202
 15700000.0 .000161705 15800000.0 .000159975 15900000.0 .000158245473110102  203
 16000000.0 .000156534 16100000.0 .000154842 16200000.0 .000153151473110102  204
 16300000.0 .000151459 16400000.0 .000149768 16500000.0 .000148155473110102  205
 16600000.0 .000146600 16700000.0 .000145046 16800000.0 .000143492473110102  206
 16900000.0 .000141937 17000000.0 .000140408 17100000.0 .000138903473110102  207
 17200000.0 .000137399 17300000.0 .000135895 17400000.0 .000134391473110102  208
 17500000.0 .000132954 17600000.0 .000131569 17700000.0 .000130183473110102  209
 17800000.0 .000128798 17900000.0 .000127413 18000000.0 .000126053473110102  210
 18100000.0 .000124720 18200000.0 .000123387 18300000.0 .000122053473110102  211
 18400000.0 .000120720 18500000.0 .000119445 18600000.0 .000118215473110102  212
 18700000.0 .000116985 18800000.0 .000115755 18900000.0 .000114525473110102  213
 19000000.0 .000113321 19100000.0 .000112142 19200000.0 .000110963473110102  214
 19300000.0 .000109784 19400000.0 .000108605 19500000.0 .000107476473110102  215
 19600000.0 .000106386 19700000.0 .000105296 19800000.0 .000104205473110102  216
 19900000.0 .000103115 20000000.0 0.0                             473110102  217
                                                                  473110  099999
                                                                  4731 0  0    0
 4.71090E+4 1.07969E+2          0          0          1          0473140102    1
 6.806000+6 6.688400+6          0          2          0          1473140102    2
 1.000000+1 2.000000+0          0        102          0          2473140102    3
 0.000000+0 0.000000+0          0          1         22         11473140102    4
 1.000000-5 1.000000-4 1.000000+0 2.500000-3 8.000000+1 1.000000-2473140102    5
 1.500000+2 2.250000-2 3.000000+2 2.250000-2 4.000000+2 2.250000-2473140102    6
 5.000000+2 9.000000-2 6.500000+2 1.000000-2 2.500000+4 2.500000-3473140102    7
 2.000000+6 9.000000-2 2.000000+7 0.000000+0                      473140102    8
 0.000000+0 0.000000+0          0          1          4          2473140102    9
 1.000000-5 2.500000-3 2.000000+7 0.000000+0                      473140102   10
                                                                  473140  099999
                                                                  4731 0  0    0
                                                                     0 0  0    0
 4.80000E+4 1.11445E+2          0          0         34         104800 1451    1
 0.0        0.0                 0          0          0          64800 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20024800 1451    3
 3.00000E+2 0.0                 1          0         77          44800 1451    4
 48-Cd-  0 BNL        EVAL-MAY74 S.PEARLSTEIN(TRANS FROM U.K.)    4800 1451    5
                      DIST-Feb2004                                4800 1451    6
----IRDF-2002         MATERIAL 4800                               4800 1451    7
-----INCIDENT NEUTRON DATA                                        4800 1451    8
------ENDF-6 FORMAT                                               4800 1451    9
 *****************************************************************4800 1451   10
 48-CD-  0 BNL        EVAL-MAY74 S.PEARLSTEIN(TRANS FROM U.K.)    4800 1451   11
                      DIST-JAN90                       19900130   4800 1451   12
----ENDF/B-VI         MATERIAL 4800                               4800 1451   13
-----INCIDENT NEUTRON DATA                                        4800 1451   14
------ENDF-6 FORMAT                                               4800 1451   15
 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC             4800 1451   16
 *         *          *          *          *          *         *4800 1451   17
 UKNDL TO ENDF/B TRANSLATION FROM                                 4800 1451   18
 UKNDL DATA FILE  70  RECEIVED JULY 1973 FROM CCDN                4800 1451   19
                                                                  4800 1451   20
  TRANSLATION OF UKNDL DFN-70 INTO ENDF FORMAT                    4800 1451   21
                                                                  4800 1451   22
  RESONANCE REGION EVALUATED BY MF JAMES IN 1969                  4800 1451   23
  FICTITIOUS CD-111 RESONANCE AT -0.5 EV TO ADJUST CROSS SECTION  4800 1451   24
  IN EV RANGE AND ACHIEVE CONSISTENCY WITH 20 BARN CD-111 THERMAL 4800 1451   25
  CAPTURE CROSS SECTION (BALDOCK ETAL 1966 ORNL-3994)             4800 1451   26
  ABOVE THE RESOLVED RESONANCE RANGE MAINLY DRAKE GA-6997 WAS USED4800 1451   27
                                                                  4800 1451   28
 PLEASE REFER COMMENTS OR QUESTIONS ABOUT THE TRANSLATION         4800 1451   29
 CODE (UKE*** ORNL-TM-2880 OR ENDF-134) TO                        4800 1451   30
 R. Q. WRIGHT, OAK RIDGE NATIONAL LABORATORY,                     4800 1451   31
 P. O. BOX X, OAK RIDGE, TENNESSEE 37830.                         4800 1451   32
                                                                  4800 1451   33
 RANGE EXTENDED FROM 1.0E-5 EV TO 20 MEV AND ELASTIC SCATTERING   4800 1451   34
 TRANSFER AND TRANSFORMATION DATA ADDED BY NNCSC AT BNL           4800 1451   35
                                0          0          0           4800 1451   36
 ***************** PROGRAM LINEAR (VERSION 89-1) *****************4800 1451   37
 DATA LINEARIZED TO WITHIN AN ACCURACY OF     0.300 PER-CENT      4800 1451   38
 ***************** PROGRAM FIXUP (VERSION 89-2) ******************4800 1451   39
 *RECONSTRUCTED MT NUMBERS                                        4800 1451   40
   4 =+( 50, 91)                                                  4800 1451   41
 103 =+(600,649)                                                  4800 1451   42
 104 =+(650,699)                                                  4800 1451   43
 105 =+(700,749)                                                  4800 1451   44
 106 =+(750,799)                                                  4800 1451   45
 107 =+(800,849)                                                  4800 1451   46
 101 =+( 18, 18)+(102,116)                                        4800 1451   47
  27 =+(101,101)                                                  4800 1451   48
   3 =+(  4,  5)+( 16, 17)+( 22, 37)+( 41, 42)                    4800 1451   49
  19 =+( 18, 18)-( 20, 21)-( 38, 38)                              4800 1451   50
   1 =+(  2,  3)                                                  4800 1451   51
 *****************************************************************4800 1451   52
                                                                  4800 1451   53
                                                                  4800 1451   54
                                                                  4800 1451   55
                                                                  4800 1451   56
 ***************** Program LINEAR (VERSION 2002-1) ***************4800 1451   57
 For All Data Greater than 1.0000E-10 barns in Absolute Value     4800 1451   58
 Data Linearized to Within an Accuracy of .100000000 per-cent     4800 1451   59
 ***************** Program SIGMA1 (VERSION 2002-1) ***************4800 1451   60
 Data Doppler Broadened to 300.000000 Kelvin                      4800 1451   61
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4800 1451   62
 Data Linearized to Within an Accuracy pf .100000000 per-cent     4800 1451   63
 ***************** Program FIXUP (Version 2002-1) ****************4800 1451   64
 Corrected ZA/AWR in All Sections-----------------------------Yes 4800 1451   65
 Corrected Thresholds-----------------------------------------Yes 4800 1451   66
 Extended Cross Sections to 20 MeV----------------------------No  4800 1451   67
 Allow Cross Section Deletion---------------------------------No  4800 1451   68
 Allow Cross Section Reconstruction---------------------------No  4800 1451   69
 Make All Cross Sections Non-Negative-------------------------Yes 4800 1451   70
 Delete Energies Not in Ascending Order-----------------------Yes 4800 1451   71
 Deleted Duplicate Points-------------------------------------Yes 4800 1451   72
 Check for Ascending MAT/MF/MT Order--------------------------Yes 4800 1451   73
 Check for Legal MF/MT Numbers--------------------------------Yes 4800 1451   74
 Allow Creation of Missing Sections---------------------------No  4800 1451   75
 Allow Insertion of Energy Points-----------------------------No  4800 1451   76
 Create Uniform Energy Grid-----------------------------------No  4800 1451   77
 Delete Section if Cross Section =0 at All Energies-----------Yes 4800 1451   78
 ***************** Program GROUPIE (VERSION 2002-1) **************4800 1451   79
 Unshielded Group Averages Using  640 Groups                      4800 1451   80
 Weighting Spectrum: Flat (Constant) Spectrum                     4800 1451   81
                                1        451         85          04800 1451   82
                                2        151          4          04800 1451   83
                                3          1        217          04800 1451   84
                                3        102        217          04800 1451   85
                                                                  4800 1  099999
                                                                  4800 0  0    0
 4.80000E+4 1.11445E+2          0          0          1          04800 2151    1
 4.80000E+4 1.00000E+0          0          0          1          04800 2151    2
 1.00000E-5 1.00000E+5          0          0          0          04800 2151    3
 0.0        7.46000E-1          0          0          0          04800 2151    4
                                                                  4800 2  099999
                                                                  4800 0  0    0
 4.80000E+4 1.11445E+2          0          0          0          04800 3  1    1
 0.0        0.0                 0          0          1        6414800 3  1    2
        641          1                                            4800 3  1    3
 .000100000 29407.0831 .000105000 28722.2715 .000110000 28071.69934800 3  1    4
 .000115000 27472.1873 .000120000 26771.4577 .000127500 25994.10844800 3  1    5
 .000135000 25283.8161 .000142500 24631.1861 .000150000 23924.94924800 3  1    6
 .000160000 23189.2717 .000170000 22519.9646 .000180000 21905.64114800 3  1    7
 .000190000 21334.1233 .000200000 20812.4749 .000210000 20321.70614800 3  1    8
 .000220000 19865.8497 .000230000 19442.4426 .000240000 18945.56044800 3  1    9
 .000255000 18399.5789 .000270000 17978.3029 .000280000 17509.39754800 3  1   10
 .000300000 16937.7319 .000320000 16420.3040 .000340000 15946.50474800 3  1   11
 .000360000 15510.1590 .000380000 15112.0336 .000400000 14697.04614800 3  1   12
 .000425000 14272.5001 .000450000 13884.8413 .000475000 13529.48074800 3  1   13
 .000500000 13195.3428 .000525000 12890.1169 .000550000 12601.86864800 3  1   14
 .000575000 12333.8926 .000600000 12059.2969 .000630000 11776.87624800 3  1   15
 .000660000 11518.6337 .000690000 11270.9767 .000720000 11007.59514800 3  1   16
 .000760000 10725.2895 .000800000 10463.2947 .000840000 10223.37704800 3  1   17
 .000880000 9995.42393 .000920000 9786.52876 .000960000 9586.559444800 3  1   18
 .001000000 9379.48279 .001050000 9163.38923 .001100000 8960.890154800 3  1   19
 .001150000 8774.47714 .001200000 8554.69557 .001275000 8313.263874800 3  1   20
 .001350000 8092.81498 .001425000 7887.24877 .001500000 7668.998014800 3  1   21
 .001600000 7441.12967 .001700000 7233.33162 .001800000 7041.324024800 3  1   22
 .001900000 6866.22705 .002000000 6704.03241 .002100000 6551.963094800 3  1   23
 .002200000 6412.97843 .002300000 6280.18478 .002400000 6128.854704800 3  1   24
 .002550000 5961.02976 .002700000 5829.97365 .002800000 5687.805354800 3  1   25
 .003000000 5513.21311 .003200000 5354.73926 .003400000 5210.126324800 3  1   26
 .003600000 5078.63908 .003800000 4957.52520 .004000000 4831.590394800 3  1   27
 .004250000 4704.11601 .004500000 4588.10821 .004750000 4479.985594800 3  1   28
 .005000000 4381.18708 .005250000 4288.67770 .005500000 4205.248774800 3  1   29
 .005750000 4127.02585 .006000000 4043.37604 .006300000 3961.529854800 3  1   30
 .006600000 3884.53340 .006900000 3813.54589 .007200000 3737.821294800 3  1   31
 .007600000 3656.81397 .008000000 3582.25830 .008400000 3514.463134800 3  1   32
 .008800000 3449.63480 .009200000 3392.57902 .009600000 3336.147454800 3  1   33
 .010000000 3280.01050 .010500000 3220.80780 .011000000 3165.827464800 3  1   34
 .011500000 3116.26697 .012000000 3056.75349 .012750000 2993.775724800 3  1   35
 .013500000 2934.84335 .014250000 2882.95374 .015000000 2826.684314800 3  1   36
 .016000001 2770.20627 .017000001 2720.23756 .017999999 2675.037884800 3  1   37
 .018999999 2635.72908 .020000000 2599.61340 .021000000 2567.624014800 3  1   38
 .022000000 2539.13231 .023000000 2511.86739 .024000000 2482.958104800 3  1   39
 .025500000 2454.26312 .027000001 2432.51438 .028000001 2411.048314800 3  1   40
 .029999999 2387.64170 .032000002 2371.17108 .034000002 2358.183324800 3  1   41
 .035999998 2351.54253 .037999999 2346.60570 .039999999 2348.374314800 3  1   42
 .042500000 2353.69662 .045000002 2365.02466 .047499999 2379.458304800 3  1   43
 .050000001 2399.04366 .052499998 2422.16151 .055000000 2450.519444800 3  1   44
 .057500001 2481.52148 .059999999 2521.31213 .063000001 2569.398904800 3  1   45
 .066000000 2622.60408 .068999998 2682.53395 .071999997 2757.488904800 3  1   46
 .075999998 2853.88658 .079999998 2958.39422 .083999999 3076.093264800 3  1   47
 .088000000 3206.13870 .092000000 3350.11632 .096000001 3508.935544800 3  1   48
 .100000001 3705.58156 .104999997 3945.41328 .109999999 4209.616384800 3  1   49
 .115000002 4496.69776 .119999997 4881.48369 .127499998 5373.986404800 3  1   50
 .135000005 5876.81399 .142499998 6366.94877 .150000006 6853.068364800 3  1   51
 .159999996 7200.83169 .170000002 7239.14753 .180000007 6937.009264800 3  1   52
 .189999998 6352.50044 .200000003 5598.87078 .209999993 4800.688484800 3  1   53
 .219999999 4034.74925 .230000004 3356.45914 .239999995 2658.838644800 3  1   54
 .254999995 2016.93859 .270000011 1617.35818 .280000001 1275.170164800 3  1   55
 .300000012 956.926116 .319999993 738.196276 .340000004 579.5011124800 3  1   56
 .360000014 463.202190 .379999995 378.444865 .400000006 306.8630344800 3  1   57
 .425000012 246.386840 .449999988 200.535076 .474999994 165.1785714800 3  1   58
 .500000000 137.745030 .524999976 116.343794 .550000012 99.81595164800 3  1   59
 .574999988 87.2726063 .600000024 76.2313859 .629999995 66.32663664800 3  1   60
 .660000026 58.1385929 .689999998 51.3339442 .720000029 44.83185604800 3  1   61
 .759999990 38.9150369 .800000012 34.1811769 .839999974 30.26465974800 3  1   62
 .879999995 27.0299071 .920000017 24.3467777 .959999979 22.15907454800 3  1   63
 1.00000000 20.1132763 1.04999995 18.1891628 1.10000002 16.58395784800 3  1   64
 1.14999998 15.2326021 1.20000005 13.8636836 1.27499998 12.53649874800 3  1   65
 1.35000002 11.4658666 1.42499995 10.6000374 1.50000000 9.809550904800 3  1   66
 1.60000002 9.07523028 1.70000005 8.48518897 1.79999995 8.011156894800 3  1   67
 1.89999998 7.63533454 2.00000000 7.31824312 2.09999990 7.052632074800 3  1   68
 2.20000005 6.82792281 2.29999995 6.63194712 2.40000010 6.422780654800 3  1   69
 2.54999995 6.21564102 2.70000005 6.07775650 2.79999995 5.947554254800 3  1   70
 3.00000000 5.79948658 3.20000005 5.68080063 3.40000010 5.581048504800 3  1   71
 3.59999990 5.49524048 3.79999995 5.42388368 4.00000000 5.368349114800 3  1   72
 4.25000000 5.31239383 4.50000000 5.26703134 4.75000000 5.229646654800 3  1   73
 5.00000000 5.19226197 5.25000000 5.16042262 5.50000000 5.134456754800 3  1   74
 5.75000000 5.11071758 6.00000000 5.09427758 6.30000019 5.077305734800 3  1   75
 6.59999990 5.06033387 6.90000010 5.04336201 7.19999981 5.026856804800 3  1   76
 7.59999990 5.01236071 8.00000000 4.99790729 8.39999962 4.985242924800 3  1   77
 8.80000019 4.97745744 9.19999981 4.96994846 9.60000038 4.962439494800 3  1   78
 10.0000000 4.95399189 10.5000000 4.94460568 11.0000000 4.935219464800 3  1   79
 11.5000000 4.92656246 12.0000000 4.92066554 12.7500000 4.914255084800 3  1   80
 13.5000000 4.90784462 14.2500000 4.90143416 15.0000000 4.893959944800 3  1   81
 16.0000000 4.89933288 17.0000000 5.07749352 18.0000000 8.933653324800 3  1   82
 19.0000000 4.98804073 20.0000000 4.87941088 21.0000000 4.863028544800 3  1   83
 22.0000000 4.85746135 23.0000000 4.87063574 24.0000000 4.917284354800 3  1   84
 25.5000000 5.94445738 27.0000000 75.1737718 28.0000000 7.668585214800 3  1   85
 30.0000000 5.03958656 32.0000000 4.91129536 34.0000000 4.855363764800 3  1   86
 36.0000000 4.82451761 38.0000000 4.79704762 40.0000000 4.766143894800 3  1   87
 42.5000000 4.73180641 45.0000000 4.69746893 47.5000000 4.663131454800 3  1   88
 50.0000000 4.63278288 52.5000000 4.63140732 55.0000000 5.446688354800 3  1   89
 57.5000000 106.491363 60.0000000 6.28119653 63.0000000 13.84048894800 3  1   90
 66.0000000 36.6060943 69.0000000 5.20468098 72.0000000 4.804301954800 3  1   91
 76.0000000 4.64240995 80.0000000 7.53506247 84.0000000 42.95883634800 3  1   92
 88.0000000 170.588009 92.0000000 8.17224460 96.0000000 19.04447974800 3  1   93
 100.000000 8.02683261 105.000000 14.1968044 110.000000 5.315013094800 3  1   94
 115.000000 51.2187320 120.000000 57.0460427 127.500000 5.747503794800 3  1   95
 135.000000 9.72056905 142.500000 7.02178081 150.000000 8.330220964800 3  1   96
 160.000000 21.2493702 170.000000 5.27579426 180.000000 5.100755834800 3  1   97
 190.000000 21.1613051 200.000000 5.14300643 210.000000 11.68636414800 3  1   98
 220.000000 25.3065812 230.000000 19.5187065 240.000000 5.280161004800 3  1   99
 255.000000 11.1828494 270.000000 10.7891875 280.000000 10.79748984800 3  1  100
 300.000000 5.25674537 320.000000 5.33989774 340.000000 7.764123144800 3  1  101
 360.000000 6.09741115 380.000000 123.642035 400.000000 15.55537324800 3  1  102
 425.000000 15.4433666 450.000000 6.10070927 475.000000 6.039831004800 3  1  103
 500.000000 8.49148003 525.000000 10.0394565 550.000000 9.905870144800 3  1  104
 575.000000 8.42107229 600.000000 10.0872010 630.000000 5.136112944800 3  1  105
 660.000000 22.1294461 690.000000 5.51734153 720.000000 19.58187534800 3  1  106
 760.000000 6.00485425 800.000000 5.32265104 840.000000 13.50076114800 3  1  107
 880.000000 5.39921715 920.000000 12.2365042 960.000000 5.361230104800 3  1  108
 1000.00000 4.92355848 1050.00000 4.36700737 1100.00000 53.51459984800 3  1  109
 1150.00000 11.6025416 1200.00000 9.45657189 1275.00000 7.632092934800 3  1  110
 1350.00000 6.68594731 1425.00000 6.37515821 1500.00000 6.249648624800 3  1  111
 1600.00000 6.21277708 1700.00000 6.23799452 1800.00000 6.278176974800 3  1  112
 1900.00000 6.32503067 2000.00000 6.34389500 2100.00000 6.348446104800 3  1  113
 2200.00000 6.35299720 2300.00000 6.35779053 2400.00000 6.364660344800 3  1  114
 2550.00000 6.37295581 2700.00000 6.37986870 2800.00000 6.388164174800 3  1  115
 3000.00000 6.39922480 3200.00000 6.41028543 3400.00000 6.421346064800 3  1  116
 3600.00000 6.43240669 3800.00000 6.44346732 4000.00000 6.455863114800 3  1  117
 4250.00000 6.46855054 4500.00000 6.48078238 4750.00000 6.493014214800 3  1  118
 5000.00000 6.50524605 5250.00000 6.51747789 5500.00000 6.529709724800 3  1  119
 5750.00000 6.54194156 6000.00000 6.55539658 6300.00000 6.570074794800 3  1  120
 6600.00000 6.58475299 6900.00000 6.59943119 7200.00000 6.616555774800 3  1  121
 7600.00000 6.63612671 8000.00000 6.65569764 8400.00000 6.675268584800 3  1  122
 8800.00000 6.69429303 9200.00000 6.70000000 9600.00000 6.699972834800 3  1  123
 10000.0000 6.69866480 10500.0000 6.69659439 11000.0000 6.697671274800 3  1  124
 11500.0000 6.70391228 12000.0000 6.71180714 12750.0000 6.721280994800 3  1  125
 13500.0000 6.73075483 14250.0000 6.74238943 15000.0000 6.748304154800 3  1  126
 16000.0000 6.74496246 17000.0000 6.74163236 18000.0000 6.744436604800 3  1  127
 19000.0000 6.75238667 20000.0000 6.76033674 21000.0000 6.768286824800 3  1  128
 22000.0000 6.77623689 23000.0000 6.78418697 24000.0000 6.794516984800 3  1  129
 25500.0000 6.80916542 27000.0000 6.82169292 28000.0000 6.836725934800 3  1  130
 30000.0000 6.85447352 32000.0000 6.86500000 34000.0000 6.875000004800 3  1  131
 36000.0000 6.88500000 38000.0000 6.89500000 40000.0000 6.906250004800 3  1  132
 42500.0000 6.91875000 45000.0000 6.93125000 47500.0000 6.943750004800 3  1  133
 50000.0000 6.95625000 52500.0000 6.96875000 55000.0000 6.981250004800 3  1  134
 57500.0000 6.99375000 60000.0000 7.00750000 63000.0000 7.022500004800 3  1  135
 66000.0000 7.03750000 69000.0000 7.05250000 72000.0000 7.070000004800 3  1  136
 76000.0000 7.09000000 80000.0000 7.11000000 84000.0000 7.130000004800 3  1  137
 88000.0000 7.15000000 92000.0000 7.17000000 96000.0000 7.189784494800 3  1  138
 100000.000 7.19872065 105000.000 7.20167611 110000.000 7.204631574800 3  1  139
 115000.000 7.20758703 120000.000 7.21128135 127500.000 7.215714544800 3  1  140
 135000.000 7.22014773 142500.000 7.22458092 150000.000 7.229752974800 3  1  141
 160000.000 7.23566389 170000.000 7.24157481 180000.000 7.247485734800 3  1  142
 190000.000 7.25339665 200000.000 7.25930757 210000.000 7.265218494800 3  1  143
 220000.000 7.27112941 230000.000 7.27704033 240000.000 7.276246634800 3  1  144
 255000.000 7.26874831 270000.000 7.26249972 280000.000 7.255001404800 3  1  145
 300000.000 7.25034797 320000.000 7.25068470 340000.000 7.250161134800 3  1  146
 360000.000 7.25053822 380000.000 7.25041933 400000.000 7.250249054800 3  1  147
 425000.000 7.24655811 450000.000 7.23604347 475000.000 7.212445804800 3  1  148
 500000.000 7.16191677 525000.000 7.09024850 550000.000 7.025511384800 3  1  149
 575000.000 6.97525235 600000.000 6.92046648 630000.000 6.862116574800 3  1  150
 660000.000 6.82499939 690000.000 6.79499864 720000.000 6.759997764800 3  1  151
 760000.000 6.71999675 800000.000 6.67999575 840000.000 6.639994744800 3  1  152
 880000.000 6.59999374 920000.000 6.55999273 960000.000 6.519991724800 3  1  153
 1000000.00 6.40005502 1100000.00 6.20018262 1200000.00 6.002167184800 3  1  154
 1300000.00 5.84242028 1400000.00 5.81242153 1500000.00 5.810578904800 3  1  155
 1600000.00 5.72230744 1700000.00 5.60712633 1800000.00 5.499628614800 3  1  156
 1900000.00 5.39988226 2000000.00 5.33750283 2100000.00 5.312490324800 3  1  157
 2200000.00 5.22498922 2300000.00 5.07499951 2400000.00 4.942505054800 3  1  158
 2500000.00 4.82750584 2600000.00 4.73417186 2700000.00 4.662503124800 3  1  159
 2800000.00 4.59083437 2900000.00 4.51750134 3000000.00 4.451488054800 3  1  160
 3100000.00 4.39445882 3200000.00 4.33915155 3300000.00 4.291018634800 3  1  161
 3400000.00 4.24367495 3500000.00 4.20600307 3600000.00 4.178003004800 3  1  162
 3700000.00 4.15000293 3800000.00 4.12200286 3900000.00 4.094002794800 3  1  163
 4000000.00 4.07400264 4100000.00 4.06200241 4200000.00 4.050002184800 3  1  164
 4300000.00 4.03800195 4400000.00 4.02600172 4500000.00 4.018390094800 3  1  165
 4600000.00 4.01516708 4700000.00 4.01194407 4800000.00 4.008721064800 3  1  166
 4900000.00 4.00549805 5000000.00 4.00227504 5100000.00 4.000068704800 3  1  167
 5200000.00 4.00000020 5300000.00 4.00070831 5400000.00 4.002459014800 3  1  168
 5500000.00 4.00421901 5600000.00 4.00597901 5700000.00 4.007739014800 3  1  169
 5800000.00 4.00955363 5900000.00 4.01237828 6000000.00 4.015582474800 3  1  170
 6100000.00 4.01878665 6200000.00 4.02199084 6300000.00 4.025195034800 3  1  171
 6400000.00 4.02839922 6500000.00 4.03500109 6600000.00 4.045000644800 3  1  172
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 12100000.0 .002770002 12200000.0 .002750000 12300000.0 .0027299984800 3102  191
 12400000.0 .002709995 12500000.0 .002679995 12600000.0 .0026399984800 3102  192
 12700000.0 .002600000 12800000.0 .002560002 12900000.0 .0025200054800 3102  193
 13000000.0 .002490006 13100000.0 .002470006 13200000.0 .0024500064800 3102  194
 13300000.0 .002430006 13400000.0 .002410006 13500000.0 .0023900064800 3102  195
 13600000.0 .002370006 13700000.0 .002350006 13800000.0 .0023300064800 3102  196
 13900000.0 .002310006 14000000.0 .002290007 14100000.0 .0022700074800 3102  197
 14200000.0 .002250007 14300000.0 .002230007 14400000.0 .0022100074800 3102  198
 14500000.0 .002190007 14600000.0 .002170007 14700000.0 .0021500074800 3102  199
 14800000.0 .002130007 14900000.0 .002110007 15000000.0 .0021000074800 3102  200
 15100000.0 .002100007 15200000.0 .002100007 15300000.0 .0021000064800 3102  201
 15400000.0 .002100006 15500000.0 .002100006 15600000.0 .0021000064800 3102  202
 15700000.0 .002100006 15800000.0 .002100006 15900000.0 .0021000054800 3102  203
 16000000.0 .002100005 16100000.0 .002100005 16200000.0 .0021000054800 3102  204
 16300000.0 .002100005 16400000.0 .002100005 16500000.0 .0021000044800 3102  205
 16600000.0 .002100004 16700000.0 .002100004 16800000.0 .0021000044800 3102  206
 16900000.0 .002100004 17000000.0 .002100004 17100000.0 .0021000034800 3102  207
 17200000.0 .002100003 17300000.0 .002100003 17400000.0 .0021000034800 3102  208
 17500000.0 .002100003 17600000.0 .002100003 17700000.0 .0021000034800 3102  209
 17800000.0 .002100002 17900000.0 .002100002 18000000.0 .0021000024800 3102  210
 18100000.0 .002100002 18200000.0 .002100002 18300000.0 .0021000024800 3102  211
 18400000.0 .002100001 18500000.0 .002100001 18600000.0 .0021000014800 3102  212
 18700000.0 .002100001 18800000.0 .002100001 18900000.0 .0021000014800 3102  213
 19000000.0 .002100000 19100000.0 .002100000 19200000.0 .0021000004800 3102  214
 19300000.0 .002100000 19400000.0 .002100001 19500000.0 .0021000014800 3102  215
 19600000.0 .002100002 19700000.0 .002100003 19800000.0 .0021000034800 3102  216
 19900000.0 .002100004 20000000.0 0.0                             4800 3102  217
                                                                  4800 3  099999
                                                                  4800 0  0    0
                                                                     0 0  0    0
 4.91150E+4 1.13917E+2          0          0         34         104931 1451    1
 0.0        0.0                 0          0          0          64931 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20024931 1451    3
 3.00000E+2 0.0                 1          0        403         114931 1451    4
 49-In-115 FEI/CNDC   EVAL-Mar03 Zolotarev,Dunjiu,Schmittroth     4931 1451    5
                      DIST-Feb2004                                4931 1451    6
----IRDF-2002         MATERIAL 4931                               4931 1451    7
-----INCIDENT NEUTRON DATA                                        4931 1451    8
------ENDF-6 FORMAT                                               4931 1451    9
***************************************************************** 4931 1451   10
 49-In-115 FEI        EVAL-Mar03 K.I.Zolotarev                    4931 1451   11
                      DIST-Apr03                                  4931 1451   12
----BROND-2           MATERIAL 4931                               4931 1451   13
-----INCIDENT NEUTRON DATA                                        4931 1451   14
------ENDF-6 FORMAT                                               4931 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    4931 1451   16
***************************************************************** 4931 1451   17
Authors of evaluation: K.I.Zolotarev and P.K.Zolotarev            4931 1451   18
***************************************************************** 4931 1451   19
MF=3                                                              4931 1451   20
MT= 51 - In115(n,n')In115m  reaction                              4931 1451   21
-------------------------------------                             4931 1451   22
 *****************************************************************4931 1451   23
 CHINESE EVALUATION OF (N,2N) REACTION ADDED AT NDS               4931 1451   24
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451   25
                                                                  4931 1451   26
THE FOLLOWING FILE SECTIONS ARE INCLUDED -                        4931 1451   27
     MF= 1    GENERAL INFORMATION (MT=451)                        4931 1451   28
     MF= 8    RADIOACTIVITY DATA (MT=51)                          4931 1451   29
     MF=10    CROSS SECTION FOR RADIOACTIVE NUCLIDE               4931 1451   30
                PRODUCTION (MT=51)                                4931 1451   31
     MF=40    DATA COVARIANCES FOR RADIOACTIVE NUCLIDE            4931 1451   32
                PRODUCTION (MT=51)                                4931 1451   33
49-IN-115  CNDC/CIAE  EVAL-JUN91 CAI DUNJIU AND WANG ZISHENG      4931 1451   34
---ENDF-6 FORMAT      4931                  REVISION 0            4931 1451   35
                                                                  4931 1451   36
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451   37
 *****************************************************************4931 1451   38
 49-IN-115 HEDL,ANL   EVAL-MAR90 F.SCHMITTROTH,D.L.SMITH,S.CHIBA  4931 1451   39
                      DIST-JUN90                       19900329   4931 1451   40
----ENDF/B-VI         MATERIAL 4931                               4931 1451   41
 MF=2 MT=151   EVALUATION OF RESOLVED RESONANCE PARAMETERS        4931 1451   42
              BASED ON NEW BNL-325, REF(2).                       4931 1451   43
 MF=3 MT=102  VERSION-V UNRESOLVED REGION CONTAINS ADJUSTED DATA  4931 1451   44
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4931 1451   45
DOSIMETRY                                                         4931 1451   46
******************************************************************4931 1451   47
***************************************************************** 4931 1451   48
**********   Start of (N,2N) bibliographical component ********** 4931 1451   49
***************************************************************** 4931 1451   50
                                                                  4931 1451   51
      Evaluation of the 115-In(n,2n) 114m-In Reaction             4931 1451   52
                 Cross-section                                    4931 1451   53
           Cai Dunjiu Yu Baosheng Wang Zisheng                    4931 1451   54
                Lu Hanlin Zhao Wenrong                            4931 1451   55
          Institute of Atomic Energy, China                       4931 1451   56
The excitation function of 115-In(n, 2n) 114m-In reaction         4931 1451   57
covers neutron energy range from threshold of 9.228 MeV           4931 1451   58
( including the energy of isomeric state which has                4931 1451   59
0.190 MeV ) to 20 MeV. Experimental knowledge of the              4931 1451   60
115-In(n,2n) reaction cross sections is entirely based            4931 1451   61
on the results of activation measurements. There are              4931 1451   62
still no experimental results obtained by                         4931 1451   63
direct-neutron-detection methods (such as scintillation           4931 1451   64
tank). For both the indium isotopes (115-In,0.957,                4931 1451   65
113-In,0.043), the primary activity                               4931 1451   66
resulting from the (n,2n) process is due to the decay of          4931 1451   67
metastable state. The interaction with the primary isotope,       4931 1451   68
115-In, results in a metastable state in 114-In which             4931 1451   69
decays with 49.5d half-life by means of an E4 transition          4931 1451   70
to the ground state (1+) with a half-life of 71.9s.               4931 1451   71
The (n,2n) process also directly populates the ground state.      4931 1451   72
Seventeen sets of data available (1-18) were collected.           4931 1451   73
For the sake of comparison, all the experimental results were     4931 1451   74
adjusted by the unified nuclear parameters (including             4931 1451   75
intensity of r-line, half-life, branching ratio),                 4931 1451   76
the reference cross section and the dependence of cross           4931 1451   77
section on energy which were taken from (Ref.1). In several       4931 1451   78
cases, adjustments were made only for the dependence of cross     4931 1451   79
section on energy since some necessary parameters used in data    4931 1451   80
analysis were not given by the authors.                           4931 1451   81
  The evaluation was made as the following ways:                  4931 1451   82
 (1).At 14.7MeV neutron energy .                                  4931 1451   83
  Based on the results measured by Ge(Li) detector,the            4931 1451   84
recommended cross section at 14.7 MeV is 1290 mb.                 4931 1451   85
 (2). For the neutron energy range from threshold to 20 MeV.      4931 1451   86
  The recommended excitation function was obtained                4931 1451   87
by fitting the measured data with least-square method in the      4931 1451   88
neutron energy range of 10.4-20MeV and by extrapolating from      4931 1451   89
10.4MeV to 9.228MeV based on the physical trend and systematics   4931 1451   90
calculation.                                                      4931 1451   91
Covariance matrix is given for the evaluated data considering all 4931 1451   92
adjusted factors.                                                 4931 1451   93
                      References                                  4931 1451   94
  1.Zhao Wenrong et al., CNDC-89014;INDC(CPR)-16, 1989            4931 1451   95
  2.Ke Wei et al., Chin.J.Nucl.Phys.11, 3, 11(1989)               4931 1451   96
  Lu Hanlin et al., INDC(CPR)-011/GI, P67(1988)                   4931 1451   97
  3.J.Csikai et al., INDC(NDS)-232/L, P45(1989)                   4931 1451   98
  4.Li Jiangwei et al.,  Chin.J.Nucl.Phys., 10, 1, 52(1988)       4931 1451   99
  Wu Zhihua et al., 88MITO, P315(1988)                            4931 1451  100
  5.T.B.Ryves et al., J.Phys., G9, 1549(1983)                     4931 1451  101
  6.T.B.Ryves et al., J.Phys., G7, 115(1981)                      4931 1451  102
  7.A.Reggoug et al.,  82Antwerp, P873(1982);NIMA, 227, 249(1984) 4931 1451  103
  8.K.Kayashima et al.,  NEANDC(J)-61U, P94(1979)                 4931 1451  104
  9.D.C.Santry et al.,  Can.J.Phys., 54, 757(1976)                4931 1451  105
  10.Lu Hanlin et al.,  At.Energy Sci.Technol., 2, 113(1975)      4931 1451  106
  11.A.Paulsen et al.,  Atomkernenergie, 26, 34(1975)             4931 1451  107
  12.J.K.Temperley et al.,  BRL-1491(1970)                        4931 1451  108
  13.R.C.Barrall et al.,  Nucl.Phys., A138, 387(1969)             4931 1451  109
  14.R.C.Barrall et al., AFWL-TR-68-134(1969)                     4931 1451  110
  15.H.Rotzer, Nucl.Phys., A109, 694(1968);DWA176, 289(1968)      4931 1451  111
  16.B.Minetti et al.,  Z.Physik., A217, 83(1968)                 4931 1451  112
  17.H.O.Menlove et al., Phys.Rev., 163, 1308(1967)               4931 1451  113
  18.R.J.Prestwood et al.,  Phys.Rev., 121, 1438(1961)            4931 1451  114
  19.T.Kozlowski et al.,  Acta.Phys.Pol., 33, 409(1968)           4931 1451  115
  20.R.Prasad et al.,Nucl.Phys., A94, 476(1967)                   4931 1451  116
  and 88,349(1966).                                               4931 1451  117
  21.W.Nagel, JNE, 20, 475(1966)                                  4931 1451  118
  22.K.C.Garg et al.,IPA17, 525(1979)                             4931 1451  119
  23.G.N.Salaita et al.,  ANS, 16, 59(1973)                       4931 1451  120
  24.J.Janczyszyn et al.,  J.Radiational Chem., 14, 201(1973)     4931 1451  121
  25.M.Bormann et al.,  EANDC(E)76u, 51(1967)                     4931 1451  122
  26.W.Grochulski et al., INR-1172(1970);INR-1197, 10(1970)       4931 1451  123
  Acta.Phys.Pol., BI, 271(1970)                                   4931 1451  124
  27.H.K.Vonach et al.,  68WASH, 2, P885(1968)                    4931 1451  125
  28.Wang Zisheng et al., Research on the Covariances Matrix      4931 1451  126
  of the Evaluation Data(to be published)                         4931 1451  127
                                                                  4931 1451  128
***************************************************************** 4931 1451  129
**********   End of (N,2N) bibliographical component   ********** 4931 1451  130
================================================================= 4931 1451  131
                                                                  4931 1451  132
***************************************************************** 4931 1451  133
**********   Start of (N,G) bibliographical component  ********** 4931 1451  134
***************************************************************** 4931 1451  135
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451  136
 *         *          *          *          *          *         *4931 1451  137
 CAPTURE TO 54 MIN. ISOMERIC STATE DESCRIPTION MODIFIED BY        4931 1451  138
 R. SCHENTER ON 2/20/84.  THIS WAS DONE BY ADDING FILE9 WITH      4931 1451  139
 Y=.79 AND PUTTING THE TOTAL CAPTURE WIDTH IN FILE2 AND THE TOTAL 4931 1451  140
 CAPTURE CROSS SECTION IN FILE3.                                  4931 1451  141
 P.C.TO NORMALIZATION+STANDARDS SUBCOMITTEE (N,G)F.SCHMITTROTH    4931 1451  142
                                                 MF=2 MT=151      4931 1451  143
                                                 MF=2 MT=102      4931 1451  144
         *          *          *          *         *             4931 1451  145
                                                                  4931 1451  146
FILE INFORMATION                                                  4931 1451  147
                                                                  4931 1451  148
MF=1 MT=451   ATOMIC MASS FROM REF(1).                            4931 1451  149
                                                                  4931 1451  150
MF=2 MT=151   EVALUATION OF RESOLVED RESONANCE PARAMETERS         4931 1451  151
              BASED ON NEW BNL-325, REF(2).                       4931 1451  152
 MF=3 MT=102  VERSION-V UNRESOLVED REGION CONTAINS ADJUSTED DATA  4931 1451  153
              SEE DOCUMENTATION                                   4931 1451  154
              RADIATIVE NEUTRON CAPTURE TO THE IN 116M(54 MIN.)   4931 1451  155
              STATE.                                              4931 1451  156
              E  GREATER THAN  EH,                                4931 1451  157
              EVALUATION BASED ON EXPERIMENTAL DATA, REF.(3-7)    4931 1451  158
              AND THEORETICAL CALCULATIONS, REF.(8,9).            4931 1451  159
              E  LESS THAT  EH,                                   4931 1451  160
              A   1/V   COMPONENT WAS ADDED TO GIVE THE CORRECT   4931 1451  161
              2200M/S CROSS SECTION TO THE  54  MIN. STATE(THE    4931 1451  162
              2.2  SEC. STATE CROSS SECTION WAS INCLUDED).        4931 1451  163
     RADIATIVE CAPTURE TO THE  2.2  SEC. STATE OF IN 116 WAS      4931 1451  164
     INCLUDED AS PART OF THE CAPTURE TO THE  54  MIN. STATE       4931 1451  165
     FOR BOTH THERMAL AND FAST ENERGIES.                          4931 1451  166
             RESULTS WERE DIVIDED BY .79 TO GIVE THE TOTAL CAP-   4931 1451  167
             TURE CROSS SECTION IN FILE3.  FILE9 COMBINED WITH    4931 1451  168
             FILE3 IS REQUIRED TO GIVE CAPTURE TO 54 MIN.         4931 1451  169
             ISOMERIC STATE.                                      4931 1451  170
                                                                  4931 1451  171
2200M/S CAPTURE CROSS SECTION,BARNS TO THE 54 MIN. STATE          4931 1451  172
  (FROM RESONANCE PARAMETERS) = 166.413                           4931 1451  173
                                                                  4931 1451  174
COMPUTED RESONANCE INTEGRAL   =2587.345                           4931 1451  175
                                                                  4931 1451  176
REFERENCES.                                                       4931 1451  177
1.  A.H.WAPSTRA AND N.B.GOVE,NUCL. DATA TABLES,VOL.9,PART 1(1971).4931 1451  178
2.  S.F.MUGHABGHAB AND D.I.GARBER,BNL-325,3RD ED.,VOL.1(1973)     4931 1451  179
3.  H.A.GRENCH AND H.O.MENLOVE,PHYS.REV.,VOL.165(1968)1298.       4931 1451  180
4.  H.O.MENLOVE,ET AL.,PHYS.REV.,VOL.163(1967)1299.               4931 1451  181
5.  S.A.COX, PHYS.REV.,VOL.133(1964)B378.                         4931 1451  182
6.  A.E.JOHNSRUD,ET AL.,PHYS.REV.,VOL.116(1959)927.               4931 1451  183
7.  G.PETO ET AL., J.NUCL.EN.,VOL.21(1967)797.                    4931 1451  184
8.  F.SCHMITTROTH, HEDL-TME 71-106(AUGUST 1971).                  4931 1451  185
9.  F.SCHMITTROTH, HEDL-TME 73-79,ENDF-195(NOVEMBER 1973).        4931 1451  186
***************************************************************** 4931 1451  187
**********             (N,G) processing details        ********** 4931 1451  188
***************************************************************** 4931 1451  189
 Data Linearized to Within an Accuracy of .100000000 per-cent     4931 1451  190
 ***************** Program RECENT (VERSION 2002-1) ***************4931 1451  191
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4931 1451  192
 Data Linearized to within an Accuracy of .100000000 per-cent     4931 1451  193
 ***************** Program SIGMA1 (VERSION 2002-1) ***************4931 1451  194
 Data Doppler Broadened to 300.000000 Kelvin                      4931 1451  195
 for All Data Greater than 1.0000E-10 barns in Absolute Value     4931 1451  196
 Data Linearized to Within an Accuracy pf .100000000 per-cent     4931 1451  197
 ***************** Program FIXUP (Version 2002-1) ****************4931 1451  198
 Corrected ZA/AWR in All Sections-----------------------------Yes 4931 1451  199
 Corrected Thresholds-----------------------------------------Yes 4931 1451  200
 Extended Cross Sections to 20 MeV----------------------------No  4931 1451  201
 Allow Cross Section Deletion---------------------------------No  4931 1451  202
 Allow Cross Section Reconstruction---------------------------No  4931 1451  203
 Make All Cross Sections Non-Negative-------------------------Yes 4931 1451  204
 Delete Energies Not in Ascending Order-----------------------Yes 4931 1451  205
 Deleted Duplicate Points-------------------------------------Yes 4931 1451  206
 Check for Ascending MAT/MF/MT Order--------------------------Yes 4931 1451  207
 Check for Legal MF/MT Numbers--------------------------------Yes 4931 1451  208
 Allow Creation of Missing Sections---------------------------No  4931 1451  209
 Allow Insertion of Energy Points-----------------------------No  4931 1451  210
 Create Uniform Energy Grid-----------------------------------No  4931 1451  211
 Delete Section if Cross Section =0 at All Energies-----------Yes 4931 1451  212
 *************** PROGRAM ACTIVATE (VERSION 2002-1) ***************4931 1451  213
 MF=10 Activation Cross Sections Defined by Combining MF=3        4931 1451  214
 Cross Sections and MF=9 Multipliers. MF=9 Deleted.               4931 1451  215
***************************************************************** 4931 1451  216
 The metastable state component (MF/MT=10/102) was extracted from 4931 1451  217
 the ACTIVATE output and merged with the other reactions in this  4931 1451  218
 In-115 evaluation. MF/MT=33/102 was adapted as MF/MT=40/102.     4931 1451  219
***************************************************************** 4931 1451  220
**********    End of (N,G) bibliographical component   ********** 4931 1451  221
================================================================= 4931 1451  222
**********  Start of (N,N') bibliographical component  ********** 4931 1451  223
***************************************************************** 4931 1451  224
------Russian Reactor Dosimetry File RRDF-2002                    4931 1451  225
***************************************************************** 4931 1451  226
Authors of evaluation: K.I.Zolotarev and P.K.Zolotarev            4931 1451  227
***************************************************************** 4931 1451  228
MF=3                                                              4931 1451  229
MT= 51 - In115(n,n')In115m  reaction                              4931 1451  230
-------------------------------------                             4931 1451  231
    In the section MT= 51 are given evaluated  cross section data 4931 1451  232
of neutron inelastic excitation of the  4.486-hour isomeric state 4931 1451  233
in the  indium-115  in the energy range from threshold to 20 MeV. 4931 1451  234
The isomeric level has energy  336.24 keV  with spin  and  parity 4931 1451  235
1/2- [1].                                                         4931 1451  236
    Microscopic experimental data  [2-40]  were  analyzed in  the 4931 1451  237
process of preparation  of input data base  for the evaluation of 4931 1451  238
cross sections and their uncertainty  for the In-115(n,n')In-115m 4931 1451  239
reaction.  During this procedure all experimental data  if it was 4931 1451  240
possible were corrected to the new recommended cross section data 4931 1451  241
for monitor reactions used in the measurements and to the new re- 4931 1451  242
commended decay data.                                             4931 1451  243
    Special correction was done with experimental data [5], [6],  4931 1451  244
[12], [24], [25] and [27].                                        4931 1451  245
    Grench and Menlove data [5]  and  Kimura et al. data [6] bet- 4931 1451  246
ween 0.5 - 0.9 MeV obtained  in  the measurements with  T(p,n)He3 4931 1451  247
neutron source were renormalized to the integral of Liskien et al.4931 1451  248
experimental data [16] in the overlapping energy ranges. Original 4931 1451  249
cross section data  from ref. [5] and [6]  were multiplied to the 4931 1451  250
correction factors Fc=1.15268 and Fc=0.92486 , respectively.      4931 1451  251
    Data of Santry and Butler [12] obtained in the absolute measu-4931 1451  252
rements with T(p,n)He3 source in the energy range 0.348-5.130 MeV 4931 1451  253
were renormalized  to the integral of Liskien et al. experimental 4931 1451  254
data [16] in the energy interval 1.85-4.07 MeV, Fc= 1.0516        4931 1451  255
    Cross section data measured by Zhao Wenrong et al. [24]  were 4931 1451  256
renormalized also to the experimental data of Liskien et al. [16] 4931 1451  257
in the overlapping energy ranges.  All original experimental data 4931 1451  258
from ref. [24]  except cross section value  at  the  energy point 4931 1451  259
En=8.5 MeV were multiplied to the factor Fc=1.065 .               4931 1451  260
    Experimental data of Kimura et al. [6] in the energy interval 4931 1451  261
1.8-4.6 MeV and experimental data of Santry and Butler [12] obta- 4931 1451  262
ined relative to the S-32(n,p)P-32 standard were not corrected.   4931 1451  263
    Data of Zhao Wenrong et al. [24] for the energy point 8.5 MeV 4931 1451  264
was corrected  to the recommended cross section value for monitor 4931 1451  265
tor reaction Al-27(n,a)Na-24 from ref. [41].                      4931 1451  266
    Cross section data for the In-115(n,n')In-115m reaction measu-4931 1451  267
red by Lu Hanlin et al. [25] and by Csikai et al. [27] were renor-4931 1451  268
malized to the integral of Konno et al. [30] and Filatenkov et al.4931 1451  269
[31] experimental data in the overlapping energy interval 13.54 - 4931 1451  270
14.78 MeV . Original data from ref. [25] and [27] were multiplied 4931 1451  271
to the correction factors Fc=1.13622 and Fc=1.08624, respectively.4931 1451  272
    Excitation function for the In-115(n,n')In-115m  reaction  in 4931 1451  273
the energy region from threshold to 20 MeV was evaluated by means 4931 1451  274
of statistical analysis of experimental cross section data [2-31].4931 1451  275
    Experimental cross section data [32-40] were rejected  due to 4931 1451  276
their discrepancy with the main bulk of experimental data [2-31]. 4931 1451  277
Data of Martin et al. [2] in the energy interval  4.55 - 5.26 MeV 4931 1451  278
were not taken into account in the evaluation due to their syste- 4931 1451  279
matic underestimation In-115(n,n')In-115m reaction cross section. 4931 1451  280
In the rejected experiments [33-38] the cross section values were 4931 1451  281
measured only in a one energy point in the interval 14 - 15 MeV.  4931 1451  282
    Statistical analysis of input cross section data was carried  4931 1451  283
out by means of PADE-2 code [42].  Rational function was used as  4931 1451  284
the model function [43].                                          4931 1451  285
     U-235 thermal fission [44] and  Cf-252 spontaneous  fission  4931 1451  286
neutron spectra [45] averaged cross sections calculated from the  4931 1451  287
the evaluated In-115(n,n')In-115m  excitation function  are  the  4931 1451  288
following:                                                        4931 1451  289
                                                                  4931 1451  290
  4931 1451  291
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  4931 1451  292
  4931 1451  293
 U-235 neutron fission     188.40         188.2 +- 2.3    [46]  4931 1451  294
  4931 1451  295
 Cf-252 spont. fission     191.66         197.4 +- 2.704  [47]  4931 1451  296
  4931 1451  297
                                                                  4931 1451  298
MT=33                                                             4931 1451  299
MT= 51 -(n,n') cross section cov. matrix                          4931 1451  300
----------------------------------------                          4931 1451  301
     Uncertainties in the evaluated excitation function  for  the 4931 1451  302
reaction  In-115(n,n')In-115m  are given  in the form of relative 4931 1451  303
covariance matrix for the 39-neutron energy groups (LB=5).  Cova- 4931 1451  304
riance matrix of uncertainties was calculated simultaneously with 4931 1451  305
recommended cross section data by means of PADE-2 code.           4931 1451  306
    Eigenvalues  of the  6-th digits  relative covariance matrix  4931 1451  307
given in the 33-file are the following:                           4931 1451  308
                                                                  4931 1451  309
    7.55059E-08    8.01529E-08    8.14328E-08    8.29955E-08      4931 1451  310
    8.51539E-08    8.79248E-08    8.88394E-08    9.29091E-08      4931 1451  311
    9.80564E-08    1.06991E-07    1.19646E-07    1.34061E-07      4931 1451  312
    1.46033E-07    1.71437E-07    2.22942E-07    2.66525E-07      4931 1451  313
    4.04740E-07    7.05147E-07    1.52953E-06    2.70059E-06      4931 1451  314
    2.95312E-06    3.08776E-06    6.35038E-06    4.26321E-04      4931 1451  315
    6.81158E-04    9.21024E-04    9.54240E-04    1.07694E-03      4931 1451  316
    1.11466E-03    1.28566E-03    1.45684E-03    1.62008E-03      4931 1451  317
    1.97248E-03    4.10930E-03    5.75040E-03    7.29359E-03      4931 1451  318
    1.00269E-02    1.64825E-02    2.00540E-02                     4931 1451  319
                                                                  4931 1451  320
References:                                                       4931 1451  321
 1. R.B.Firestone   Table of Isotopes, Eighth edition, Vol. 1,    4931 1451  322
    John Wiley & Sons, Inc., New York, 1995                       4931 1451  323
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 3. H.O.Menlove, K.L.Coop, H.A.Grench, R.Sher  Phys. Rev., v.163, 4931 1451  325
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 4. P.Bornemisza-Pauspertl et al. Atomki Koezlemenyek, v.10, No.2,4931 1451  327
    p.112, July 1968                                              4931 1451  328
 5. H.A.Grench, H.O.Menlove  Physical Review, v.165, p.1298, 1968 4931 1451  329
 6. I.Kimura et al.  Journal of Nucl. Science and Technology, v.6,4931 1451  330
    p.485, September 1969                                         4931 1451  331
 7. R.C.Barrall et al. Report AFWL-TR-68-134, Albuquerque, NM,    4931 1451  332
    March 1969 ;                                                  4931 1451  333
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 9. L.Lakosi, A.Veres  2nd Nat'l Soviet Conf. on Neutron Physics, 4931 1451  336
    Kiev, v.4, p.312, May 1973                                    4931 1451  337
10. K.Kobayashi et al. J. Nucl. Energ., v.27, p.741, October 1973 4931 1451  338
11. D.L.Smith, J.W.Meadows Report ANL-NDM-14, Argonne, July 1975; 4931 1451  339
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12. D.C.Santry, J.P.Butler  Can. J. Phys., v.54, p.757, 1976      4931 1451  341
13. C.G.Hudson, W.L.Alford  Bull. Amer. Phys. Soc., v.21,         4931 1451  342
    p.188(DB5), February 1976                                     4931 1451  343
14. G.Magnusson, I.Bergqvist  Nuclear Technology, v.34, p.114,    4931 1451  344
    June 1977                                                     4931 1451  345
15. S.Yamamoto et al.  Report NEANDC(J)-56, p.25, September 1978  4931 1451  346
16. H.Liskien et al. Nucl. Sci. Eng., v.67, p.334, September 1978 4931 1451  347
17. P.Andersson et al.  Report LUNF-D6-3021, University of Lund,  4931 1451  348
    November 1978                                                 4931 1451  349
18. C.F.Ai, J.C.Chou  Nuclear Science, Taiwan, v.16, no.3, p.157, 4931 1451  350
    September 1979                                                4931 1451  351
19. L.Adamski et al.  Annals of Nucl. Energy, v.7, p.397, 1980    4931 1451  352
20. Fan Pei-Guo et al.  Chinese J. of Nuclear Physics, v.2, No.4, 4931 1451  353
    p.337, November 1980                                          4931 1451  354
21. V.L.Demekhin et al.    6th All Union Conference on Neutron    4931 1451  355
    Physics, Kiev, 2 - 6 October, v.3, p.195, 1983                4931 1451  356
22. T.B.Ryves et al.  J. of Physics, pt.G, v.9, p.1549, Dec. 1983 4931 1451  357
23. K.Kudo et al.  Report NEANDC(J)-106/U, p.1, September 1984    4931 1451  358
24. Zhao Wenrong, Lu Hanlin et al. Report INDC(CPR)-16, Sep. 1989 4931 1451  359
25. Lu Hanlin et al.  Chinese J. of Nuclear Physics, v.11, n.2,   4931 1451  360
    p.53, 1989                                                    4931 1451  361
26. I.Kimura, K.Kobayashi  Nucl. Sci. Eng., v.106, p.332, 1990    4931 1451  362
27. J.Csikai et al.  Zeitschrift fuer Physik, v.A337, p.39, 1990  4931 1451  363
28. N.N.Moiseev et al. Atomnaja Energija, v.68, February 1990     4931 1451  364
29. Y.Ikeda et al.  Proc. of an Int. Conf. Nuclear Data for Sci-  4931 1451  365
    ence and Technology, Julich, FRG, 13-17 May 1991, Springer-   4931 1451  366
    Verlag, 1992, pp.294-296                                      4931 1451  367
30. C.Konno et al.  Report JAERI-1329, October 1993               4931 1451  368
31. A.A.Filatenkov et al. Report RI-252, St. Petesburg, May 1999; 4931 1451  369
    A.A.Filatenkov et al. VANT, Ser.:Yadernye Konstanty, v.2, p.8,4931 1451  370
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32. S.G.Cohen   Nature, v.161, p.475, March 1948                  4931 1451  372
33. W.Nagel  EXFOR 20198.016 , December 1966                      4931 1451  373
34. H.Roetzer  Nucl. Phys., v.A109, p.694, March 1968             4931 1451  374
35. B.Minetti, A.Pasquarelli  Zeitschrift f. Physik, v.217, p.83, 4931 1451  375
    October 1968                                                  4931 1451  376
36. I.Garlea et al. Rev. Roum. Phys., v.29, p.421, 1984           4931 1451  377
37. R.Pepelnik et al. Report NEANDC(E)-262U, No.5,p.32, June 1985 4931 1451  378
38. I.Garlea et al. Rev. Roum. Phys., v.37, no.1, pp.19-25, 1992  4931 1451  379
39. J.Csikai, P.Raics  EXFOR 30983.002 July 1992                  4931 1451  380
40. N.I.Molla et al.  EXFOR 30984.002                             4931 1451  381
41. H.Vonach in "Nuclear Data Standards for Nuclear Measurements",4931 1451  382
    Report NEANDC-311 U, pp.75-77, OECD, Paris, 1992. ;           4931 1451  383
    M.Wagner et al. Evaluation of cross sections for 14 important 4931 1451  384
    neutron-dosimetry reactions. Physics Data No.13-5, 1990       4931 1451  385
42. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          4931 1451  386
43. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 4931 1451  387
    st's Meeting on Evaluation and Processing of Covariance Data, 4931 1451  388
    Oak Ridge, USA, 1992, OECD, Paris, 1993, p.105                4931 1451  389
44. L.W.Weston et al.  Evaluated Neutron Data  for  Uranium-235,  4931 1451  390
    ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989    4931 1451  391
45. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        4931 1451  392
46. W.Mannhart  Prog. Report INDC(Ger)-045, pp.40-43, June 1999   4931 1451  393
47. W.Mannhart  Validation of Differential Cross Sections with    4931 1451  394
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 4931 1451  395
    September 2002                                                4931 1451  396
***************************************************************** 4931 1451  397
**********   End of (N,N') bibliographical component   ********** 4931 1451  398
================================================================= 4931 1451  399
                                                                  4931 1451  400
                                                                  4931 1451  401
                                                                  4931 1451  402
                                                                  4931 1451  403
***************************************************************** 4931 1451  404
 ***************** Program GROUPIE (VERSION 2002-1) **************4931 1451  405
 Unshielded Group Averages Using  640 Groups                      4931 1451  406
 Weighting Spectrum: Flat (Constant) Spectrum                     4931 1451  407
                                1        451        418          14931 1451  408
                                2        151          4          14931 1451  409
                                8          4          2          14931 1451  410
                                8         16          2          14931 1451  411
                                8        102          2          14931 1451  412
                               10          4         75          14931 1451  413
                               10         16         40          14931 1451  414
                               10        102        217          14931 1451  415
                               40          4        148          14931 1451  416
                               40         16         24          14931 1451  417
                               40        102          7          04931 1451  418
                                                                  4931 1  099999
                                                                  4931 0  0    0
 4.91150E+4 1.13917E+2          0          0          1          04931 2151    1
 4.911500+4 1.000000+0          0          0          1          04931 2151    2
 1.000000-5 2.000000+7          0          0          0          04931 2151    3
 4.500000+0 6.550000-1          0          0          0          04931 2151    4
                                                                  4931 2  099999
                                                                  4931 0  0    0
 4.91150E+4 1.13917E+2          0          0          1          14931 8  4    1
 4.911500+4 0.000000+0         10          0          0          04931 8  4    2
                                                                  4931 8  099999
 4.91150E+4 1.13917E+2          0          0          1          14931 8 16    1
 4.911400+4 0.000000+0         10          1          0          04931 8 16    2
                                                                  4931 8  099999
 4.91150E+4 1.13917E+2          0          0          1          14931 8102    1
 4.911600+4 0.000000+0         10          1          0          04931 8102    2
                                                                  4931 8  099999
                                                                  4931 0  0    0
 4.91150E+4 1.13917E+2          0          0          1          0493110  4    1
 0.0       -3.36240E+5      49115          0          1        214493110  4    2
        214          1                                            493110  4    3
 320000.000 4.26808E-7 340000.000 .000287403 360000.000 .000819582493110  4    4
 380000.000 .001351761 400000.000 .001832778 425000.000 .002262633493110  4    5
 450000.000 .002833150 475000.000 .003544330 500000.000 .004427385493110  4    6
 525000.000 .005482315 550000.000 .006739573 575000.000 .008199158493110  4    7
 600000.000 .010079555 630000.000 .012413913 660000.000 .015179200493110  4    8
 690000.000 .018214627 720000.000 .022308693 760000.000 .027583680493110  4    9
 800000.000 .033469320 840000.000 .039925608 880000.000 .046913900493110  4   10
 920000.000 .054352860 960000.000 .062152500 1000000.00 .076485100493110  4   11
 1100000.00 .097441650 1200000.00 .118527000 1300000.00 .139380000493110  4   12
 1400000.00 .160001000 1500000.00 .180578500 1600000.00 .201329500493110  4   13
 1700000.00 .222376500 1800000.00 .243662000 1900000.00 .264895000493110  4   14
 2000000.00 .285530500 2100000.00 .304807500 2200000.00 .321855000493110  4   15
 2300000.00 .335859000 2400000.00 .346250000 2500000.00 .352839500493110  4   16
 2600000.00 .355853500 2700000.00 .355855500 2800000.00 .353599500493110  4   17
 2900000.00 .349874500 3000000.00 .345387500 3100000.00 .340700500493110  4   18
 3200000.00 .336218000 3300000.00 .332201500 3400000.00 .328796500493110  4   19
 3500000.00 .326066000 3600000.00 .324015500 3700000.00 .322611500493110  4   20
 3800000.00 .321799500 3900000.00 .321514500 4000000.00 .321685000493110  4   21
 4100000.00 .322240000 4200000.00 .323110500 4300000.00 .324231500493110  4   22
 4400000.00 .325543000 4500000.00 .326989000 4600000.00 .328519500493110  4   23
 4700000.00 .330089000 4800000.00 .331656000 4900000.00 .333185000493110  4   24
 5000000.00 .334645000 5100000.00 .336008000 5200000.00 .337250500493110  4   25
 5300000.00 .338353000 5400000.00 .339299500 5500000.00 .340077500493110  4   26
 5600000.00 .340676500 5700000.00 .341089500 5800000.00 .341312500493110  4   27
 5900000.00 .341344000 6000000.00 .341183500 6100000.00 .340833000493110  4   28
 6200000.00 .340296500 6300000.00 .339579000 6400000.00 .338687000493110  4   29
 6500000.00 .337627500 6600000.00 .336408500 6700000.00 .335039000493110  4   30
 6800000.00 .333529000 6900000.00 .331887000 7000000.00 .330122500493110  4   31
 7100000.00 .328245500 7200000.00 .326265500 7300000.00 .324192500493110  4   32
 7400000.00 .322034500 7500000.00 .319800000 7600000.00 .317498000493110  4   33
 7700000.00 .315135880 7800000.00 .312720756 7900000.00 .310258876493110  4   34
 8000000.00 .307756374 8100000.00 .305218372 8200000.00 .302649000493110  4   35
 8300000.00 .300052000 8400000.00 .297430500 8500000.00 .294787000493110  4   36
 8600000.00 .292123000 8700000.00 .289438500 8800000.00 .286733000493110  4   37
 8900000.00 .284005500 9000000.00 .281254000 9100000.00 .278476000493110  4   38
 9200000.00 .275667000 9300000.00 .272821500 9400000.00 .269933500493110  4   39
 9500000.00 .266996500 9600000.00 .264002000 9700000.00 .260941000493110  4   40
 9800000.00 .257803000 9900000.00 .254576500 10000000.0 .251249500493110  4   41
 10100000.0 .247808500 10200000.0 .244240000 10300000.0 .240529500493110  4   42
 10400000.0 .236662500 10500000.0 .232624000 10600000.0 .228400500493110  4   43
 10700000.0 .223979000 10800000.0 .219348000 10900000.0 .214498500493110  4   44
 11000000.0 .209424000 11100000.0 .204123000 11200000.0 .198597000493110  4   45
 11300000.0 .192853500 11400000.0 .186906500 11500000.0 .180774500493110  4   46
 11600000.0 .174483500 11700000.0 .168065500 11800000.0 .161558000493110  4   47
 11900000.0 .155003500 12000000.0 .148448000 12100000.0 .141940000493110  4   48
 12200000.0 .135528500 12300000.0 .129261000 12400000.0 .123182000493110  4   49
 12500000.0 .117333000 12600000.0 .111749500 12700000.0 .106459500493110  4   50
 12800000.0 .101484750 12900000.0 .096840450 13000000.0 .092534700493110  4   51
 13100000.0 .088568950 13200000.0 .084939150 13300000.0 .081636350493110  4   52
 13400000.0 .078647650 13500000.0 .075957250 13600000.0 .073547100493110  4   53
 13700000.0 .071397750 13800000.0 .069489100 13900000.0 .067800800493110  4   54
 14000000.0 .066312900 14100000.0 .065006050 14200000.0 .063861900493110  4   55
 14300000.0 .062863200 14400000.0 .061993800 14500000.0 .061238900493110  4   56
 14600000.0 .060584900 14700000.0 .060019550 14800000.0 .059531700493110  4   57
 14900000.0 .059111250 15000000.0 .058749350 15100000.0 .058438100493110  4   58
 15200000.0 .058170400 15300000.0 .057940000 15400000.0 .057741350493110  4   59
 15500000.0 .057569650 15600000.0 .057420750 15700000.0 .057290850493110  4   60
 15800000.0 .057176700 15900000.0 .057075600 16000000.0 .056985050493110  4   61
 16100000.0 .056902900 16200000.0 .056827400 16300000.0 .056756950493110  4   62
 16400000.0 .056690250 16500000.0 .056626150 16600000.0 .056563600493110  4   63
 16700000.0 .056501850 16800000.0 .056440200 16900000.0 .056378050493110  4   64
 17000000.0 .056314950 17100000.0 .056250500 17200000.0 .056184400493110  4   65
 17300000.0 .056116350 17400000.0 .056046150 17500000.0 .055973650493110  4   66
 17600000.0 .055898750 17700000.0 .055821400 17800000.0 .055741500493110  4   67
 17900000.0 .055659050 18000000.0 .055574050 18100000.0 .055486500493110  4   68
 18200000.0 .055396500 18300000.0 .055304050 18400000.0 .055209200493110  4   69
 18500000.0 .055112050 18600000.0 .055012650 18700000.0 .054911100493110  4   70
 18800000.0 .054807450 18900000.0 .054701750 19000000.0 .054594150493110  4   71
 19100000.0 .054484700 19200000.0 .054373500 19300000.0 .054260700493110  4   72
 19400000.0 .054146300 19500000.0 .054030400 19600000.0 .053913150493110  4   73
 19700000.0 .053794600 19800000.0 .053674800 19900000.0 .053553850493110  4   74
 20000000.0 0.0                                                   493110  4   75
                                                                  493110  099999
 4.91150E+4 1.13917E+2          0          0          1          0493110 16    1
-9.03500E+6-9.03900E+6      49114          1          1        110493110 16    2
        110          1                                            493110 16    3
 9100000.00 .000902663 9200000.00 .003604598 9300000.00 .006356199493110 16    4
 9400000.00 .012049000 9500000.00 .020683000 9600000.00 .038782500493110 16    5
 9700000.00 .066347500 9800000.00 .096622500 9900000.00 .129607500493110 16    6
 10000000.0 .166775000 10100000.0 .208125000 10200000.0 .250125000493110 16    7
 10300000.0 .292775000 10400000.0 .337550000 10500000.0 .384450000493110 16    8
 10600000.0 .427975000 10700000.0 .468125000 10800000.0 .507375000493110 16    9
 10900000.0 .545725000 11000000.0 .583150000 11100000.0 .619650000493110 16   10
 11200000.0 .655200000 11300000.0 .689800000 11400000.0 .723475000493110 16   11
 11500000.0 .756225000 11600000.0 .788000000 11700000.0 .818800000493110 16   12
 11800000.0 .848650000 11900000.0 .877550000 12000000.0 .905500000493110 16   13
 12100000.0 .932500000 12200000.0 .958525000 12300000.0 .983575000493110 16   14
 12400000.0 1.00757500 12500000.0 1.03052500 12600000.0 1.05275000493110 16   15
 12700000.0 1.07425000 12800000.0 1.09475000 12900000.0 1.11425000493110 16   16
 13000000.0 1.13250000 13100000.0 1.14950000 13200000.0 1.16600000493110 16   17
 13300000.0 1.18200000 13400000.0 1.19675000 13500000.0 1.21025000493110 16   18
 13600000.0 1.22300000 13700000.0 1.23500000 13800000.0 1.24625000493110 16   19
 13900000.0 1.25675000 14000000.0 1.26625000 14100000.0 1.27475000493110 16   20
 14200000.0 1.28250000 14300000.0 1.28950000 14400000.0 1.29550000493110 16   21
 14500000.0 1.30050000 14600000.0 1.30500000 14700000.0 1.30900000493110 16   22
 14800000.0 1.31200000 14900000.0 1.31400000 15000000.0 1.31550000493110 16   23
 15100000.0 1.31650000 15200000.0 1.31675000 15300000.0 1.31625000493110 16   24
 15400000.0 1.31525000 15500000.0 1.31375000 15600000.0 1.31150000493110 16   25
 15700000.0 1.30850000 15800000.0 1.30500000 15900000.0 1.30100000493110 16   26
 16000000.0 1.29725000 16100000.0 1.29375000 16200000.0 1.29050000493110 16   27
 16300000.0 1.28750000 16400000.0 1.28450000 16500000.0 1.28150000493110 16   28
 16600000.0 1.27850000 16700000.0 1.27550000 16800000.0 1.27275000493110 16   29
 16900000.0 1.27025000 17000000.0 1.26750000 17100000.0 1.26450000493110 16   30
 17200000.0 1.26150000 17300000.0 1.25850000 17400000.0 1.25625000493110 16   31
 17500000.0 1.25475000 17600000.0 1.25200000 17700000.0 1.24800000493110 16   32
 17800000.0 1.24425000 17900000.0 1.24075000 18000000.0 1.23675000493110 16   33
 18100000.0 1.23225000 18200000.0 1.22750000 18300000.0 1.22250000493110 16   34
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 18700000.0 1.19625000 18800000.0 1.18925000 18900000.0 1.18175000493110 16   36
 19000000.0 1.17325000 19100000.0 1.16375000 19200000.0 1.15575000493110 16   37
 19300000.0 1.14925000 19400000.0 1.14125000 19500000.0 1.13175000493110 16   38
 19600000.0 1.12325000 19700000.0 1.11575000 19800000.0 1.10975000493110 16   39
 19900000.0 1.10525000 20000000.0 0.0                             493110 16   40
                                                                  493110  099999
 4.91150E+4 1.13917E+2          0          0          1          0493110102    1
 6.59800E+6 6.47100E+6      49116          1          1        641493110102    2
        641          1                                            493110102    3
 .000100000 2530.88414 .000105000 2471.88467 .000110000 2415.83488493110102    4
 .000115000 2364.18745 .000120000 2303.81185 .000127500 2236.82763493110102    5
 .000135000 2175.62735 .000142500 2119.38548 .000150000 2058.51629493110102    6
 .000160000 1995.10691 .000170000 1937.41300 .000180000 1884.45516493110102    7
 .000190000 1835.18318 .000200000 1790.19880 .000210000 1747.87618493110102    8
 .000220000 1708.56509 .000230000 1672.04232 .000240000 1629.17348493110102    9
 .000255000 1582.06568 .000270000 1545.71437 .000280000 1505.24830493110102   10
 .000300000 1455.90177 .000320000 1411.22219 .000340000 1370.30386493110102   11
 .000360000 1332.61620 .000380000 1298.21284 .000400000 1262.34619493110102   12
 .000425000 1225.64578 .000450000 1192.11774 .000475000 1161.37617493110102   13
 .000500000 1132.46491 .000525000 1106.04382 .000550000 1081.08605493110102   14
 .000575000 1057.87581 .000600000 1034.08749 .000630000 1009.61610493110102   15
 .000660000 987.225515 .000690000 965.747222 .000720000 942.894744493110102   16
 .000760000 918.392797 .000800000 895.644642 .000840000 874.798327493110102   17
 .000880000 854.985782 .000920000 836.824321 .000960000 819.433034493110102   18
 .001000000 801.410313 .001050000 782.594609 .001100000 764.954098493110102   19
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 1.211570-4 6.422440-5 2.129620-5 1.760800-6 4.940700-6 2.345520-5493140  4   34
 4.687370-5 6.446370-5 6.730320-5 5.071720-5 1.791030-5-1.663400-5493140  4   35
-3.112930-5-4.007490-6 1.070280-5-1.409080-6 3.731500-5 7.122080-5493140  4   36
 6.455080-5 1.691960-5-6.307810-5 9.240770-4 7.675920-4 4.340610-4493140  4   37
 1.889700-4 1.325150-4 2.036500-4 2.734330-4 2.663410-4 2.109280-4493140  4   38
 1.732390-4 2.013720-4 2.440090-4 1.973620-4 1.369210-4 1.122500-4493140  4   39
 1.158290-4 1.227070-4 1.151780-4 8.908630-5 5.088970-5 1.234660-5493140  4   40
-1.398150-5-1.790000-5 5.614170-6 5.273010-5 1.061770-4 1.346640-4493140  4   41
 1.086590-4 8.010530-6-1.714580-5 3.278800-6-7.062050-5-1.210310-4493140  4   42
-9.776650-5-1.037440-5 1.226180-4 9.546890-4 7.540960-4 4.133690-4493140  4   43
 1.813170-4 1.439300-4 2.215060-4 2.802070-4 2.649190-4 2.156310-4493140  4   44
 1.900630-4 2.284680-4 2.124410-4 1.497320-4 9.875520-5 7.807040-5493140  4   45
 7.694660-5 7.839720-5 7.148870-5 5.401340-5 3.043210-5 8.679040-6493140  4   46
-2.660430-6 3.122390-6 2.780290-5 6.406400-5 9.262080-5 8.926870-5493140  4   47
 2.787230-5-8.191790-6 2.318770-6-4.305850-5-8.056290-5-7.095120-5493140  4   48
-1.525760-5 7.614750-5 8.694270-4 7.223920-4 4.411470-4 2.072530-4493140  4   49
 1.351120-4 1.979550-4 2.804950-4 3.039050-4 2.397420-4 1.892090-4493140  4   50
 2.105450-4 2.021130-4 1.444630-4 6.981550-5 1.106630-5-1.608080-5493140  4   51
-1.243000-5 1.139470-5 4.138380-5 6.438450-5 7.046690-5 5.465750-5493140  4   52
 1.925360-5-2.317160-5-4.967550-5-3.874690-5 1.900880-5 1.733130-5493140  4   53
-1.875750-6 5.481740-5 9.222240-5 7.368310-5 7.773300-6-9.093480-5493140  4   54
 8.437620-4 6.922390-4 3.945370-4 1.678950-4 1.322530-4 2.241410-4493140  4   55
 3.091200-4 2.895730-4 1.917900-4 1.965230-4 2.182840-4 1.842480-4493140  4   56
 1.057970-4 2.432440-5-2.765660-5-3.849000-5-1.433110-5 2.851190-5493140  4   57
 7.046930-5 9.347820-5 8.467190-5 4.085560-5-2.518830-5-8.071180-5493140  4   58
-8.571350-5-6.050750-6 2.148780-5-3.050890-6 7.758670-5 1.407540-4493140  4   59
 1.215040-4 2.476510-5-1.302080-4 7.537630-4 5.999170-4 3.582540-4493140  4   60
 1.938090-4 1.677170-4 2.210780-4 2.804930-4 2.407070-4 1.971600-4493140  4   61
 1.872690-4 1.735310-4 1.395770-4 9.310370-5 4.913060-5 1.906170-5493140  4   62
 7.299560-6 1.213740-5 2.794930-5 4.713000-5 6.149060-5 6.363530-5493140  4   63
 4.938290-5 2.183980-5-5.824060-6-1.365510-5 2.746100-6-2.615160-7493140  4   64
 9.972300-6 2.683640-5 3.081800-5 1.621390-5-1.577760-5 6.874230-4493140  4   65
 5.930930-4 3.888430-4 2.152050-4 1.510340-4 2.149250-4 2.777380-4493140  4   66
 2.208290-4 1.552380-4 1.277890-4 1.254540-4 1.244010-4 1.107370-4493140  4   67
 8.300850-5 4.797540-5 1.567460-5-4.165470-6-4.403130-6 1.754150-5493140  4   68
 5.700600-5 9.884150-5 1.177310-4 9.163860-5 7.032800-6-1.298370-5493140  4   69
 2.635880-6-5.452030-5-9.177090-5-7.258980-5-5.858680-6 9.367750-5493140  4   70
 6.984770-4 5.998120-4 3.905110-4 2.177820-4 1.643490-4 2.496240-4493140  4   71
 2.401640-4 1.625400-4 1.005740-4 7.632990-5 7.582980-5 7.915320-5493140  4   72
 7.395470-5 5.760930-5 3.453510-5 1.265710-5 5.009790-7 4.746930-6493140  4   73
 2.736710-5 6.170590-5 8.964200-5 8.792500-5 3.048300-5-6.860330-6493140  4   74
 2.141220-6-3.854400-5-7.285930-5-6.473150-5-1.483150-5 6.743770-5493140  4   75
 6.794630-4 5.880390-4 4.120080-4 2.046770-4 1.791660-4 2.230490-4493140  4   76
 1.950760-4 1.224160-4 5.248990-5 9.757100-6-2.819680-6 6.196620-6493140  4   77
 2.492440-5 4.277600-5 5.230010-5 4.962290-5 3.464360-5 1.163020-5493140  4   78
-1.012700-5-1.801450-5-4.334340-6 2.656360-5 1.123010-5-8.027190-7493140  4   79
 2.968020-5 4.546760-5 3.256580-5-1.089380-6-4.696880-5 6.692510-4493140  4   80
 5.967890-4 3.337210-4 1.478540-4 1.794010-4 2.087530-4 1.676660-4493140  4   81
 8.628630-5 1.020560-5-3.268420-5-3.644080-5-1.037140-5 2.914370-5493140  4   82
 6.470420-5 8.156430-5 7.029990-5 3.016520-5-2.616250-5-7.025470-5493140  4   83
-6.990740-5-4.097690-7 1.851090-5-2.494130-6 6.434960-5 1.144400-4493140  4   84
 9.699850-5 1.817360-5-1.054790-4 6.538970-4 4.759820-4 2.050210-4493140  4   85
 1.555750-4 1.903250-4 1.923420-4 1.459370-4 7.909290-5 2.201650-5493140  4   86
-8.494560-6-9.980650-6 1.023950-5 4.005930-5 6.621900-5 7.685960-5493140  4   87
 6.423430-5 2.897320-5-1.489200-5-4.161670-5-2.023840-5 8.502410-6493140  4   88
-1.276300-6 3.285250-5 6.792760-5 6.581680-5 2.293130-5-5.350550-5493140  4   89
 5.583280-4 4.180940-4 2.489800-4 1.766490-4 1.680740-4 1.729660-4493140  4   90
 1.637680-4 1.349170-4 9.352230-5 5.110810-5 1.857310-5 3.829230-6493140  4   91
 1.078380-5 3.833840-5 7.858220-5 1.147730-4 1.233560-4 8.807400-5493140  4   92
 3.427490-6-1.108340-5 2.411080-6-4.692260-5-7.510350-5-5.583280-5493140  4   93
 6.437070-8 7.914460-5 5.804090-4 4.883400-4 3.168900-4 1.822360-4493140  4   94
 1.094620-4 8.282420-5 7.868330-5 7.922270-5 7.542560-5 6.546800-5493140  4   95
 5.200740-5 3.985100-5 3.415550-5 3.863190-5 5.298760-5 6.988770-5493140  4   96
 7.532620-5 4.531980-5 2.467620-6 1.232100-6-1.071810-5-2.656170-5493140  4   97
-2.803710-5-1.132890-5 2.137410-5 5.949420-4 5.163190-4 3.443930-4493140  4   98
 1.708030-4 4.781190-5-9.797840-6-1.163620-5 2.145840-5 6.666680-5493140  4   99
 1.042040-4 1.195530-4 1.049130-4 6.158490-5 3.732010-6-4.049620-5493140  4  100
-4.161550-5 1.743500-5 2.079450-5-2.023920-6 6.181430-5 1.071800-4493140  4  101
 8.914680-5 1.598400-5-9.587700-5 6.000740-4 5.451120-4 4.087660-4493140  4  102
 2.570900-4 1.355900-4 6.405750-5 4.237700-5 5.878300-5 9.650450-5493140  4  103
 1.377670-4 1.659380-4 1.674840-4 1.359050-4 7.855500-5 2.071900-5493140  4  104
-5.170160-6 9.055910-6 1.766610-8 2.062530-5 5.068850-5 5.590750-5493140  4  105
 2.835380-5-2.840850-5 6.739910-4 6.927520-4 6.167070-4 4.848130-4493140  4  106
 3.391070-4 2.135360-4 1.304150-4 1.008420-4 1.258180-4 1.957880-4493140  4  107
 2.876630-4 3.614250-4 3.658400-4 2.695410-4 5.687140-5-1.227630-5493140  4  108
 5.854420-6-8.315820-5-1.307890-4-9.386730-5 4.777720-6 1.398230-4493140  4  109
 8.956910-4 9.575600-4 8.828450-4 7.147410-4 5.104730-4 3.243900-4493140  4  110
 1.995880-4 1.642560-4 2.278840-4 3.731440-4 5.432940-4 6.390690-4493140  4  111
 5.617050-4 2.059750-4-1.496280-5 1.094680-5-1.490800-4-2.677640-4493140  4  112
-2.241700-4-3.753940-5 2.492840-4 1.162210-3 1.192480-3 1.073010-3493140  4  113
 8.613620-4 6.242780-4 4.231130-4 3.065680-4 3.051580-4 4.212260-4493140  4  114
 6.109330-4 7.689480-4 7.583550-4 3.872640-4 1.155060-5 1.229960-5493140  4  115
-1.247520-4-2.585100-4-2.416660-4-7.022010-5 2.204960-4 1.343780-3493140  4  116
 1.330780-3 1.189850-3 9.760530-4 7.480340-4 5.597400-4 4.555950-4493140  4  117
 4.629220-4 5.750540-4 7.263900-4 7.901080-4 5.293260-4 5.902690-5493140  4  118
 9.604270-6-1.975500-5-1.034080-4-1.331120-4-7.277150-5 7.165800-5493140  4  119
 1.451870-3 1.437840-3 1.314470-3 1.119050-3 8.943890-4 6.864230-4493140  4  120
 5.422510-4 5.005960-4 5.645720-4 6.630800-4 5.762300-4 1.088810-4493140  4  121
 4.604840-6 1.171430-4 1.262400-4 5.316320-5-3.993310-5-1.213230-4493140  4  122
 1.572160-3 1.581420-3 1.471710-3 1.262400-3 9.874770-4 6.999370-4493140  4  123
 4.734690-4 3.826190-4 4.401470-4 5.046240-4 1.412560-4-3.152520-8493140  4  124
 2.265060-4 3.332960-4 2.408730-4 1.886390-5-2.712420-4 1.734270-3493140  4  125
 1.746910-3 1.610620-3 1.336220-3 9.638700-4 5.761930-4 2.950810-4493140  4  126
 2.200200-4 3.302870-4 1.414370-4-1.714830-6 2.594610-4 4.302920-4493140  4  127
 3.542960-4 8.349750-5-3.120190-4 1.897100-3 1.887450-3 1.700100-3493140  4  128
 1.343370-3 8.733620-4 4.133040-4 1.239200-4 1.115010-4 1.039020-4493140  4  129
 1.308320-6 1.906180-4 3.619560-4 3.374430-4 1.279230-4-2.160140-4493140  4  130
 2.044200-3 2.034690-3 1.822330-3 1.400220-3 8.333560-4 2.891650-4493140  4  131
-4.530750-5 3.594830-5 9.252940-6 2.722010-5 1.214320-4 1.685150-4493140  4  132
 1.254710-4-2.967280-6 2.278240-3 2.346400-3 2.144150-3 1.617530-3493140  4  133
 8.591030-4 2.100590-5-3.725150-5 1.991280-5-1.808000-4-2.312720-4493140  4  134
-1.228560-4 5.691170-5 2.535410-4 2.803450-3 3.009470-3 2.750750-3493140  4  135
 1.945570-3 5.171010-4-6.650430-5 2.771530-5-3.310770-4-5.477510-4493140  4  136
-4.324660-4-7.477900-5 4.251560-4 3.769220-3 4.055680-3 3.524510-3493140  4  137
 1.623270-3 2.112930-5 2.413140-5-2.769420-4-5.905430-4-5.680570-4493140  4  138
-2.218830-4 3.548060-4 5.097970-3 5.247340-3 3.288620-3 2.938230-4493140  4  139
 3.478540-6 1.013570-4-1.266150-4-3.055100-4-2.789910-4-4.752080-5493140  4  140
 6.316630-3 4.933610-3 7.344400-4-2.188660-5 7.292020-4 8.080040-4493140  4  141
 4.010620-4-1.342080-4-6.368090-4 4.945260-3 1.213690-3 3.634430-5493140  4  142
 1.177520-3 1.652270-3 1.220020-3 2.789710-4-8.913250-4 8.698960-4493140  4  143
 3.475700-4 3.534930-4 4.186150-4 3.550390-4 1.773520-4-7.331360-5493140  4  144
 5.153350-4 3.975890-4 2.332660-4 1.091980-4 2.823100-5-2.163150-5493140  4  145
 1.382620-3 1.844060-3 1.642420-3 1.011630-3 1.406180-4 2.928410-3493140  4  146
 3.028540-3 2.435580-3 1.422320-3 3.697970-3 3.780810-3 3.486050-3493140  4  147
 4.941200-3 5.924580-3 8.514690-3                                 493140  4  148
                                                                  493140  099999
 4.91150E+4 1.13917E+2          0          0          1          0493140 16    1
-9.035000+6-9.225000+6          0          0          0          1493140 16    2
 1.000000+1 0.000000+0          0         16          0          1493140 16    3
 0.000000+0 0.000000+0          1          5        120         15493140 16    4
 1.000000-5 9.100000+6 1.050000+7 1.150000+7 1.220000+7 1.270000+7493140 16    5
 1.320000+7 1.380000+7 1.420000+7 1.470000+7 1.520000+7 1.600000+7493140 16    6
 1.720000+7 1.800000+7 2.000000+7 4.000000-1 1.154500-2 2.886700-3493140 16    7
 5.207500-4 6.268700-4 2.634000-4 7.576400-5 0.000000+0 0.000000+0493140 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.360500-3493140 16    9
 2.329300-4 4.379300-5 3.313900-5 2.375700-5 6.429400-6 0.000000+0493140 16   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0493140 16   11
 4.273200-4 5.149000-5 5.671700-5 3.970200-5 1.611800-5 0.000000+0493140 16   12
 5.134000-6 5.330100-6 0.000000+0 3.850900-6 2.755800-7 0.000000+0493140 16   13
 1.326100-4 7.026400-5 5.057000-5 1.814000-5 1.025800-5 1.091900-5493140 16   14
 1.151900-5 6.054300-6 4.032200-6 3.183000-6 2.577000-7 1.061600-4493140 16   15
 7.193900-5 1.827700-5 7.806100-6 1.063900-5 1.195100-5 9.623500-6493140 16   16
 6.619700-6 5.063800-6 1.300400-6 9.380800-5 2.002300-5 8.788300-6493140 16   17
 1.212000-5 1.349000-5 1.062800-5 7.704500-6 6.688400-6 1.473800-6493140 16   18
 5.145600-5 2.270400-5 1.436100-5 1.686000-5 4.715200-6 4.452700-6493140 16   19
 4.233200-6 1.200700-6 4.804900-5 1.232200-5 1.347800-5 3.765900-6493140 16   20
 2.757000-6 3.388400-6 4.405400-7 4.707100-5 2.134000-5 8.565900-6493140 16   21
 1.578500-5 9.719500-6 9.119700-6 4.580100-5 1.385300-5 1.154500-5493140 16   22
 1.754500-5 3.156100-6 4.554700-5 1.336600-5 2.469400-5 2.724500-6493140 16   23
 4.622500-5 2.217600-5 1.374800-5 7.898800-5 5.926800-6 8.012400-5493140 16   24
                                                                  493140  099999
 4.91150E+4 1.13917E+2          0          0          1          0493140102    1
 6.598000+6 6.471000+6          0          1          0          1493140102    2
 1.000000+1 1.000000+0          0        102          0          1493140102    3
 0.000000+0 0.000000+0          0          1         14          7493140102    4
 1.000000-5 3.600000-3 1.000000+3 2.250000-2 1.000000+4 8.100000-3493140102    5
 1.000000+5 2.500000-3 1.000000+6 4.900000-3 4.000000+6 1.690000-2493140102    6
 2.000000+7 0.000000+0                                            493140102    7
                                                                  493140  099999
                                                                  4931 0  0    0
                                                                     0 0  0    0
 5.31270E+4 1.25814E+2          0          0         34         105325 1451    1
 0.0        0.0                 0          0          0          65325 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20025325 1451    3
 3.00000E+2 0.0                 1          0         60          45325 1451    4
 53-I -127 CNDC/CIAE  EVAL-JUN91 Zhao Wenrong and Lu Hanlin et.al.5325 1451    5
                      DIST-Feb2004                                5325 1451    6
----IRDF-2002         MATERIAL 5325                               5325 1451    7
-----INCIDENT NEUTRON DATA                                        5325 1451    8
------ENDF-6 FORMAT                                               5325 1451    9
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 5325 1451   10
53-I -127  CNDC/CIAE  EVAL-JUN91 Zhao Wenrong and Lu Hanlin et.al.5325 1451   11
---ENDF-6 FORMAT      5325                  REVISION 0            5325 1451   12
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 5325 1451   13
                                                                  5325 1451   14
Results of the evaluation in ENDF/B Format                        5325 1451   15
53-I-127                                                          5325 1451   16
I-127(n,2n)I-126  Dosimetry reaction                              5325 1451   17
Evaluated by Zhao Wenrong Lu Hanlin Yu Weixiang Cai Dunjiu        5325 1451   18
Wang Zisheng Huang Xiaolong                                       5325 1451   19
                                                                  5325 1451   20
The reaction of I-127(n,2n)I-126 is used as a threshold detector  5325 1451   21
 for neutron dosimetry applications. Its threshold is 9.137       5325 1451   22
MeV. The half-life of I-126 is 13.023d. Iodine is a monoisotopic  5325 1451   23
element. The main gamma ray energies of I-126 are 388.6keV        5325 1451   24
and 666.4keV with branch ratios of 34.1 percent and 33.1 percent  5325 1451   25
respectively. In order to get reasonable results, the necessary   5325 1451   26
adjustment was made first for the collected data. Then the        5325 1451   27
evaluation was performed by spline fitting procedure. The         5325 1451   28
uncertainties were derived from experimental errors and           5325 1451   29
the consideration of systematics.                                 5325 1451   30
                                                                  5325 1451   31
Evaluation documentation: Zhao Wenrong.                           5325 1451   32
Report CIAE 1991                                                  5325 1451   33
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 5325 1451   34
  The Q values and threshold energies were updated prior to pro-  5325 1451   35
  cessing through the codes to comply with the values obtained    5325 1451   36
  using the NNDC calculation program which is based on the 1995   5325 1451   37
  Update to the Atomic mass Evaluation.                           5325 1451   38
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 5325 1451   39
 ***************** Program LINEAR (VERSION 2002-1) ***************5325 1451   40
 For All Data Greater than 1.0000E-10 barns in Absolute Value     5325 1451   41
 Data Linearized to Within an Accuracy of .100000000 per-cent     5325 1451   42
 ***************** Program SIGMA1 (VERSION 2002-1) ***************5325 1451   43
 Data Doppler Broadened to 300.000000 Kelvin                      5325 1451   44
 for All Data Greater than 1.0000E-10 barns in Absolute Value     5325 1451   45
 Data Linearized to Within an Accuracy pf .100000000 per-cent     5325 1451   46
 ***************** Program FIXUP (Version 2002-1) ****************5325 1451   47
 Corrected ZA/AWR in All Sections-----------------------------Yes 5325 1451   48
 Corrected Thresholds-----------------------------------------Yes 5325 1451   49
 Extended Cross Sections to 20 MeV----------------------------No  5325 1451   50
 Allow Cross Section Deletion---------------------------------No  5325 1451   51
 Allow Cross Section Reconstruction---------------------------No  5325 1451   52
 Make All Cross Sections Non-Negative-------------------------Yes 5325 1451   53
 Delete Energies Not in Ascending Order-----------------------Yes 5325 1451   54
 Deleted Duplicate Points-------------------------------------Yes 5325 1451   55
 Check for Ascending MAT/MF/MT Order--------------------------Yes 5325 1451   56
 Check for Legal MF/MT Numbers--------------------------------Yes 5325 1451   57
 Allow Creation of Missing Sections---------------------------No  5325 1451   58
 Allow Insertion of Energy Points-----------------------------No  5325 1451   59
 Create Uniform Energy Grid-----------------------------------No  5325 1451   60
 Delete Section if Cross Section =0 at All Energies-----------Yes 5325 1451   61
 ***************** Program GROUPIE (VERSION 2002-1) **************5325 1451   62
 Unshielded Group Averages Using  640 Groups                      5325 1451   63
 Weighting Spectrum: Flat (Constant) Spectrum                     5325 1451   64
                                1        451         68          15325 1451   65
                                2        151          4          15325 1451   66
                                3         16         40          15325 1451   67
                               33         16         19          15325 1451   68
                                                                  5325 1  099999
                                                                  5325 0  0    0
 5.31270E+4 1.25814E+2          0          0          1          05325 2151    1
 5.31270E+4 1.00000E+0          0          0          1          05325 2151    2
 1.00000E-5 1.98900E+1          0          0          0          05325 2151    3
 2.50000E+0 5.70000E-1          0          0          0          05325 2151    4
                                                                  5325 2  099999
                                                                  5325 0  0    0
 5.31270E+4 1.25814E+2          0          0          1          05325 3 16    1
-9.14300E+6-9.14300E+6          0          0          1        1095325 3 16    2
        109          1                                            5325 3 16    3
 9200000.00 .002125030 9300000.00 .003744262 9400000.00 .0058736845325 3 16    4
 9500000.00 .008981316 9600000.00 .031000000 9700000.00 .0660600005325 3 16    5
 9800000.00 .108200000 9900000.00 .155240000 10000000.0 .2070000005325 3 16    6
 10100000.0 .262032500 10200000.0 .320900000 10300000.0 .3824372375325 3 16    7
 10400000.0 .448368421 10500000.0 .517276842 10600000.0 .5849000005325 3 16    8
 10700000.0 .651900000 10800000.0 .718900000 10900000.0 .7858500005325 3 16    9
 11000000.0 .851150000 11100000.0 .915570000 11200000.0 .9773500005325 3 16   10
 11300000.0 1.03776632 11400000.0 1.09542105 11500000.0 1.151272635325 3 16   11
 11600000.0 1.19980000 11700000.0 1.24544000 11800000.0 1.285400005325 3 16   12
 11900000.0 1.32310750 12000000.0 1.35620000 12100000.0 1.387452505325 3 16   13
 12200000.0 1.41480000 12300000.0 1.44060105 12400000.0 1.463263165325 3 16   14
 12500000.0 1.48443579 12600000.0 1.50185000 12700000.0 1.518110005325 3 16   15
 12800000.0 1.53215000 12900000.0 1.54537000 13000000.0 1.556000005325 3 16   16
 13100000.0 1.56600000 13200000.0 1.57600000 13300000.0 1.585794875325 3 16   17
 13400000.0 1.59369231 13500000.0 1.60112821 13600000.0 1.608564105325 3 16   18
 13700000.0 1.61572676 13800000.0 1.62125000 13900000.0 1.626500005325 3 16   19
 14000000.0 1.63175000 14100000.0 1.63679830 14200000.0 1.640636365325 3 16   20
 14300000.0 1.64427273 14400000.0 1.64790909 14500000.0 1.651545455325 3 16   21
 14600000.0 1.65518182 14700000.0 1.65826506 14800000.0 1.660795185325 3 16   22
 14900000.0 1.66332530 15000000.0 1.66585542 15100000.0 1.668385545325 3 16   23
 15200000.0 1.67091566 15300000.0 1.67344578 15400000.0 1.675975905325 3 16   24
 15500000.0 1.67817198 15600000.0 1.67940000 15700000.0 1.680566675325 3 16   25
 15800000.0 1.68173333 15900000.0 1.68290000 16000000.0 1.684066675325 3 16   26
 16100000.0 1.68494750 16200000.0 1.68500000 16300000.0 1.684748725325 3 16   27
 16400000.0 1.68376923 16500000.0 1.68274359 16600000.0 1.681717955325 3 16   28
 16700000.0 1.68006051 16800000.0 1.67710000 16900000.0 1.674100005325 3 16   29
 17000000.0 1.67110000 17100000.0 1.66762000 17200000.0 1.663150005325 3 16   30
 17300000.0 1.65795667 17400000.0 1.65133333 17500000.0 1.644666675325 3 16   31
 17600000.0 1.63800000 17700000.0 1.63028708 17800000.0 1.621050005325 3 16   32
 17900000.0 1.61180000 18000000.0 1.60255000 18100000.0 1.592388755325 3 16   33
 18200000.0 1.58090000 18300000.0 1.56824212 18400000.0 1.553897445325 3 16   34
 18500000.0 1.53953846 18600000.0 1.52517949 18700000.0 1.509750005325 3 16   35
 18800000.0 1.49325000 18900000.0 1.47550000 19000000.0 1.456500005325 3 16   36
 19100000.0 1.43675000 19200000.0 1.41625000 19300000.0 1.393692315325 3 16   37
 19400000.0 1.36907692 19500000.0 1.34446154 19600000.0 1.319880525325 3 16   38
 19700000.0 1.29935484 19800000.0 1.28161290 19900000.0 1.263870975325 3 16   39
 20000000.0 0.0                                                   5325 3 16   40
                                                                  5325 3  099999
                                                                  5325 0  0    0
 5.31270E+4 1.25814E+2          0          0          1          1532533 16    1
 0.000000+0 0.000000+0          0         16          0          1532533 16    2
 0.000000+0 0.000000+0          1          5         91         13532533 16    3
 1.000000-5 9.200000+6 1.058000+7 1.118000+7 1.157000+7 1.237000+7532533 16    4
 1.355000+7 1.415000+7 1.454000+7 1.514000+7 1.712000+7 1.811000+7532533 16    5
 1.989000+7 1.000000-1 2.189400-3 1.465900-3 8.864000-4 6.104300-4532533 16    6
 5.784600-4 5.628800-4 4.006100-4 5.706500-4 2.236400-4 3.653400-4532533 16    7
 3.326600-4 2.851600-4 6.491500-5 3.944500-5 2.716400-5 2.613800-5532533 16    8
 2.527600-5 1.805000-5 2.583600-5 9.952100-6 1.661900-5 1.522700-5532533 16    9
 1.278300-4 2.641000-5 1.818700-5 1.750000-5 1.692300-5 1.208500-5532533 16   10
 1.729800-5 6.663300-6 1.112700-5 1.019500-5 6.062500-5 1.953900-5532533 16   11
 2.045100-5 8.819600-6 9.864000-6 7.941700-6 3.976900-6 1.965700-5532533 16   12
 1.911200-5 4.140300-5 1.991900-5 1.119300-5 9.425200-6 1.161100-5532533 16   13
 1.011200-5 1.294000-5 1.031500-5 2.200000-5 9.677000-6 7.798900-6532533 16   14
 1.012000-5 7.187100-6 7.827200-6 6.343900-6 1.636500-5 1.249200-5532533 16   15
 1.206100-5 9.854400-6 9.520400-6 8.511300-6 1.567300-5 1.273500-5532533 16   16
 7.466100-6 8.300400-6 6.147800-6 1.539000-5 1.140600-5 1.040700-5532533 16   17
 8.057200-6 1.543700-5 1.378500-5 8.856800-6 1.830900-5 1.393200-5532533 16   18
 2.509400-5                                                       532533 16   19
                                                                  532533  099999
                                                                  5325 0  0    0
                                                                     0 0  0    0
 5.71390E+4 1.37713E+2          0          0         34         105728 1451    1
 0.0        0.0                 0          0          0          65728 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20025728 1451    3
 3.00000E+2 0.0                 1          0        200          45728 1451    4
 57-La-139 FEI        EVAL-SEP01 K.I.Zolotarev                    5728 1451    5
                      DIST-Feb2004                                5728 1451    6
----IRDF-2002         MATERIAL 5728                               5728 1451    7
-----INCIDENT NEUTRON DATA                                        5728 1451    8
------ENDF-6 FORMAT                                               5728 1451    9
***************************************************************** 5728 1451   10
 57-La-139 FEI        EVAL-Sep01 K.I.Zolotarev                    5728 1451   11
                      DIST-Jan04                                  5728 1451   12
----BROND-3           MATERIAL 5728         Revision 1, Jan. 2004 5728 1451   13
-----INCIDENT NEUTRON DATA                                        5728 1451   14
------ENDF-6 FORMAT                                               5728 1451   15
***************************************************************** 5728 1451   16
------Russian Reactor Dosimetry File RRDF-2002                    5728 1451   17
***************************************************************** 5728 1451   18
Authors of evaluation: K.I.Zolotarev and V.G.Pronyaev             5728 1451   19
***************************************************************** 5728 1451   20
                                                                  5728 1451   21
                    ----- MF=2 MT=151 -----                       5728 1451   22
                                                                  5728 1451   23
RESONANCE PARAMETERS                                              5728 1451   24
1. Resolved Resonance Region (RRR)                                5728 1451   25
   Resolved MLBW resonance parameters  up to  20  keV were based  5728 1451   26
on data from ref.[1-2]. Spins of resonances, which were not iden- 5728 1451   27
tified, have been assigned by taking into account 2*J+1 law  and  5728 1451   28
approximate linear growth of the number of levels with given spin 5728 1451   29
and parity from energy.  Average gamma-widths  0.055 eV (L=0) and 5728 1451   30
0.04 eV (L=1)  were assigned  to  those resonances , widths  for  5728 1451   31
which were absent.  Fictitious  P-resonances  were  added  in the 5728 1451   32
energy region  (3 - 20) keV  to obtain the average capture cross  5728 1451   33
section values observed in the experiments [3],[4],[5].           5728 1451   34
                                                                  5728 1451   35
2. Unresolved Resonance Region (URR)                              5728 1451   36
   Unresolved resonance parameters in the region 20 keV - 160 keV 5728 1451   37
were evaluated  by  using  'EVPAR' code (Hauser-Feshbach-Moldauer 5728 1451   38
statistical model) [6]. URR parameters were calculated from opti- 5728 1451   39
mized fit to the measured capture [4,5]  and  total cross section 5728 1451   40
[7,8,9] data.  Average resolved resonance  parameters  have been  5728 1451   41
used as zero approximation.  Contribution of F-wave in the energy 5728 1451   42
interval  60 - 160 keV given as smoothed background cross section 5728 1451   43
in File 3.                                                        5728 1451   44
                                                                  5728 1451   45
                    ----- MF=3 MT=102 -----                       5728 1451   46
                                                                  5728 1451   47
   Capture cross sections from 1.0E-5 eV to 160 keV  are reconst- 5728 1451   48
ructed from evaluated  MLBW resolved and unresolved resonance pa- 5728 1451   49
rameters.  Small background  was added  in  RRR  for taking into  5728 1451   50
account non-statistical reaction mechanism contribution. Contri-  5728 1451   51
bution of F-wave in the energy interval (60 - 160) keV was added  5728 1451   52
as described above.                                               5728 1451   53
   Data base for the evaluation La-139(n,g)La-140 excitation func-5728 1451   54
tion in the neutron energy range 160 keV - 20 MeV was formed from 5728 1451   55
microscopic experimental  data [4-5], [10-28] and  data  received 5728 1451   56
from theoretical model calculations. Experimental data [4], [10], 5728 1451   57
[12-18], [20-22], [27-28] were  corrected  to  the  new standards.5728 1451   58
Uncertainties  for cross section data  measured by Johnsrud et al.5728 1451   59
[13] were evaluated between +-(16-19)%. Theoretical model calcula-5728 1451   60
tions was done by means of GNASH code [29].  New modified version 5728 1451   61
of GNASH was utilized for calculations [30].   Data from theoreti-5728 1451   62
cal model  calculation were dominant  in the neutron energy range 5728 1451   63
3.5 - 20 MeV.                                                     5728 1451   64
    The evaluation  La-139(n,g)La-140  excitation function in the 5728 1451   65
energy range above 160 keV has been carried out within the frame- 5728 1451   66
work  of generalized least squares method , rational function was 5728 1451   67
used as model function [31]. Procedure of calculation recommended 5728 1451   68
cross section data was performed by means of PADE-2 code [32].    5728 1451   69
   Capture cross section at En=0.0253 eV and Resonance Integral   5728 1451   70
(0.5 to 2.0E+7 eV) from present evaluation are given below in the 5728 1451   71
Table 1. in a comparison with data from compilations [1], [33-34].5728 1451   72
                                                      Table 1.    5728 1451   73
        -------------------------------------------------         5728 1451   74
          Parameters            Values, barn   References         5728 1451   75
        -------------------------------------------------         5728 1451   76
        Capture cross section   9.04 +- 0.23   This eval.         5728 1451   77
        at En=0.0253 eV         8.93 +- 0.04     [ 1]             5728 1451   78
                                9.04 +- 0.04     [33]             5728 1451   79
                                9.2  +- 0.2      [34]             5728 1451   80
        -------------------------------------------------         5728 1451   81
        Resonance Integral      12.1           This eval.         5728 1451   82
                                11.8 +- 0.8      [ 1]             5728 1451   83
                                12.1 +- 0.6      [33]             5728 1451   84
                                11.8 +- 0.8      [34]             5728 1451   85
        -------------------------------------------------         5728 1451   86
                                                                  5728 1451   87
                    ----- MF=33 MT=102-----                       5728 1451   88
    Uncertainties in  the evaluated excitation function  for the  5728 1451   89
reaction  La-139(n,g)La-140  are given  in the three independent  5728 1451   90
matrixes.                                                         5728 1451   91
    In the energy range 1.000E-05 - 200 eV uncertainties are pre- 5728 1451   92
sented in the form of relative covariance matrix for the 16-neut- 5728 1451   93
ron energy groups (LB=5). Eigenvalues  of this 6-th digits relat- 5728 1451   94
ive covariance matrix are the following:                          5728 1451   95
                                                                  5728 1451   96
    1.29984E-04    1.80010E-04    2.41627E-04    2.69103E-04      5728 1451   97
    3.03943E-04    3.53897E-04    4.83948E-04    5.72815E-04      5728 1451   98
    6.17194E-04    6.90136E-04    9.46937E-04    1.01148E-03      5728 1451   99
    1.61882E-03    1.76694E-03    1.98803E-03    2.89526E-02      5728 1451  100
                                                                  5728 1451  101
    In the energy range 0.2 - 20  keV  uncertainties are given in 5728 1451  102
the form  of  diagonal matrix of uncertainties  for  7-th neutron 5728 1451  103
energy intervals (LB=1)                                           5728 1451  104
    In the energy range 20 keV - 20 MeV uncertainties are presen- 5728 1451  105
ted in the form of relative covariance matrix for the 23-neutron  5728 1451  106
energy groups (LB=5).  Eigenvalues  of this 6-th digits relative  5728 1451  107
covariance matrix are the following:                              5728 1451  108
                                                                  5728 1451  109
    1.96223E-10    5.86297E-08    3.57093E-07    1.00052E-05      5728 1451  110
    3.95061E-05    1.50141E-04    2.46548E-04    3.34259E-04      5728 1451  111
    4.59370E-04    6.23219E-04    7.85798E-04    8.75929E-04      5728 1451  112
    1.31621E-03    1.62913E-03    1.81439E-03    1.87643E-03      5728 1451  113
    2.55332E-03    2.70062E-03    3.40954E-03    4.32177E-03      5728 1451  114
    1.13231E-02    3.04915E-02    1.18873E-01                     5728 1451  115
                                                                  5728 1451  116
References :                                                      5728 1451  117
 1. S.F.Mughabghab et al.  Neutron Cross Sections ,Vol.1,Part A,  5728 1451  118
    New York, Academic Press,1981                                 5728 1451  119
 2. S.I.Sukhoruchkin et al. Landolt Bornstein New Series, v.I/16B,5728 1451  120
    ed. H.Schopper, Springer, 1998, pp.w19-w23                    5728 1451  121
 3. V.A.Konks, Ju.P.Popov, F.L.Shapiro  Zurnal Eksperim. i Teor.  5728 1451  122
    Fiziki, (USSR), v.46,(1), p.80, 1963                          5728 1451  123
 4. D.C.Stupegia et al.  J. Nucl. Energ., v.22, p.267, May 1968   5728 1451  124
 5. B.J.Allen, J.W.Boldeman, R.L.Macklin  Nucl. Sci. Eng., v.82,  5728 1451  125
    n.2, p.230, October 1982                                      5728 1451  126
 6. G.N.Manturov et al. Voprosy Atomnoy Nauki i Tekhniki, Ser.:   5728 1451  127
    Jadernye Konstanty, v.1, p.50, 1983                           5728 1451  128
 7. M.Divadeenam et al. Diss. Abstr. B , 1968, v.28, p.3834, 1968 5728 1451  129
 8. E.Islam et al.  Nucl. Phys. A, v.209, p.189, 1973             5728 1451  130
 9. K.Nishimura et al. Report JAERI-M-6883, January 1977          5728 1451  131
10. R.L.Macklin et al.  Phys. Rev., v.107, p.504, 1957            5728 1451  132
11. J.L.Perkin et al.  Proc. Phys. Soc., v.72, p.505, 1958        5728 1451  133
12. W.S.Lyon, R.L.Macklin  Phys. Rev., v.114, p.1619, 1959        5728 1451  134
13. A.E.Johnsrud et al.  Phys. Rev., v.116, p.927, 1959           5728 1451  135
14. R.G.Wille, R.W.Fink  Phys. Rev., v.118, p.242, 1960           5728 1451  136
15. J.H.Gibbons et al.  Phys. Rev., v.122, p.182, 1961            5728 1451  137
16. J.Csikai et al.  J. Atomki Kozlemenyek, v.8, p.79, June 1966  5728 1451  138
    J.Csikai et al.  Nucl. Phys. A, v.95, p.229, March 1967       5728 1451  139
17. A.K.Chaubey, M.L.Sehgal  Phys. Rev., v.152, p.1055, Dec. 1966 5728 1451  140
18. G.Peto et al.  J. Nucl. Energ., v.21, p.797, October 1967     5728 1451  141
19. F.Rigaud et al.  Nucl. Phys., v.A176, p.545, December 1971    5728 1451  142
20. G.G.Zaikin et al.  Ukrainskij Fizichnij Zhurnal, v.16(7),     5728 1451  143
    p.1205, July 1971                                             5728 1451  144
21. F.Rigaud et al.  Nucl. Sci. Eng., v.55, p.17, September 1974  5728 1451  145
22. O.Schwerer et al.  Nucl. Phys. A, v.264, p.105, June 1976     5728 1451  146
23. A.R.Del.Musgrove, B.J.Allen, R.L.Macklin  Proc. of Int. Conf. 5728 1451  147
    on Neutron Physics and Nuclear Data for Reactors and Other    5728 1451  148
    Applied Purposes, AERE Harwell, 25-29 September 1978, p.449   5728 1451  149
24. W.P.Poenitz  Progress Report ANL-83-4, p.239, April 1982      5728 1451  150
25. J.Voignier et al.  Nucl. Sci. Eng., v.93, p.43, 1986          5728 1451  151
26. H.Beer  Progress Report NEANDC(E)-272U,(5), p.8, June 1986    5728 1451  152
27. Y.N.Trofimov   Voprosy Atomnoy Nauki i Tekhniki, Serija:      5728 1451  153
    Jadernye Konstanty, v.4, p.10, 1987                           5728 1451  154
28. Y.N.Trofimov Proc. of the 1-st International Conf. on Neutron 5728 1451  155
    Physics, Kiev, 14-18 September 1987, v.3, p.331, Moscow 1988  5728 1451  156
29. P.G.Young, E.D.Arthur  A Preequilibrium Statistical Nuclear   5728 1451  157
    Model Code for Calculation of Cross Section and Emission      5728 1451  158
    Spectra. Report LA-6947, Los Alamos, 1977                     5728 1451  159
30. E.L.Trykov, G.Ya.Tertychnyi  Private communication, IPPE,     5728 1451  160
    Obninsk, May 1999                                             5728 1451  161
31. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 5728 1451  162
    st's Meeting on Evaluation and Processing of Covariance Data, 5728 1451  163
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  5728 1451  164
32. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          5728 1451  165
33. S.F.Mughabghab et al.  Termal Neutron Capture Cross Sections  5728 1451  166
    Resonance Integrals and G-factors, Report INDC(NDS)-440,      5728 1451  167
    IAEA, Vienna, February 2003                                   5728 1451  168
34. A.V.Ignatyuk et al.  Landolt Bornstein New Series, v.I/16A,   5728 1451  169
    Part 1, ed. H.Schopper, Springer, 1998, p.8-18                5728 1451  170
***************************************************************** 5728 1451  171
 The total and elastic cross-section files gave double counting   5728 1451  172
 of the cross-sections in the resonance region, these two files   5728 1451  173
 were modified for this library. The total and elastic cross-     5728 1451  174
 section files were taken from ENDF/B-VI Release 1.               5728 1451  175
***************************************************************** 5728 1451  176
 ***************** Program LINEAR (VERSION 2002-1) ***************5728 1451  177
 For All Data Greater than 1.0000E-10 barns in Absolute Value     5728 1451  178
 Data Linearized to Within an Accuracy of .100000000 per-cent     5728 1451  179
 ***************** Program RECENT (VERSION 2002-1) ***************5728 1451  180
 for All Data Greater than 1.0000E-10 barns in Absolute Value     5728 1451  181
 Data Linearized to within an Accuracy of .100000000 per-cent     5728 1451  182
 ***************** Program SIGMA1 (VERSION 2002-1) ***************5728 1451  183
 Data Doppler Broadened to 300.000000 Kelvin                      5728 1451  184
 for All Data Greater than 1.0000E-10 barns in Absolute Value     5728 1451  185
 Data Linearized to Within an Accuracy pf .100000000 per-cent     5728 1451  186
 ***************** Program FIXUP (Version 2002-1) ****************5728 1451  187
 Corrected ZA/AWR in All Sections-----------------------------Yes 5728 1451  188
 Corrected Thresholds-----------------------------------------Yes 5728 1451  189
 Extended Cross Sections to 20 MeV----------------------------No  5728 1451  190
 Allow Cross Section Deletion---------------------------------No  5728 1451  191
 Allow Cross Section Reconstruction---------------------------No  5728 1451  192
 Make All Cross Sections Non-Negative-------------------------Yes 5728 1451  193
 Delete Energies Not in Ascending Order-----------------------Yes 5728 1451  194
 Deleted Duplicate Points-------------------------------------Yes 5728 1451  195
 Check for Ascending MAT/MF/MT Order--------------------------Yes 5728 1451  196
 Check for Legal MF/MT Numbers--------------------------------Yes 5728 1451  197
 Allow Creation of Missing Sections---------------------------No  5728 1451  198
 Allow Insertion of Energy Points-----------------------------No  5728 1451  199
 Create Uniform Energy Grid-----------------------------------No  5728 1451  200
 Delete Section if Cross Section =0 at All Energies-----------Yes 5728 1451  201
 ***************** Program GROUPIE (VERSION 2002-1) **************5728 1451  202
 Unshielded Group Averages Using  640 Groups                      5728 1451  203
 Weighting Spectrum: Flat (Constant) Spectrum                     5728 1451  204
                                1        451        208          15728 1451  205
                                2        151          4          15728 1451  206
                                3        102        217          15728 1451  207
                               33        102         93          15728 1451  208
                                                                  5728 1  099999
                                                                  5728 0  0    0
 5.71390E+4 1.37713E+2          0          0          1          05728 2151    1
 5.71390E+4 1.00000E+0          0          0          1          05728 2151    2
 1.00000E-5 2.00000E+4          0          0          0          05728 2151    3
 3.50000E+0 6.24850E-1          0          0          0          05728 2151    4
                                                                  5728 2  099999
                                                                  5728 0  0    0
 5.71390E+4 1.37713E+2          0          0          0          05728 3102    1
 5.16110E+6 5.16110E+6          0          0          1        6415728 3102    2
        641          1                                            5728 3102    3
 .000100000 140.916130 .000105000 137.631355 .000110000 134.5107985728 3102    4
 .000115000 131.635331 .000120000 128.273838 .000127500 124.5443475728 3102    5
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 1.919730-3 1.889840-3 1.905170-3 1.601770-3 2.429640-3 1.576590-3572833102   22
 1.668390-3 0.000000+0 2.175610-3 2.372830-3 1.886870-3 1.806130-3572833102   23
 1.868630-3 1.545720-3 2.359900-3 1.537840-3 1.596370-3 0.000000+0572833102   24
 3.401930-3 2.444360-3 2.279290-3 2.370740-3 1.958590-3 2.989980-3572833102   25
 1.947030-3 2.026610-3 0.000000+0 2.267330-3 1.989240-3 1.949760-3572833102   26
 1.647100-3 2.494680-3 1.617180-3 1.718630-3 0.000000+0 2.152470-3572833102   27
 1.957590-3 1.558050-3 2.394310-3 1.564730-3 1.603350-3 0.000000+0572833102   28
 2.316060-3 1.674220-3 2.457340-3 1.587250-3 1.713230-3 0.000000+0572833102   29
 1.593640-3 2.044400-3 1.329110-3 1.370750-3 0.000000+0 4.144240-3572833102   30
 2.022380-3 2.119610-3 0.000000+0 1.549840-3 1.413310-3 0.000000+0572833102   31
 2.109240-3 0.000000+0 0.000000+0                                 572833102   32
 0.000000+0 0.000000+0          0          1         20         10572833102   33
 1.000000-5 0.000000+0 2.000000+2 2.345650-1 3.000000+2 3.374160-1572833102   34
 5.000000+2 2.215830-1 1.000000+3 1.670580-1 2.200000+3 9.646030-2572833102   35
 4.750000+3 1.530000-1 1.000000+4 2.445570-1 2.000000+4 0.000000+0572833102   36
 2.000000+7 0.000000+0                                            572833102   37
 0.000000+0 0.000000+0          1          5        325         25572833102   38
 1.000000-5 2.000000+4 4.000000+4 6.000000+4 8.000000+4 1.000000+5572833102   39
 2.000000+5 4.000000+5 6.000000+5 8.000000+5 1.000000+6 2.000000+6572833102   40
 3.000000+6 4.000000+6 5.000000+6 6.000000+6 7.000000+6 8.000000+6572833102   41
 9.000000+6 1.000000+7 1.200000+7 1.400000+7 1.600000+7 1.800000+7572833102   42
 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0572833102   43
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0572833102   44
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0572833102   45
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0572833102   46
 0.000000+0 4.373210-3 4.257650-3 4.190390-3 4.171110-3 4.148810-3572833102   47
 4.161440-3 3.619020-3 2.457010-3 1.445370-3 1.531360-3 8.031520-4572833102   48
 1.043540-3 1.200720-3 1.215670-3 1.172440-3 1.144140-3 1.175140-3572833102   49
 1.194820-3 1.182890-3 1.164400-3 1.307070-3 1.656590-3 1.955650-3572833102   50
 4.480110-3 4.497000-3 4.428800-3 4.177620-3 4.221330-3 3.656530-3572833102   51
 2.681970-3 1.606600-3 1.534450-3 8.608040-4 1.089460-3 1.307050-3572833102   52
 1.346700-3 1.277400-3 1.206560-3 1.240720-3 1.298720-3 1.259650-3572833102   53
 1.263580-3 1.392600-3 1.800410-3 2.077550-3 4.599630-3 4.605670-3572833102   54
 4.281150-3 4.258790-3 3.657810-3 2.547890-3 1.545390-3 1.541850-3572833102   55
 8.321630-4 1.060020-3 1.239290-3 1.268460-3 1.219390-3 1.174940-3572833102   56
 1.203660-3 1.237920-3 1.216770-3 1.206490-3 1.344290-3 1.716880-3572833102   57
 2.010090-3 4.742920-3 4.459620-3 4.291190-3 3.680760-3 2.327280-3572833102   58
 1.405120-3 1.562540-3 7.833310-4 1.022270-3 1.137270-3 1.142630-3572833102   59
 1.123670-3 1.124920-3 1.148600-3 1.141660-3 1.150330-3 1.115430-3572833102   60
 1.269810-3 1.584080-3 1.905780-3 4.605220-3 4.273810-3 3.718160-3572833102   61
 2.442330-3 1.420210-3 1.576280-3 8.058040-4 1.059450-3 1.197410-3572833102   62
 1.202570-3 1.168140-3 1.156000-3 1.186970-3 1.191920-3 1.190400-3572833102   63
 1.162340-3 1.315120-3 1.652630-3 1.970050-3 4.650030-3 3.785000-3572833102   64
 2.297160-3 1.362930-3 1.607150-3 8.019660-4 1.059440-3 1.177090-3572833102   65
 1.176780-3 1.153250-3 1.155170-3 1.183480-3 1.175920-3 1.183830-3572833102   66
 1.148000-3 1.307290-3 1.631080-3 1.960810-3 4.191990-3 3.716890-3572833102   67
 2.220880-3 1.586800-3 9.805650-4 1.200080-3 1.483940-3 1.552120-3572833102   68
 1.462450-3 1.354480-3 1.388990-3 1.478980-3 1.419310-3 1.438570-3572833102   69
 1.569140-3 2.050230-3 2.338900-3 6.013730-3 5.613730-3 1.648130-3572833102   70
 1.136680-3 1.104900-3 1.402660-3 1.605800-3 1.597240-3 1.462240-3572833102   71
 1.416670-3 1.530810-3 1.479160-3 1.507310-3 1.624740-3 2.135960-3572833102   72
 2.441640-3 9.596400-3 2.815990-3 9.693480-4 1.103800-3 1.023690-3572833102   73
 1.074000-3 1.221770-3 1.341960-3 1.284610-3 1.173230-3 1.279090-3572833102   74
 1.172100-3 1.398410-3 1.645660-3 2.135440-3 5.787750-3 1.657310-3572833102   75
 2.205260-3 2.617220-3 2.669340-3 2.556840-3 2.464170-3 2.529390-3572833102   76
 2.598890-3 2.555700-3 2.531740-3 2.824340-3 3.602280-3 4.223850-3572833102   77
 3.633110-3 4.267780-3 4.641970-3 4.800960-3 4.840430-3 4.849650-3572833102   78
 4.869290-3 4.846410-3 4.898520-3 4.754970-3 5.395380-3 6.744660-3572833102   79
 8.112480-3 5.966690-3 6.739140-3 6.708790-3 6.302550-3 5.970150-3572833102   80
 6.109290-3 6.347980-3 6.211780-3 6.184360-3 6.864580-3 8.790700-3572833102   81
 1.027570-2 8.063440-3 8.221160-3 7.668950-3 7.008490-3 6.952500-3572833102   82
 7.356010-3 7.186020-3 7.197940-3 7.924890-3 1.020480-2 1.189920-2572833102   83
 8.717380-3 8.454870-3 7.820360-3 7.406320-3 7.592980-3 7.632630-3572833102   84
 7.502130-3 8.380310-3 1.061400-2 1.263480-2 8.701350-3 8.438740-3572833102   85
 7.794530-3 7.432500-3 7.718140-3 7.386790-3 8.453560-3 1.047490-2572833102   86
 1.273760-2 8.742840-3 8.359810-3 7.410060-3 7.578710-3 7.242570-3572833102   87
 8.353630-3 1.032520-2 1.250930-2 8.829350-3 8.074660-3 7.385510-3572833102   88
 7.413820-3 8.264620-3 1.053090-2 1.236150-2 8.774640-3 7.717270-3572833102   89
 7.483530-3 8.327420-3 1.057710-2 1.255790-2 8.949390-3 7.595650-3572833102   90
 8.383470-3 1.059340-2 1.256530-2 8.513730-3 8.420100-3 1.022820-2572833102   91
 1.243340-2 1.077640-2 1.217860-2 1.364410-2 1.682810-2 1.804110-2572833102   92
 2.429660-2                                                       572833102   93
                                                                  572833  099999
                                                                  5728 0  0    0
                                                                     0 0  0    0
 5.91410E+4 1.39697E+2          0          0         34         105925 1451    1
 0.0        0.0                 0          0          0          65925 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20025925 1451    3
 3.00000E+2 0.0                 1          0        122          45925 1451    4
 59-Pr-141 FEI        EVAL-Jan97 K.I.Zolotarev et al.             5925 1451    5
                      DIST-Feb2004                                5925 1451    6
----IRDF-2002         MATERIAL 5925                               5925 1451    7
-----INCIDENT NEUTRON DATA                                        5925 1451    8
------ENDF-6 FORMAT                                               5925 1451    9
***************************************************************** 5925 1451   10
 59-PR-141 FEI        EVAL-Jan97 K.I.Zolotarev et al.             5925 1451   11
                      DIST-Jan02                       20020123   5925 1451   12
----BROND-2           MATERIAL 5925                               5925 1451   13
-----INCIDENT NEUTRON DATA                                        5925 1451   14
------ENDF-6 FORMAT                                               5925 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    5925 1451   16
***************************************************************** 5925 1451   17
Authors of evaluation: K.Zolotarev, V.Manokhin, A.Pashchenko      5925 1451   18
***************************************************************** 5925 1451   19
MF= 3                                                             5925 1451   20
MT= 16 - Pr-141(n,2n)Pr-140 reaction                              5925 1451   21
--------------------------------------                            5925 1451   22
    Excitation function for the  Pr-141(n,2n)Pr-140  reaction in  5925 1451   23
the energy region from threshold to 20 MeV was evaluated by means 5925 1451   24
of statistical analysis of experimental cross section data [1-19] 5925 1451   25
and data from systematics  of (n,2n)  excitation function [20] in 5925 1451   26
the energy regions 9.5 - 12.0 MeV and 18.0 - 20.0 MeV.            5925 1451   27
    All experimental data were renormalized to  the new standards 5925 1451   28
for monitor reactions cross sections and decay data.              5925 1451   29
    The final procedure of evaluation has been carried out within 5925 1451   30
the framework of generalized least squares method. Rational func- 5925 1451   31
tion was used as model function [21].  Calculations was performed 5925 1451   32
by means of Pade-2 code [22].                                     5925 1451   33
    U-235 thermal fission [23]   and   Cf-252 spontaneous fission 5925 1451   34
neutron spectra [24]  averaged cross-sections calculated from the 5925 1451   35
evaluated Pr141(n,2n)Pr140 excitation function are the following: 5925 1451   36
                                                                  5925 1451   37
         --------------------------------------------             5925 1451   38
              TYPE OF SPECTRUM     I  CS>, mb (calc.)             5925 1451   39
         --------------------------I-----------------             5925 1451   40
         U-235  neutron  fission   I     1.0922                   5925 1451   41
         CF-252 spontan. fission   I     1.9843                   5925 1451   42
                                                                  5925 1451   43
MF=33                                                             5925 1451   44
MT= 16 -(n,2n) cross section cov. matrix                          5925 1451   45
----------------------------------------                          5925 1451   46
    Uncertainties in the evaluated excitation function for the re-5925 1451   47
action Pr-141(n,2n)Pr-140 are given in the form of relative cova- 5925 1451   48
riance matrix for the 18-neutron energy groups (LB=5). Covariance 5925 1451   49
matrix  of  uncertainties  was  calculated  simultaneously  with  5925 1451   50
recommended cross section data by means of PADE-2 code.           5925 1451   51
    Eigenvalues  of the  6-th digits  relative covariance matrix  5925 1451   52
given in the 33-file are the following:                           5925 1451   53
                                                                  5925 1451   54
    6.47369E-06    6.50089E-06    6.56924E-06    6.70314E-06      5925 1451   55
    6.90792E-06    7.20594E-06    7.64163E-06    8.30022E-06      5925 1451   56
    9.35563E-06    1.12079E-05    1.49213E-05    2.36154E-05      5925 1451   57
    4.48092E-05    3.28699E-04    6.81059E-03    1.70941E-02      5925 1451   58
    2.55798E-02    1.53270E-01                                    5925 1451   59
                                                                  5925 1451   60
References :                                                      5925 1451   61
 1. E.B.Paul, R.L.Clarke  Canadian J. Phys., v.31,p.267, 1953     5925 1451   62
 2. J.M.Ferguson, W.E.Thompson  Phys. Rev., v.118, p.228, 1960    5925 1451   63
 3. R.G.Wille, R.W.Fink  Phys. Rev., v.118, p.242, 1960           5925 1451   64
 4. L.A.Rayburn  Phys. Rev., v.122, p.168, 1961                   5925 1451   65
 5. C.S.Khurana, H.S.Hans  Nucl. Phys., v.28, p.560, 1961         5925 1451   66
 6. D.R.Koehler, W.L.Alford  Report NP-11667, 1962                5925 1451   67
 7. M.Cevolani, S.Petralia  Nucl. Sci. Eng., v.26, p.1328, 1962   5925 1451   68
 8. L.A.Rayburn  Bull. American Phys. Soc., v.8, p.60, Jan. 1963  5925 1451   69
 9. M.P.Menon, M.Y.Cuypers  Phys. Rev., v.156, p.1340, 1967       5925 1451   70
10. P.Cuzzocrea e.a. Nuovo Cimento, Sec.B, v.52, n.2, p.476, 1967 5925 1451   71
11. M.Bormann e.a.  Nucl. Phys., Sec.A, v.115, p.309, July 1968   5925 1451   72
12. G.Peto e.a.  Acta Physica Hung., v.24, p.93, April 1968       5925 1451   73
13. A.Chatterjee e.a.  Proc. of 12th Nucl. Phys. and Solid State  5925 1451   74
    Phys. Sympos., Roorkee, India, 28-31 December 1969, v.2,p.117 5925 1451   75
14. A.Bari   Dissertation Abstracts, sec.B, v.32, p.5091, 1972    5925 1451   76
15. J.Araminowicz, J.Dresler  Prog. Rep. INR-1464, p.14, May 1973 5925 1451   77
16. R.A.Sigg, P.K.Kuroda  Inorg. Nucl. Chem., v.37, p.631, 1975   5925 1451   78
17. M.Valkonen  Report JU-RR-1/1976, Jyvaeskylae University, 1976 5925 1451   79
18. S.Murahira et al.  Report INDC(JPN)-175/U, p.171, Nov. 1995   5925 1451   80
19. Y.Kasugai, Y.Ikeda, Y.Uno Proc. of Int. Conf. on Nuclear Data 5925 1451   81
    for Science and Technology, Trieste, Italy, 19-24 May 1997,   5925 1451   82
    v.1, p.635                                                    5925 1451   83
20. V.N.Manokhin  Report INDC(CCP)-397, IAEA, Vienna, 1997        5925 1451   84
21. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 5925 1451   85
    st's Meeting on Evaluation and Processing of Covariance Data, 5925 1451   86
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  5925 1451   87
22. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          5925 1451   88
23. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 5925 1451   89
    Library, MAT=9228, MF=5, MT=18, eval. April 1989              5925 1451   90
24. W.Mannhart   IAEA-TECDOC-410, p.158, Vienna, 1987             5925 1451   91
******************************************************************5925 1451   92
 The Q values and threshold energies were updated prior to pro-   5925 1451   93
 cessing through the codes to comply with the values obtained     5925 1451   94
 using the NNDC calculation program which is based on the 1995    5925 1451   95
 Update to the Atomic mass Evaluation.                            5925 1451   96
                                                                  5925 1451   97
 File 2 added to the pointwise file containing only the effective 5925 1451   98
 scattering radius with no resonance parameters given.            5925 1451   99
 Taken from ENDF/B-VI                                             5925 1451  100
******************************************************************5925 1451  101
 ***************** Program LINEAR (VERSION 2002-1) ***************5925 1451  102
 For All Data Greater than 1.0000E-10 barns in Absolute Value     5925 1451  103
 Data Linearized to Within an Accuracy of .100000000 per-cent     5925 1451  104
 ***************** Program SIGMA1 (VERSION 2002-1) ***************5925 1451  105
 Data Doppler Broadened to 300.000000 Kelvin                      5925 1451  106
 for All Data Greater than 1.0000E-10 barns in Absolute Value     5925 1451  107
 Data Linearized to Within an Accuracy pf .100000000 per-cent     5925 1451  108
 ***************** Program FIXUP (Version 2002-1) ****************5925 1451  109
 Corrected ZA/AWR in All Sections-----------------------------Yes 5925 1451  110
 Corrected Thresholds-----------------------------------------Yes 5925 1451  111
 Extended Cross Sections to 20 MeV----------------------------No  5925 1451  112
 Allow Cross Section Deletion---------------------------------No  5925 1451  113
 Allow Cross Section Reconstruction---------------------------No  5925 1451  114
 Make All Cross Sections Non-Negative-------------------------Yes 5925 1451  115
 Delete Energies Not in Ascending Order-----------------------Yes 5925 1451  116
 Deleted Duplicate Points-------------------------------------Yes 5925 1451  117
 Check for Ascending MAT/MF/MT Order--------------------------Yes 5925 1451  118
 Check for Legal MF/MT Numbers--------------------------------Yes 5925 1451  119
 Allow Creation of Missing Sections---------------------------No  5925 1451  120
 Allow Insertion of Energy Points-----------------------------No  5925 1451  121
 Create Uniform Energy Grid-----------------------------------No  5925 1451  122
 Delete Section if Cross Section =0 at All Energies-----------Yes 5925 1451  123
 ***************** Program GROUPIE (VERSION 2002-1) **************5925 1451  124
 Unshielded Group Averages Using  640 Groups                      5925 1451  125
 Weighting Spectrum: Flat (Constant) Spectrum                     5925 1451  126
                                1        451        130          15925 1451  127
                                2        151          4          15925 1451  128
                                3         16         39          15925 1451  129
                               33         16         38          15925 1451  130
                                                                  5925 1  099999
                                                                  5925 0  0    0
 5.91410E+4 1.39697E+2          0          0          1          05925 2151    1
 5.914100+4 1.000000+0          0          0          1          05925 2151    2
 1.000000-5 1.004920+4          0          0          0          05925 2151    3
 2.500000+0 4.930000-1          0          0          0          05925 2151    4
                                                                  5925 2  099999
                                                                  5925 0  0    0
 5.91410E+4 1.39697E+2          0          0          0          05925 3 16    1
-9.39700E+6-9.39700E+6          0          0          1        1075925 3 16    2
        107          1                                            5925 3 16    3
 9400000.00 .000102039 9500000.00 .004115304 9600000.00 .0164385955925 3 16    4
 9700000.00 .038856950 9800000.00 .070499450 9900000.00 .1102883505925 3 16    5
 10000000.0 .157013000 10100000.0 .209402000 10200000.0 .2661885005925 3 16    6
 10300000.0 .326164000 10400000.0 .388315750 10500000.0 .4513412505925 3 16    7
 10600000.0 .514366750 10700000.0 .577392250 10800000.0 .6395045005925 3 16    8
 10900000.0 .699850500 11000000.0 .758343500 11100000.0 .8147340005925 3 16    9
 11200000.0 .868854500 11300000.0 .920604500 11400000.0 .9699370005925 3 16   10
 11500000.0 1.01684800 11600000.0 1.06136500 11700000.0 1.102987505925 3 16   11
 11800000.0 1.14290250 11900000.0 1.18068500 12000000.0 1.216335005925 3 16   12
 12100000.0 1.25004500 12200000.0 1.28181500 12300000.0 1.311847505925 3 16   13
 12400000.0 1.34014250 12500000.0 1.36689000 12600000.0 1.392090005925 3 16   14
 12700000.0 1.41561500 12800000.0 1.43746500 12900000.0 1.459315005925 3 16   15
 13000000.0 1.47946167 13100000.0 1.49790500 13200000.0 1.516348335925 3 16   16
 13300000.0 1.53338000 13400000.0 1.54900000 13500000.0 1.564620005925 3 16   17
 13600000.0 1.57889750 13700000.0 1.59183250 13800000.0 1.604767505925 3 16   18
 13900000.0 1.61770250 14000000.0 1.62927600 14100000.0 1.639488005925 3 16   19
 14200000.0 1.64970000 14300000.0 1.65991200 14400000.0 1.670124005925 3 16   20
 14500000.0 1.67916600 14600000.0 1.68703800 14700000.0 1.694910005925 3 16   21
 14800000.0 1.70278200 14900000.0 1.71065400 15000000.0 1.717540835925 3 16   22
 15100000.0 1.72344250 15200000.0 1.72934417 15300000.0 1.735245835925 3 16   23
 15400000.0 1.74114750 15500000.0 1.74704917 15600000.0 1.752039295925 3 16   24
 15700000.0 1.75611786 15800000.0 1.76019643 15900000.0 1.764275005925 3 16   25
 16000000.0 1.76835357 16100000.0 1.77243214 16200000.0 1.776510715925 3 16   26
 16300000.0 1.77971063 16400000.0 1.78203188 16500000.0 1.784353135925 3 16   27
 16600000.0 1.78667438 16700000.0 1.78899563 16800000.0 1.791316885925 3 16   28
 16900000.0 1.79363813 17000000.0 1.79595938 17100000.0 1.797471675925 3 16   29
 17200000.0 1.79817500 17300000.0 1.79887833 17400000.0 1.799581675925 3 16   30
 17500000.0 1.80028500 17600000.0 1.80098833 17700000.0 1.800834175925 3 16   31
 17800000.0 1.79982250 17900000.0 1.79881083 18000000.0 1.797799175925 3 16   32
 18100000.0 1.79678750 18200000.0 1.79577583 18300000.0 1.793587005925 3 16   33
 18400000.0 1.79022100 18500000.0 1.78685500 18600000.0 1.783489005925 3 16   34
 18700000.0 1.78012300 18800000.0 1.77536333 18900000.0 1.769210005925 3 16   35
 19000000.0 1.76305667 19100000.0 1.75515667 19200000.0 1.745510005925 3 16   36
 19300000.0 1.73586333 19400000.0 1.72389250 19500000.0 1.709597505925 3 16   37
 19600000.0 1.69321500 19700000.0 1.67284000 19800000.0 1.648080005925 3 16   38
 19900000.0 1.61751500 20000000.0 0.0                             5925 3 16   39
                                                                  5925 3  099999
                                                                  5925 0  0    0
 5.91410E+4 1.39697E+2          0          0          0          1592533 16    1
 0.000000+0 0.000000+0          0         16          0          1592533 16    2
 0.000000+0 0.000000+0          1          5        210         20592533 16    3
 1.000000-5 9.400000+6 1.050000+7 1.100000+7 1.150000+7 1.200000+7592533 16    4
 1.250000+7 1.300000+7 1.350000+7 1.400000+7 1.450000+7 1.500000+7592533 16    5
 1.550000+7 1.600000+7 1.650000+7 1.700000+7 1.750000+7 1.800000+7592533 16    6
 1.850000+7 1.900000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0592533 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0592533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0592533 16    9
 0.000000+0 0.000000+0 0.000000+0 7.629710-2 5.270640-2 3.376320-2592533 16   10
 2.074520-2 1.252350-2 7.563810-3 4.706180-3 3.188710-3 2.533760-3592533 16   11
 2.446920-3 2.749080-3 3.334790-3 4.148410-3 5.171510-3 6.419360-3592533 16   12
 7.945970-3 9.861990-3 1.237550-2 4.016490-2 2.809550-2 1.900490-2592533 16   13
 1.265780-2 8.366950-3 5.519320-3 3.674800-3 2.539500-3 1.923500-3592533 16   14
 1.707930-3 1.823370-3 2.237300-3 2.948350-3 3.986210-3 5.417190-3592533 16   15
 7.354640-3 9.962330-3 2.145550-2 1.571000-2 1.127530-2 7.970050-3592533 16   16
 5.552600-3 3.813640-3 2.597590-3 1.796650-3 1.340690-3 1.189230-3592533 16   17
 1.326580-3 1.760550-3 2.524460-3 3.682770-3 5.338130-3 7.621620-3592533 16   18
 1.236030-2 9.413210-3 7.029290-3 5.152190-3 3.707030-3 2.623120-3592533 16   19
 1.845220-3 1.335170-3 1.071090-3 1.046710-3 1.272260-3 1.777090-3592533 16   20
 2.614640-3 3.867430-3 5.635080-3 7.582390-3 5.943050-3 4.583860-3592533 16   21
 3.484360-3 2.620050-3 1.966010-3 1.503080-3 1.220170-3 1.115420-3592533 16   22
 1.197700-3 1.489140-3 2.029030-3 2.877480-3 4.106360-3 4.916750-3592533 16   23
 3.993780-3 3.224900-3 2.597250-3 2.101980-3 1.730500-3 1.477540-3592533 16   24
 1.342690-3 1.331920-3 1.459470-3 1.750620-3 2.244570-3 2.989940-3592533 16   25
 3.456170-3 2.967610-3 2.561130-3 2.226210-3 1.959650-3 1.758980-3592533 16   26
 1.623750-3 1.556590-3 1.564460-3 1.660280-3 1.865240-3 2.208980-3592533 16   27
 2.737410-3 2.515350-3 2.327170-3 2.163680-3 2.023420-3 1.905210-3592533 16   28
 1.808580-3 1.734270-3 1.685040-3 1.667360-3 1.695630-3 2.469300-3592533 16   29
 2.400280-3 2.330770-3 2.251710-3 2.160910-3 2.055290-3 1.930710-3592533 16   30
 1.782030-3 1.604310-3 1.399900-3 2.450900-3 2.455830-3 2.435060-3592533 16   31
 2.378170-3 2.280110-3 2.133270-3 1.926860-3 1.647670-3 1.288780-3592533 16   32
 2.543100-3 2.568940-3 2.550460-3 2.474410-3 2.331110-3 2.106380-3592533 16   33
 1.781790-3 1.343610-3 2.656650-3 2.673470-3 2.633140-3 2.518610-3592533 16   34
 2.314590-3 2.000500-3 1.558140-3 2.749450-3 2.752370-3 2.692880-3592533 16   35
 2.550410-3 2.305410-3 1.937640-3 2.834100-3 2.852250-3 2.816520-3592533 16   36
 2.705480-3 2.499580-3 3.001600-3 3.118840-3 3.217400-3 3.275390-3592533 16   37
 3.472370-3 3.866030-3 4.312850-3 4.687830-3 5.673930-3 7.407790-3592533 16   38
                                                                  592533  099999
                                                                  5925 0  0    0
                                                                     0 0  0    0
 6.40000E+4 1.55901E+2         -1          0         34         106400 1451    1
 0.0        0.0                 0          0          0          66400 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20026400 1451    3
 3.00000E+2 0.0                 1          0         59          36400 1451    4
 64-Gd-  0  NDS       IAEA-JAN04                                  6400 1451    5
                      DIST-Feb2004                                6400 1451    6
----IRDF-2002                                                     6400 1451    7
-----INCIDENT NEUTRON DATA                                        6400 1451    8
------ENDF-6 FORMAT                                               6400 1451    9
 *****************************************************************6400 1451   10
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************6400 1451   11
DOSIMETRY  Assembled at NDS from the ENDF/B-VI evaluations for    6400 1451   12
           64-Gd-152,154,155,156,157,158 and 160. The files       6400 1451   13
           were processed through the 2002 pre-processing codes   6400 1451   14
           LINEAR,RECENT,SIGMA1 and FIXUP to produce pointwise    6400 1451   15
           files prior to input to MIXER.                         6400 1451   16
                                                                  6400 1451   17
MIXER INPUT FILE                                                  6400 1451   18
 ***************** Program MIXER (VERSION 2002-1) ****************6400 1451   19
GADOLINIUM,MET.   DENSITY  7.901 G/CC. CONSTITUENTS:  160-21.86   6400 1451   20
 158-24.84, 152-0.2, 154-2.18, 155-14.8,156-20.47, 157-15.65      6400 1451   21
 ----------------------------------------                         6400 1451   22
 Composition                                                      6400 1451   23
 ----------------------------------------                         6400 1451   24
 Isotope MF   MT  Atom-Fract     Grams/cc                         6400 1451   25
 ----------------------------------------                         6400 1451   26
   64152  3    1  .001999808   .015264700                         6400 1451   27
   64154  3    1  .021799790   .168591500                         6400 1451   28
   64155  3    1  .147999470   1.15202110                         6400 1451   29
   64156  3    1  .204700250   1.60365810                         6400 1451   30
   64157  3    1  .156499785   1.23392290                         6400 1451   31
   64158  3    1  .248400703   1.97099140                         6400 1451   32
   64160  3    1  .218600194   1.75653450                         6400 1451   33
 ----------------------------------------                         6400 1451   34
   64000  3    1  1.00000000   7.90098420                         6400 1451   35
 ----------------------------------------                         6400 1451   36
 ***************** Program MIXER (VERSION 2002-1) ****************6400 1451   37
GADOLINIUM,MET.   DENSITY  7.901 G/CC. CONSTITUENTS:  160-21.86   6400 1451   38
 158-24.84, 152-0.2, 154-2.18, 155-14.8,156-20.47, 157-15.65      6400 1451   39
 ----------------------------------------                         6400 1451   40
 Composition                                                      6400 1451   41
 ----------------------------------------                         6400 1451   42
 Isotope MF   MT  Atom-Fract     Grams/cc                         6400 1451   43
 ----------------------------------------                         6400 1451   44
   64152  3  102  .001999808   .015264700                         6400 1451   45
   64154  3  102  .021799790   .168591500                         6400 1451   46
   64155  3  102  .147999470   1.15202110                         6400 1451   47
   64156  3  102  .204700250   1.60365810                         6400 1451   48
   64157  3  102  .156499785   1.23392290                         6400 1451   49
   64158  3  102  .248400703   1.97099140                         6400 1451   50
   64160  3  102  .218600194   1.75653450                         6400 1451   51
 ----------------------------------------                         6400 1451   52
   64000  3  102  1.00000000   7.90098420                         6400 1451   53
 ----------------------------------------                         6400 1451   54
 *****************************************************************6400 1451   55
                                                                  6400 1451   56
                                                                  6400 1451   57
                                                                  6400 1451   58
                                                                  6400 1451   59
 *****************************************************************6400 1451   60
 ***************** Program GROUPIE (VERSION 2002-1) **************6400 1451   61
 Unshielded Group Averages Using  640 Groups                      6400 1451   62
 Weighting Spectrum: Flat (Constant) Spectrum                     6400 1451   63
                                1        451         66          06400 1451   64
                                3          1        217          06400 1451   65
                                3        102        217          06400 1451   66
                                                                  6400 1  099999
                                                                  6400 0  0    0
 6.40000E+4 1.55901E+2          0          0          0          06400 3  1    1
 0.0        0.0                 0          0          1        6416400 3  1    2
        641          1                                            6400 3  1    3
 .000100000 589975.698 .000105000 576263.743 .000110000 563237.9996400 3  1    4
 .000115000 551236.393 .000120000 537207.265 .000127500 521643.7756400 3  1    5
 .000135000 507426.347 .000142500 494362.490 .000150000 480225.4426400 3  1    6
 .000160000 465500.570 .000170000 452104.974 .000180000 439810.8086400 3  1    7
 .000190000 428373.756 .000200000 417933.482 .000210000 408112.2456400 3  1    8
 .000220000 398991.461 .000230000 390518.607 .000240000 380574.7966400 3  1    9
 .000255000 369650.434 .000270000 361222.513 .000280000 351842.7476400 3  1   10
 .000300000 340406.989 .000320000 330055.677 .000340000 320578.4706400 3  1   11
 .000360000 311852.081 .000380000 303888.913 .000400000 295589.4916400 3  1   12
 .000425000 287099.710 .000450000 279345.803 .000475000 272240.2776400 3  1   13
 .000500000 265560.337 .000525000 259458.199 .000550000 253695.5916400 3  1   14
 .000575000 248338.457 .000600000 242850.160 .000630000 237206.3286400 3  1   15
 .000660000 232045.336 .000690000 227095.998 .000720000 221833.3046400 3  1   16
 .000760000 216193.334 .000800000 210960.030 .000840000 206167.7206400 3  1   17
 .000880000 201614.870 .000920000 197444.084 .000960000 193451.9046400 3  1   18
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 .001600000 150679.577 .001700000 146543.973 .001800000 142724.4306400 3  1   22
 .001900000 139242.265 .002000000 136018.231 .002100000 132996.6396400 3  1   23
 .002200000 130235.002 .002300000 127597.042 .002400000 124594.0286400 3  1   24
 .002550000 121263.966 .002700000 118663.917 .002800000 115847.2726400 3  1   25
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 .003600000 103799.615 .003800000 101394.497 .004000000 98926.89826400 3  1   27
 .004250000 96446.8108 .004500000 94116.3537 .004750000 92031.69016400 3  1   28
 .005000000 90052.7594 .005250000 88259.9430 .005500000 86584.14836400 3  1   29
 .005750000 84985.7159 .006000000 83423.3912 .006300000 81754.47316400 3  1   30
 .006600000 80285.8467 .006900000 78856.9970 .007200000 77345.67306400 3  1   31
 .007600000 75741.3503 .008000000 74259.2536 .008400000 72905.22576400 3  1   32
 .008800000 71606.4403 .009200000 70452.3569 .009600000 69310.09086400 3  1   33
 .010000000 68168.2878 .010500000 66961.4528 .011000000 65835.29176400 3  1   34
 .011500000 64812.6881 .012000000 63580.7132 .012750000 62262.54436400 3  1   35
 .013500000 61017.9283 .014250000 59899.8789 .015000000 58665.31746400 3  1   36
 .016000001 57381.5012 .017000001 56196.4155 .017999999 55083.30886400 3  1   37
 .018999999 54053.0189 .020000000 53067.6345 .021000000 52144.11396400 3  1   38
 .022000000 51273.0324 .023000000 50401.9583 .024000000 49329.60956400 3  1   39
 .025500000 48142.7567 .027000001 47179.1975 .028000001 46024.12316400 3  1   40
 .029999999 44500.3126 .032000002 43015.3586 .034000002 41552.58366400 3  1   41
 .035999998 40100.7539 .037999999 38649.2567 .039999999 37022.65226400 3  1   42
 .042500000 35228.1518 .045000002 33470.3801 .047499999 31736.19736400 3  1   43
 .050000001 30059.6715 .052499998 28409.0926 .055000000 26820.79836400 3  1   44
 .057500001 25286.7754 .059999999 23676.4725 .063000001 22016.52586400 3  1   45
 .066000000 20454.6852 .068999998 18989.8397 .071999997 17413.42796400 3  1   46
 .075999998 15771.9502 .079999998 14291.7495 .083999999 12962.05766400 3  1   47
 .088000000 11768.9216 .092000000 10697.5306 .096000001 9743.521686400 3  1   48
 .100000001 8791.29030 .104999997 7861.73990 .109999999 7051.680946400 3  1   49
 .115000002 6344.97492 .119999997 5586.76237 .127499998 4821.438736400 3  1   50
 .135000005 4187.76665 .142499998 3659.95592 .150000006 3152.561666400 3  1   51
 .159999996 2680.10654 .170000002 2298.61194 .180000007 1987.812616400 3  1   52
 .189999998 1731.80601 .200000003 1518.87476 .209999993 1340.324736400 3  1   53
 .219999999 1189.70658 .230000004 1061.56016 .239999995 927.6548976400 3  1   54
 .254999995 795.424418 .270000011 704.201722 .280000001 614.3485966400 3  1   55
 .300000012 516.932409 .319999993 440.064304 .340000004 378.5042506400 3  1   56
 .360000014 328.611225 .379999995 287.669565 .400000006 249.9390966400 3  1   57
 .425000012 215.792288 .449999988 188.059115 .474999994 165.2783926400 3  1   58
 .500000000 146.367689 .524999976 130.518725 .550000012 117.1220506400 3  1   59
 .574999988 105.735374 .600000024 95.0807037 .629999995 85.24093946400 3  1   60
 .660000026 76.9287302 .689999998 69.8538784 .720000029 62.88688686400 3  1   61
 .759999990 56.2288703 .800000012 50.7023383 .839999974 46.08568046400 3  1   62
 .879999995 42.2131854 .920000017 38.9203473 .959999979 36.12422896400 3  1   63
 1.00000000 33.4721011 1.04999995 31.0180402 1.10000002 29.00273926400 3  1   64
 1.14999998 27.3535870 1.20000005 25.7500083 1.27499998 24.36919116400 3  1   65
 1.35000002 23.5459552 1.42499995 23.2845714 1.50000000 23.84482546400 3  1   66
 1.60000002 26.1504101 1.70000005 32.4331292 1.79999995 53.78486416400 3  1   67
 1.89999998 155.165344 2.00000000 180.836068 2.09999990 77.07810556400 3  1   68
 2.20000005 72.7161857 2.29999995 122.584743 2.40000010 562.9680816400 3  1   69
 2.54999995 807.932885 2.70000005 278.975585 2.79999995 184.9995716400 3  1   70
 3.00000000 35.5484623 3.20000005 19.5117011 3.40000010 18.28310716400 3  1   71
 3.59999990 17.2413804 3.79999995 10.3079106 4.00000000 8.794554646400 3  1   72
 4.25000000 8.05001316 4.50000000 7.70017817 4.75000000 7.633698076400 3  1   73
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 6.59999990 19.3480461 6.90000010 11.8316475 7.19999981 21.19399026400 3  1   76
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 8.80000019 6.25730918 9.19999981 6.06853531 9.60000038 12.22528286400 3  1   78
 10.0000000 11.9591698 10.5000000 6.13540176 11.0000000 15.84106066400 3  1   79
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 13.5000000 8.60534329 14.2500000 66.2241929 15.0000000 9.265762166400 3  1   81
 16.0000000 290.499829 17.0000000 32.9229550 18.0000000 9.258952006400 3  1   82
 19.0000000 72.7887372 20.0000000 346.790026 21.0000000 197.8306356400 3  1   83
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 42.5000000 71.8714886 45.0000000 33.1826967 47.5000000 85.92709666400 3  1   88
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 3600.00000 18.6352557 3800.00000 21.8262933 4000.00000 14.64195546400 3  1  117
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 5000.00000 14.2057028 5250.00000 13.7991348 5500.00000 17.33480146400 3  1  119
 5750.00000 17.5389078 6000.00000 12.4630288 6300.00000 20.30633486400 3  1  120
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 13500.0000 12.9605378 14250.0000 12.8360389 15000.0000 12.68510826400 3  1  126
 16000.0000 12.5217112 17000.0000 12.3704396 18000.0000 12.23315166400 3  1  127
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 25500.0000 11.4594611 27000.0000 11.3541697 28000.0000 11.23707246400 3  1  130
 30000.0000 11.0961046 32000.0000 10.9648458 34000.0000 10.84195626400 3  1  131
 36000.0000 10.7410115 38000.0000 10.6492020 40000.0000 10.54942476400 3  1  132
 42500.0000 10.4470982 45000.0000 10.3581264 47500.0000 10.27274246400 3  1  133
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 57500.0000 10.0124601 60000.0000 9.76443676 63000.0000 9.689982456400 3  1  135
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 100000.000 8.48682498 105000.000 8.42252774 110000.000 8.361276256400 3  1  139
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 135000.000 8.11419980 142500.000 8.05589435 150000.000 7.996959396400 3  1  141
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 2500000.00 .057141393 2600000.00 .054710812 2700000.00 .0523201196400 3102  159
 2800000.00 .049611054 2900000.00 .047026440 3000000.00 .0445149146400 3102  160
 3100000.00 .042084889 3200000.00 .039822789 3300000.00 .0377065136400 3102  161
 3400000.00 .035722156 3500000.00 .033858365 3600000.00 .0321133366400 3102  162
 3700000.00 .030493172 3800000.00 .028982027 3900000.00 .0275765426400 3102  163
 4000000.00 .026219435 4100000.00 .024876597 4200000.00 .0236320366400 3102  164
 4300000.00 .022495919 4400000.00 .021435397 4500000.00 .0204442786400 3102  165
 4600000.00 .019501871 4700000.00 .018624202 4800000.00 .0178237516400 3102  166
 4900000.00 .017074183 5000000.00 .015772308 5100000.00 .0140780706400 3102  167
 5200000.00 .012622355 5300000.00 .011368583 5400000.00 .0102818246400 3102  168
 5500000.00 .009336237 5600000.00 .008511148 5700000.00 .0077866516400 3102  169
 5800000.00 .007147537 5900000.00 .006582712 6000000.00 .0060694126400 3102  170
 6100000.00 .005600859 6200000.00 .005183362 6300000.00 .0048076596400 3102  171
 6400000.00 .004470193 6500000.00 .004165613 6600000.00 .0038901806400 3102  172
 6700000.00 .003640278 6800000.00 .003413231 6900000.00 .0032058246400 3102  173
 7000000.00 .003065946 7100000.00 .002986322 7200000.00 .0029105346400 3102  174
 7300000.00 .002839559 7400000.00 .002772072 7500000.00 .0027092016400 3102  175
 7600000.00 .002648953 7700000.00 .002591789 7800000.00 .0025376516400 3102  176
 7900000.00 .002486687 8000000.00 .002437506 8100000.00 .0023905776400 3102  177
 8200000.00 .002346184 8300000.00 .002303809 8400000.00 .0022636646400 3102  178
 8500000.00 .002224818 8600000.00 .002188145 8700000.00 .0021529156400 3102  179
 8800000.00 .002118685 8900000.00 .002085983 9000000.00 .0020523506400 3102  180
 9100000.00 .002018307 9200000.00 .001985613 9300000.00 .0019544866400 3102  181
 9400000.00 .001925030 9500000.00 .001897835 9600000.00 .0018721106400 3102  182
 9700000.00 .001847179 9800000.00 .001822937 9900000.00 .0017996956400 3102  183
 10000000.0 .001791199 10100000.0 .001797257 10200000.0 .0018037856400 3102  184
 10300000.0 .001810747 10400000.0 .001818129 10500000.0 .0018263526400 3102  185
 10600000.0 .001835104 10700000.0 .001844113 10800000.0 .0018532976400 3102  186
 10900000.0 .001862688 11000000.0 .001872472 11100000.0 .0018826206400 3102  187
 11200000.0 .001892899 11300000.0 .001903236 11400000.0 .0019136906400 3102  188
 11500000.0 .001924459 11600000.0 .001935424 11700000.0 .0019464346400 3102  189
 11800000.0 .001957509 11900000.0 .001968591 12000000.0 .0019806366400 3102  190
 12100000.0 .001993613 12200000.0 .002006590 12300000.0 .0020195666400 3102  191
 12400000.0 .002032556 12500000.0 .002045583 12600000.0 .0020586126400 3102  192
 12700000.0 .002071640 12800000.0 .002084669 12900000.0 .0020977096400 3102  193
 13000000.0 .002110872 13100000.0 .002124147 13200000.0 .0021374226400 3102  194
 13300000.0 .002150696 13400000.0 .002163971 13500000.0 .0021772456400 3102  195
 13600000.0 .002190520 13700000.0 .002203795 13800000.0 .0022170706400 3102  196
 13900000.0 .002230354 14000000.0 .002243718 14100000.0 .0022571586400 3102  197
 14200000.0 .002270598 14300000.0 .002284038 14400000.0 .0022974786400 3102  198
 14500000.0 .002310919 14600000.0 .002324359 14700000.0 .0023377996400 3102  199
 14800000.0 .002351239 14900000.0 .002364679 15000000.0 .0023789686400 3102  200
 15100000.0 .002394105 15200000.0 .002409242 15300000.0 .0024243796400 3102  201
 15400000.0 .002439516 15500000.0 .002454653 15600000.0 .0024697906400 3102  202
 15700000.0 .002484927 15800000.0 .002500064 15900000.0 .0025152016400 3102  203
 16000000.0 .002530362 16100000.0 .002545547 16200000.0 .0025607336400 3102  204
 16300000.0 .002575919 16400000.0 .002591104 16500000.0 .0026062906400 3102  205
 16600000.0 .002621475 16700000.0 .002636661 16800000.0 .0026518476400 3102  206
 16900000.0 .002667032 17000000.0 .002682234 17100000.0 .0026974526400 3102  207
 17200000.0 .002712670 17300000.0 .002727887 17400000.0 .0027431056400 3102  208
 17500000.0 .002758323 17600000.0 .002773541 17700000.0 .0027887596400 3102  209
 17800000.0 .002803976 17900000.0 .002819194 18000000.0 .0028344276400 3102  210
 18100000.0 .002849674 18200000.0 .002864922 18300000.0 .0028801696400 3102  211
 18400000.0 .002895417 18500000.0 .002910664 18600000.0 .0029259126400 3102  212
 18700000.0 .002941159 18800000.0 .002956407 18900000.0 .0029716546400 3102  213
 19000000.0 .002986913 19100000.0 .003002184 19200000.0 .0030174546400 3102  214
 19300000.0 .003032724 19400000.0 .003047995 19500000.0 .0030632656400 3102  215
 19600000.0 .003078536 19700000.0 .003093806 19800000.0 .0031090766400 3102  216
 19900000.0 .003124347 20000000.0 0.0                             6400 3102  217
                                                                  6400 3  099999
                                                                  6400 0  0    0
                                                                     0 0  0    0
 6.91690E+4 1.67483E+2          0          0         34         106925 1451    1
 0.0        0.0                 0          0          0          66925 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20026925 1451    3
 3.00000E+2 0.0                 1          0         88          46925 1451    4
 69-Tm-169 SRI        EVAL-JAN96 N.ODANO (SHIP RES. INST.)        6925 1451    5
                      DIST-Feb2004                                6925 1451    6
----IRDF-2002         MATERIAL 6925                               6925 1451    7
-----INCIDENT NEUTRON DATA                                        6925 1451    8
------ENDF-6 FORMAT                                               6925 1451    9
****************************************************************  6925 1451   10
 69-TM-169 SRI        EVAL-JAN96 N.ODANO (SHIP RES. INST.)        6925 1451   11
                      DIST-JUL98                                  6925 1451   12
----JENDL/D-99        MATERIAL 6925                               6925 1451   13
****************************************************************  6925 1451   14
HISTORY                                                           6925 1451   15
96-01   EVALUATION FOR JENDL DOSIMETRY FILE VERSION 2 WAS MADE BY 6925 1451   16
        N.ODANO (SHIP RES. INST.).                                6925 1451   17
97-09   COMPILED TO JENDL DOSIMETRY FILE 99.                      6925 1451   18
                                                                  6925 1451   19
             ==== POINT-WISE DATA FILE ====                       6925 1451   20
                                                                  6925 1451   21
 <DOSIMETRY CROSS SECTION>                                        6925 1451   22
      TM-169 (N,2N) TM-168 (HALF-LIFE = 93.1 D)                   6925 1451   23
                                                                  6925 1451   24
MF=1  GENERAL INFORMATION                                         6925 1451   25
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          6925 1451   26
                                                                  6925 1451   27
MF=2  RESONANCE PARAMETERS                                        6925 1451   28
 MT=151  PARAMETERS                                               6925 1451   29
     ONLY SPIN AND SCATTERING RADIUS ARE GIVEN.                   6925 1451   30
                                                                  6925 1451   31
MF=3 NEUTRON CROSS SECTIONS                                       6925 1451   32
 MT=16 (N,2N) CROSS SECTION                                       6925 1451   33
       EXPERIMENTAL DATA/1-13/ IN NESTOR-2/14/ WERE TAKEN FOR     6925 1451   34
       THE EVALUATION USING GMA CODE/15/.                         6925 1451   35
                                                                  6925 1451   36
MF=33 COVARIANCES OF NEUTRON CROSS SECTIONS                       6925 1451   37
 MT=16  GENERATED USING THE GMA CODE.                             6925 1451   38
                                                                  6925 1451   39
REFERENCES                                                        6925 1451   40
 1) W.DILG+ : NUCL. PHYS. A, 118, 9 (1968).                       6925 1451   41
 2) D.S.MATHER+ : AWRE-O-72/,72 (1972).                           6925 1451   42
 3) D.R.NETHERWAY : NUCL. PHYS. A, 190, 635 (1972).               6925 1451   43
 4) R.VOS+ : BULLETIN OF THE AMERICAN PHYSICAL SOCIETY, 18,       6925 1451   44
    775(EB6) (1973).        6931 1451                             6925 1451   45
 5) S.M.QAIM : NUCL. PHYS. A, 224, 319 (1974).                    6925 1451   46
 6) B.P.BAYHURST+ : PHYS. REV. C, 12, 451 (1975).                 6925 1451   47
 7) L.R.VEESER+ : PHYS. REV. C, 16, 1792 (1977).                  6925 1451   48
 8) J.FREHAUT+ : PROC. SYMP. ON NEUTRON CROSS SECTIONS FROM 10-50 6925 1451   49
    MEV, UPTON, USA, 12-14 MAY, 1980, P.399 (1980).               6925 1451   50
 9) J.LAUREC+ : CEA-R-5109 (1981).                                6925 1451   51
10) L.R.GREENWOOD : ASTM-STP-956, 743 (1987).                     6925 1451   52
11) LU HANLIN+ : INDC(CRP)-16 (1989).                             6925 1451   53
12) WANG XIUYUAN+ : A COLLECTION OF ACADEMIC EXCHANGE REPORT IN   6925 1451   54
    THE FIELDS OD RADIOCHEMISTRY, CHEMICAL INDUSTRY AND ISOTOPE,  6925 1451   55
    NUCLEAR INSTITUTE OF SICHUAN (1989).                          6925 1451   56
13) C.KONNO+ : JAERI 1329 (1993).                                 6925 1451   57
14) T.NAKAGAWA : THE JAERI NUCLEAR DATA CENTER, UNPUBLISHED.      6925 1451   58
15) W.P.POENITZ : PROC. CONF. NUCLEAR DATA EVALUATION METHODS     6925 1451   59
    AND PROCEDURES, BROOKHAVEN NATIONAL LAB. 1980, BNL-NCS-       6925 1451   60
    51363, P.249 (1981).                                          6925 1451   61
****************************************************************  6925 1451   62
  The Q values and threshold energies were updated prior to pro-  6925 1451   63
  cessing through the codes to comply with the values obtained    6925 1451   64
  using the NNDC calculation program which is based on the 1995   6925 1451   65
  Update to the Atomic mass Evaluation.                           6925 1451   66
****************************************************************  6925 1451   67
 ***************** Program LINEAR (VERSION 2002-1) ***************6925 1451   68
 For All Data Greater than 1.0000E-10 barns in Absolute Value     6925 1451   69
 Data Linearized to Within an Accuracy of .100000000 per-cent     6925 1451   70
 ***************** Program SIGMA1 (VERSION 2002-1) ***************6925 1451   71
 Data Doppler Broadened to 300.000000 Kelvin                      6925 1451   72
 for All Data Greater than 1.0000E-10 barns in Absolute Value     6925 1451   73
 Data Linearized to Within an Accuracy pf .100000000 per-cent     6925 1451   74
 ***************** Program FIXUP (Version 2002-1) ****************6925 1451   75
 Corrected ZA/AWR in All Sections-----------------------------Yes 6925 1451   76
 Corrected Thresholds-----------------------------------------Yes 6925 1451   77
 Extended Cross Sections to 20 MeV----------------------------No  6925 1451   78
 Allow Cross Section Deletion---------------------------------No  6925 1451   79
 Allow Cross Section Reconstruction---------------------------No  6925 1451   80
 Make All Cross Sections Non-Negative-------------------------Yes 6925 1451   81
 Delete Energies Not in Ascending Order-----------------------Yes 6925 1451   82
 Deleted Duplicate Points-------------------------------------Yes 6925 1451   83
 Check for Ascending MAT/MF/MT Order--------------------------Yes 6925 1451   84
 Check for Legal MF/MT Numbers--------------------------------Yes 6925 1451   85
 Allow Creation of Missing Sections---------------------------No  6925 1451   86
 Allow Insertion of Energy Points-----------------------------No  6925 1451   87
 Create Uniform Energy Grid-----------------------------------No  6925 1451   88
 Delete Section if Cross Section =0 at All Energies-----------Yes 6925 1451   89
 ***************** Program GROUPIE (VERSION 2002-1) **************6925 1451   90
 Unshielded Group Averages Using  640 Groups                      6925 1451   91
 Weighting Spectrum: Flat (Constant) Spectrum                     6925 1451   92
                                1        451         96          16925 1451   93
                                2        151          4          16925 1451   94
                                3         16         44          16925 1451   95
                               33         16         23          16925 1451   96
                                                                  6925 1  099999
                                                                  6925 0  0    0
 6.91690E+4 1.67483E+2          0          0          1          06925 2151    1
 6.91690E+4 1.00000E+0          0          0          1          06925 2151    2
 0.0        0.0                 0          0          0          06925 2151    3
 5.00000E-1 7.70000E-1          0          0          0          06925 2151    4
                                                                  6925 2  099999
                                                                  6925 0  0    0
 6.91690E+4 1.67483E+2          0          0          0          06925 3 16    1
-8.03340E+6-8.03340E+6          0          0          1        1216925 3 16    2
        121          1                                            6925 3 16    3
 8000000.00 .000162775 8100000.00 .006767183 8200000.00 .0167043106925 3 16    4
 8300000.00 .026641437 8400000.00 .070615833 8500000.00 .1486275006925 3 16    5
 8600000.00 .226639167 8700000.00 .304650833 8800000.00 .3826625006925 3 16    6
 8900000.00 .460674167 9000000.00 .535816000 9100000.00 .6080880006925 3 16    7
 9200000.00 .680360000 9300000.00 .752632000 9400000.00 .8249040006925 3 16    8
 9500000.00 .897176000 9600000.00 .969448000 9700000.00 1.041720006925 3 16    9
 9800000.00 1.11399200 9900000.00 1.18626400 10000000.0 1.235935006925 3 16   10
 10100000.0 1.26300500 10200000.0 1.29007500 10300000.0 1.317145006925 3 16   11
 10400000.0 1.34421500 10500000.0 1.37128500 10600000.0 1.398355006925 3 16   12
 10700000.0 1.42542500 10800000.0 1.45249500 10900000.0 1.479565006925 3 16   13
 11000000.0 1.50758000 11100000.0 1.53654000 11200000.0 1.565500006925 3 16   14
 11300000.0 1.59446000 11400000.0 1.62342000 11500000.0 1.652380006925 3 16   15
 11600000.0 1.68134000 11700000.0 1.71030000 11800000.0 1.739260006925 3 16   16
 11900000.0 1.76822000 12000000.0 1.79406500 12100000.0 1.816795006925 3 16   17
 12200000.0 1.83952500 12300000.0 1.86225500 12400000.0 1.884985006925 3 16   18
 12500000.0 1.90771500 12600000.0 1.93044500 12700000.0 1.953175006925 3 16   19
 12800000.0 1.97590500 12900000.0 1.99863500 13000000.0 2.009486676925 3 16   20
 13100000.0 2.00846000 13200000.0 2.00743333 13300000.0 2.006406676925 3 16   21
 13400000.0 2.00538000 13500000.0 2.00435333 13600000.0 2.003326676925 3 16   22
 13700000.0 2.00230000 13800000.0 2.00127333 13900000.0 2.000246676925 3 16   23
 14000000.0 1.99922000 14100000.0 1.99819333 14200000.0 1.997166676925 3 16   24
 14300000.0 1.99614000 14400000.0 1.99511333 14500000.0 1.994686676925 3 16   25
 14600000.0 1.99486000 14700000.0 1.99503333 14800000.0 1.995206676925 3 16   26
 14900000.0 1.99538000 15000000.0 1.99555333 15100000.0 1.995726676925 3 16   27
 15200000.0 1.99590000 15300000.0 1.99607333 15400000.0 1.996246676925 3 16   28
 15500000.0 1.99642000 15600000.0 1.99659333 15700000.0 1.996766676925 3 16   29
 15800000.0 1.99694000 15900000.0 1.99711333 16000000.0 1.994380006925 3 16   30
 16100000.0 1.98874000 16200000.0 1.98310000 16300000.0 1.977460006925 3 16   31
 16400000.0 1.97182000 16500000.0 1.96618000 16600000.0 1.960540006925 3 16   32
 16700000.0 1.95490000 16800000.0 1.94926000 16900000.0 1.943620006925 3 16   33
 17000000.0 1.91730500 17100000.0 1.87031500 17200000.0 1.823325006925 3 16   34
 17300000.0 1.77633500 17400000.0 1.72934500 17500000.0 1.682355006925 3 16   35
 17600000.0 1.63536500 17700000.0 1.58837500 17800000.0 1.541385006925 3 16   36
 17900000.0 1.49439500 18000000.0 1.45198500 18100000.0 1.414155006925 3 16   37
 18200000.0 1.37632500 18300000.0 1.33849500 18400000.0 1.300665006925 3 16   38
 18500000.0 1.26283500 18600000.0 1.22500500 18700000.0 1.187175006925 3 16   39
 18800000.0 1.14934500 18900000.0 1.11151500 19000000.0 1.081435006925 3 16   40
 19100000.0 1.05910500 19200000.0 1.03677500 19300000.0 1.014445006925 3 16   41
 19400000.0 .992115000 19500000.0 .969785000 19600000.0 .9474550006925 3 16   42
 19700000.0 .925125000 19800000.0 .902795000 19900000.0 .8804650006925 3 16   43
 20000000.0 0.0                                                   6925 3 16   44
                                                                  6925 3  099999
                                                                  6925 0  0    0
 6.91690E+4 1.67483E+2          0          0          0          1692533 16    1
 0.000000+0 0.000000+0          0         16          0          1692533 16    2
 0.000000+0 0.000000+0          1          5        120         15692533 16    3
 1.000000-5 8.000000+6 8.240180+6 8.700000+6 9.500000+6 1.050000+7692533 16    4
 1.150000+7 1.250000+7 1.375000+7 1.525000+7 1.650000+7 1.750000+7692533 16    5
 1.850000+7 1.950000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0692533 16    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0692533 16    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.544490-3692533 16    8
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0692533 16    9
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0692533 16   10
 1.544490-3 2.161260-4 8.021960-5 8.018380-5 8.965270-5 1.308120-4692533 16   11
 8.611730-5 7.978640-5 1.636990-4 1.667380-4 9.654600-5 2.752760-4692533 16   12
 1.762320-3 1.773580-4 1.789170-4 1.261310-4 1.126210-4 7.632130-5692533 16   13
 6.414960-5 1.179690-4 1.202010-4 7.090170-5 1.789260-4 2.253400-3692533 16   14
 3.400620-4 1.941300-4 1.014070-4 7.258540-5 4.974090-5 6.811760-5692533 16   15
 7.143290-5 4.130170-5 6.744160-5 2.055720-3 1.967720-4 1.028640-4692533 16   16
 7.314980-5 5.047840-5 6.867560-5 7.201810-5 4.176900-5 6.741150-5692533 16   17
 7.739520-4 1.059610-4 7.502940-5 7.712840-5 9.702920-5 1.017520-4692533 16   18
 5.552930-5 7.629130-5 2.742330-4 8.094930-5 8.206160-5 1.132040-4692533 16   19
 1.180210-4 6.526070-5 1.110700-4 1.449620-4 5.756050-5 7.774620-5692533 16   20
 8.052350-5 5.484240-5 7.438890-5 4.765490-4 1.022420-4 1.031120-4692533 16   21
 1.117260-4 7.429010-5 3.972050-4 1.424560-4 1.295420-4 1.435500-4692533 16   22
 4.368100-4 1.091050-4 1.436310-4 2.619390-3 1.132960-4 1.091640-3692533 16   23
                                                                  692533  099999
                                                                  6925 0  0    0
                                                                     0 0  0    0
 7.31810E+4 1.79393E+2          0          0         34         107328 1451    1
 0.0        0.0                 0          0          0          67328 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20027328 1451    3
 3.00000E+2 0.0                 1          0        117          47328 1451    4
 73-Ta-181 NAIG       EVAL-MAR87 N.YAMAMURO                       7328 1451    5
                      DIST-Feb2004                                7328 1451    6
----IRDF-2002         MATERIAL 7328         REVISION 2            7328 1451    7
-----INCIDENT NEUTRON DATA                                        7328 1451    8
------ENDF-6 FORMAT                                               7328 1451    9
****************************************************************  7328 1451   10
 73-TA-181 NAIG       EVAL-MAR87 N.YAMAMURO                       7328 1451   11
                      DIST-SEP89 REV2-FEB94                       7328 1451   12
----JENDL-3.2         MATERIAL 7328         REVISION 2            7328 1451   13
 <DOSIMETRY CROSS SECTION>                                        7328 1451   14
      TA-181 CAPTURE TA-181(HALF-LIFE = 114.43D)                  7328 1451   15
****************************************************************  7328 1451   16
HISTORY                                                           7328 1451   17
76-03 THE EVALUATION FOR JENDL-1 /1/ WAS MADE BY H.YAMAKOSHI      7328 1451   18
      (SHIP RESEARCH INSTITUTE) AND JENDL-1 COMPILATION GROUP.    7328 1451   19
83-03 JENDL-1 DATA WERE ADOPTED FOR JENDL-2 AND EXTENDED TO 20    7328 1451   20
      MEV. MF=5 WAS REVISED, AND UNRESOLVED RESONANCE PARAMETERS  7328 1451   21
      WERE ADDED BY Y.KIKUCHI (JAERI) /2/.                        7328 1451   22
83-11 COMMENT DATA WERE ADDED.                                    7328 1451   23
87-03 THE EVALUATION FOR JENDL-3 WAS MADE BY N.YAMAMURO (NAIG).   7328 1451   24
      RESONANCE PARAMETERS WERE ADDED BY NEW EXPERIMENTAL DATA.   7328 1451   25
      NEUTRON CROSS SECTIONS, EXCEPT TOTAL AND ELASTIC SCATTERING 7328 1451   26
      CROSS SECTIONS, AND ENERGY DISTRIBUTIONS OF SECONDARY       7328 1451   27
      NEUTRONS AND PHOTONS WERE CALCULATED WITH GNASH /3/ AND     7328 1451   28
      CASTHY /4/ CODES.                                           7328 1451   29
94-02 JENDL-3.2.                                                  7328 1451   30
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          7328 1451   31
                                                                  7328 1451   32
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  7328 1451   33
      (12,102)                                                    7328 1451   34
             DATA WERE DETERMINED FROM ENERGY BALANCE.            7328 1451   35
     ***********************************************************  7328 1451   36
                                                                  7328 1451   37
                                                                  7328 1451   38
MF=1   GENERAL INFORMATION                                        7328 1451   39
  MT=451     DESCRIPTIVE DATA AND DICTIONARY                      7328 1451   40
                                                                  7328 1451   41
MF=2   RESONANCE PARAMETERS                                       7328 1451   42
  MT=151     RESOLVED AND UNRESOLVED RESONANCE PARAMETERS         7328 1451   43
  RESOLVED PARAMETERS FOR MLBW FORMULA                            7328 1451   44
                                                                  7328 1451   45
      THE ENERGY REGION FROM 1.0E-5EV TO 1.0 KEV. PARAMETERS WERE 7328 1451   46
      TAKEN FROM REFS./5,6,7/ FOR POSITIVE RESONANCES, AND FROM   7328 1451   47
      ENDF/B-IV FOR A NEGATIVE RESONANCE. THE RADIATIVE WIDTH OF  7328 1451   48
      0.059EV WAS ASSUMED FOR THE RESONANCE WHOSE RADIATIVE WIDTH 7328 1451   49
      WAS UNKNOWN.                                                7328 1451   50
                                                                  7328 1451   51
  UNRESOLVED PARAMETERS                                           7328 1451   52
                                                                  7328 1451   53
      IN THE ENERGY RANGE FROM 1 TO 100KEV, PARAMETERS WERE       7328 1451   54
      DETERMINED TO REPRODUCE THE MEASURED CAPTURE CROSS SECTIONS 7328 1451   55
      /6,8/. THE PARAMETERS ARE AS FOLLOWS,                       7328 1451   56
                                                                  7328 1451   57
         R= 7.8 FM , DOBS= 4.2 EV , RADIATIVE WIDTH= 0.065 EV,    7328 1451   58
         SO= 1.7E-04  S1= 2.0E-05  S2= 2.3E-04  NL= 3             7328 1451   59
                                                                  7328 1451   60
      CALCULATED 2200-M/SEC CROSS SECTIONS AND RESONANCE INTEGRALS7328 1451   61
                        2200-M/SEC      RES. INTEG                7328 1451   62
          ELASTIC         5.65 B            -                     7328 1451   63
          CAPTURE        20.67 B         660.43 B                 7328 1451   64
          TOTAL          26.32 B            -                     7328 1451   65
                                                                  7328 1451   66
MF=3   NEUTRON CROSS SECTIONS                                     7328 1451   67
  MT=1   TOTAL                                                    7328 1451   68
    EVALUATED FROM EXPERIMENTAL DATA.                             7328 1451   69
  MT=2   ELASTIC SCATTERING                                       7328 1451   70
    (TOTAL CROSS SECTION) - (REACTION CROSS SECTION)              7328 1451   71
  MT=102  RADIATIVE CAPTURE CROSS SECTION                         7328 1451   72
    CALCULATED WITH CASTHY/4/.                                    7328 1451   73
                                                                  7328 1451   74
REFERENCES                                                        7328 1451   75
 1) IGARASI S. ET AL.: JAERI 1261 (1979)                          7328 1451   76
 2) (ED.) NAKAGAWA T.: JAERI-M 84-103 (1984)                      7328 1451   77
 3) YOUNG,P.G. AND ARTHUR,E.D.: "GNASH, A PREEQUILIBRIUM          7328 1451   78
    STATISTICAL NUCLEAR-MODEL CODE FOR CALCULATION OF CROSS       7328 1451   79
    SECTIONS AND EMISSION SPECTRA", LA-6974 (1977).               7328 1451   80
 4) IGARASHI,S. AND FUKAHORI,T.: JAERI 1321 (1991).               7328 1451   81
 5) MUGHABGHAB,S.F, AND GARDER,D.I.: BNL325, 3RD ED. (1973).      7328 1451   82
 6) MACKLIN,R,L,: NUCL,SCI,ENG., 86,362 (1984).                   7328 1451   83
 7) TSUBONE,I., NAKAJIMA,Y. AND KANDA,Y.: PRIVATE COMMUNICATION   7328 1451   84
 8) YAMAMURO,N., SAITO,K., EMOTO,T., WADA,T., FUJITA,Y. AND       7328 1451   85
    KOBAYASHI,K.: J.NUCL.SCI.TECHNOL., 17, 582 (1980).            7328 1451   86
 9) WILMORE,D. AND HODGSON,P.E.: NUCL, PHYS., 55, 673 (1964).     7328 1451   87
10) FIRESTONE,R.B.* NUCL, DATA SHEETS 43, 289 (1984).             7328 1451   88
 ***************************************************************  7328 1451   89
  The Q values and threshold energies were updated prior to pro-  7328 1451   90
  cessing through the codes to comply with the values obtained    7328 1451   91
  using the NNDC calculation program which is based on the 1995   7328 1451   92
  Update to the Atomic mass Evaluation.                           7328 1451   93
 ***************** Program LINEAR (VERSION 2002-1) ***************7328 1451   94
 For All Data Greater than 1.0000E-10 barns in Absolute Value     7328 1451   95
 Data Linearized to Within an Accuracy of .100000000 per-cent     7328 1451   96
 ***************** Program RECENT (VERSION 2002-1) ***************7328 1451   97
 for All Data Greater than 1.0000E-10 barns in Absolute Value     7328 1451   98
 Data Linearized to within an Accuracy of .100000000 per-cent     7328 1451   99
 ***************** Program SIGMA1 (VERSION 2002-1) ***************7328 1451  100
 Data Doppler Broadened to 300.000000 Kelvin                      7328 1451  101
 for All Data Greater than 1.0000E-10 barns in Absolute Value     7328 1451  102
 Data Linearized to Within an Accuracy pf .100000000 per-cent     7328 1451  103
 ***************** Program FIXUP (Version 2002-1) ****************7328 1451  104
 Corrected ZA/AWR in All Sections-----------------------------Yes 7328 1451  105
 Corrected Thresholds-----------------------------------------Yes 7328 1451  106
 Extended Cross Sections to 20 MeV----------------------------No  7328 1451  107
 Allow Cross Section Deletion---------------------------------No  7328 1451  108
 Allow Cross Section Reconstruction---------------------------No  7328 1451  109
 Make All Cross Sections Non-Negative-------------------------Yes 7328 1451  110
 Delete Energies Not in Ascending Order-----------------------Yes 7328 1451  111
 Deleted Duplicate Points-------------------------------------Yes 7328 1451  112
 Check for Ascending MAT/MF/MT Order--------------------------Yes 7328 1451  113
 Check for Legal MF/MT Numbers--------------------------------Yes 7328 1451  114
 Allow Creation of Missing Sections---------------------------No  7328 1451  115
 Allow Insertion of Energy Points-----------------------------No  7328 1451  116
 Create Uniform Energy Grid-----------------------------------No  7328 1451  117
 Delete Section if Cross Section =0 at All Energies-----------Yes 7328 1451  118
 ***************** Program GROUPIE (VERSION 2002-1) **************7328 1451  119
 Unshielded Group Averages Using  640 Groups                      7328 1451  120
 Weighting Spectrum: Flat (Constant) Spectrum                     7328 1451  121
                                1        451        125          17328 1451  122
                                2        151          4          17328 1451  123
                                3        102        217          17328 1451  124
                               33        102         16          17328 1451  125
                                                                  7328 1  099999
                                                                  7328 0  0    0
 7.31810E+4 1.79394E+2          0          0          1          07328 2151    1
 7.31810E+4 1.00000E+0          0          0          1          07328 2151    2
 1.00000E-5 2.40000E+3          0          0          0          07328 2151    3
 3.50000E+0 7.80000E-1          0          0          0          07328 2151    4
                                                                  7328 2  099999
                                                                  7328 0  0    0
 7.31810E+4 1.79393E+2          0          0          0          07328 3102    1
 6.06296E+6 6.06296E+6          0          0          1        6417328 3102    2
        641          1                                            7328 3102    3
 .000100000 323.217903 .000105000 315.681488 .000110000 308.5218207328 3102    4
 .000115000 301.924447 .000120000 294.211880 .000127500 285.6549077328 3102    5
 .000135000 277.837071 .000142500 270.652682 .000150000 262.8772027328 3102    6
 .000160000 254.777193 .000170000 247.407203 .000180000 240.6421387328 3102    7
 .000190000 234.347828 .000200000 228.601006 .000210000 223.1942217328 3102    8
 .000220000 218.172206 .000230000 213.506120 .000240000 208.0290837328 3102    9
 .000255000 202.010625 .000270000 197.366526 .000280000 192.1967877328 3102   10
 .000300000 185.892130 .000320000 180.183474 .000340000 174.9552667328 3102   11
 .000360000 170.139778 .000380000 165.743885 .000400000 161.1609207328 3102   12
 .000425000 156.471122 .000450000 152.185981 .000475000 148.2575327328 3102   13
 .000500000 144.563214 .000525000 141.186770 .000550000 137.9971507328 3102   14
 .000575000 135.030648 .000600000 131.990183 .000630000 128.8623417328 3102   15
 .000660000 126.000351 .000690000 123.254902 .000720000 120.3335897328 3102   16
 .000760000 117.201272 .000800000 114.293003 .000840000 111.6277757328 3102   17
 .000880000 109.094632 .000920000 106.772417 .000960000 104.5484537328 3102   18
 .001000000 102.243220 .001050000 99.8368250 .001100000 97.58099947328 3102   19
 .001150000 95.5024452 .001200000 93.0505503 .001275000 90.35585597328 3102   20
 .001350000 87.8922920 .001425000 85.5932451 .001500000 83.15089677328 3102   21
 .001600000 80.5973361 .001700000 78.2663165 .001800000 76.11048847328 3102   22
 .001900000 74.1411257 .002000000 72.3150953 .002100000 70.60153967328 3102   23
 .002200000 69.0322893 .002300000 67.5316982 .002400000 65.81944087328 3102   24
 .002550000 63.9166791 .002700000 62.4282767 .002800000 60.81092297328 3102   25
 .003000000 58.8199465 .003200000 57.0083580 .003400000 55.35215557328 3102   26
 .003600000 53.8422601 .003800000 52.4486161 .004000000 50.99654757328 3102   27
 .004250000 49.5228933 .004500000 48.1779215 .004750000 46.92074987328 3102   28
 .005000000 45.7666443 .005250000 44.6962028 .005500000 43.68386187328 3102   29
 .005750000 42.7554179 .006000000 41.7800919 .006300000 40.80494017328 3102   30
 .006600000 39.8823962 .006900000 39.0272497 .007200000 38.09835167328 3102   31
 .007600000 37.1060107 .008000000 36.1997943 .008400000 35.35036067328 3102   32
 .008800000 34.5611280 .009200000 33.8269194 .009600000 33.12773187328 3102   33
 .010000000 32.4026932 .010500000 31.6356982 .011000000 30.93437197328 3102   34
 .011500000 30.2654520 .012000000 29.4991382 .012750000 28.65129477328 3102   35
 .013500000 27.8663681 .014250000 27.1466861 .015000000 26.37937077328 3102   36
 .016000001 25.5739361 .017000001 24.8352752 .017999999 24.16073867328 3102   37
 .018999999 23.5405789 .020000000 22.9587048 .021000000 22.42625467328 3102   38
 .022000000 21.9247118 .023000000 21.4575784 .024000000 20.90912817328 3102   39
 .025500000 20.3185917 .027000001 19.8510914 .028000001 19.34385857328 3102   40
 .029999999 18.7191818 .032000002 18.1495657 .034000002 17.62914457328 3102   41
 .035999998 17.1541449 .037999999 16.7162398 .039999999 16.25956907328 3102   42
 .042500000 15.7963649 .045000002 15.3734911 .047499999 14.98001797328 3102   43
 .050000001 14.6188762 .052499998 14.2855256 .055000000 13.97040047328 3102   44
 .057500001 13.6816926 .059999999 13.3779349 .063000001 13.07361657328 3102   45
 .066000000 12.7868579 .068999998 12.5198571 .071999997 12.23061137328 3102   46
 .075999998 11.9210685 .079999998 11.6386548 .083999999 11.37346237328 3102   47
 .088000000 11.1271550 .092000000 10.8993591 .096000001 10.68200867328 3102   48
 .100000001 10.4585554 .104999997 10.2230982 .109999999 10.01148777328 3102   49
 .115000002 9.80350319 .119999997 9.56591573 .127499998 9.302968457328 3102   50
 .135000005 9.06519879 .142499998 8.85047362 .150000006 8.611181927328 3102   51
 .159999996 8.36500915 .170000002 8.14190890 .180000007 7.936169207328 3102   52
 .189999998 7.74863484 .200000003 7.57624267 .209999993 7.414342437328 3102   53
 .219999999 7.26714837 .230000004 7.12657600 .239999995 6.967096497328 3102   54
 .254999995 6.79444309 .270000011 6.65867698 .280000001 6.506931487328 3102   55
 .300000012 6.32981886 .319999993 6.16390128 .340000004 6.016448777328 3102   56
 .360000014 5.88316035 .379999995 5.76064335 .400000006 5.638514697328 3102   57
 .425000012 5.51094212 .449999988 5.39930491 .474999994 5.293406217328 3102   58
 .500000000 5.20181742 .524999976 5.11979303 .550000012 5.040015447328 3102   59
 .574999988 4.97152095 .600000024 4.89835339 .629999995 4.828992277328 3102   60
 .660000026 4.76586672 .689999998 4.70668359 .720000029 4.647732187328 3102   61
 .759999990 4.58926122 .800000012 4.53760167 .839999974 4.493618077328 3102   62
 .879999995 4.45908763 .920000017 4.42635679 .959999979 4.400948137328 3102   63
 1.00000000 4.38047823 1.04999995 4.36080083 1.10000002 4.352205107328 3102   64
 1.14999998 4.34647759 1.20000005 4.35372121 1.27499998 4.373801537328 3102   65
 1.35000002 4.40641307 1.42499995 4.45505394 1.50000000 4.526569107328 3102   66
 1.60000002 4.63429955 1.70000005 4.76924637 1.79999995 4.931018797328 3102   67
 1.89999998 5.12693861 2.00000000 5.36046731 2.09999990 5.637265167328 3102   68
 2.20000005 5.96494115 2.29999995 6.35008715 2.40000010 6.941300167328 3102   69
 2.54999995 7.84111183 2.70000005 8.80088160 2.79999995 10.36313967328 3102   70
 3.00000000 13.4083627 3.20000005 18.5268378 3.40000010 28.11516527328 3102   71
 3.59999990 49.5999519 3.79999995 117.762222 4.00000000 1864.175127328 3102   72
 4.25000000 4217.02960 4.50000000 143.147392 4.75000000 42.00771997328 3102   73
 5.00000000 20.2062067 5.25000000 12.0053159 5.50000000 8.073107877328 3102   74
 5.75000000 5.91096196 6.00000000 4.51817820 6.30000019 3.602336537328 3102   75
 6.59999990 3.05305713 6.90000010 2.73098589 7.19999981 2.560686137328 3102   76
 7.59999990 2.58363598 8.00000000 2.87132560 8.39999962 3.577203567328 3102   77
 8.80000019 5.17996978 9.19999981 9.48804025 9.60000038 28.83530107328 3102   78
 10.0000000 1152.78967 10.5000000 100.954787 11.0000000 10.39886767328 3102   79
 11.5000000 4.47835387 12.0000000 2.82413562 12.7500000 4.149997407328 3102   80
 13.5000000 211.005186 14.2500000 5.61719025 15.0000000 1.326127797328 3102   81
 16.0000000 .858612427 17.0000000 .790138076 18.0000000 .9493522797328 3102   82
 19.0000000 3.17141199 20.0000000 92.5348042 21.0000000 2.159240617328 3102   83
 22.0000000 21.5641816 23.0000000 346.522306 24.0000000 73.20486597328 3102   84
 25.5000000 1.59578597 27.0000000 1.09924377 28.0000000 5.224979117328 3102   85
 30.0000000 7.15285916 32.0000000 5.72530707 34.0000000 654.9549897328 3102   86
 36.0000000 98.6698075 38.0000000 733.614832 40.0000000 9.137630807328 3102   87
 42.5000000 1.56797274 45.0000000 .759940196 47.5000000 17.44797517328 3102   88
 50.0000000 .433509742 52.5000000 .267497265 55.0000000 1.913621877328 3102   89
 57.5000000 4.35998799 60.0000000 13.9354033 63.0000000 40.84589957328 3102   90
 66.0000000 .269789538 69.0000000 .258716157 72.0000000 .9648387337328 3102   91
 76.0000000 106.781470 80.0000000 69.0689934 84.0000000 26.40454717328 3102   92
 88.0000000 30.7258512 92.0000000 1.42803656 96.0000000 178.7203687328 3102   93
 100.000000 10.2114323 105.000000 67.9552512 110.000000 34.08127427328 3102   94
 115.000000 68.2257086 120.000000 48.9855917 127.500000 1.098669687328 3102   95
 135.000000 55.2013522 142.500000 40.4836758 150.000000 1.967551847328 3102   96
 160.000000 9.59669617 170.000000 77.6984939 180.000000 2.592638467328 3102   97
 190.000000 51.4677260 200.000000 21.1497552 210.000000 50.82953907328 3102   98
 220.000000 22.2651844 230.000000 41.9442047 240.000000 7.870144437328 3102   99
 255.000000 23.8695611 270.000000 49.0972569 280.000000 18.32445337328 3102  100
 300.000000 29.9053474 320.000000 11.7928411 340.000000 24.43636697328 3102  101
 360.000000 10.6273928 380.000000 12.8887613 400.000000 19.31791287328 3102  102
 425.000000 24.5828611 450.000000 20.2086210 475.000000 11.18047187328 3102  103
 500.000000 15.0434555 525.000000 19.2149034 550.000000 10.31598217328 3102  104
 575.000000 14.9287376 600.000000 14.8980170 630.000000 11.38951727328 3102  105
 660.000000 5.31134378 690.000000 12.9585358 720.000000 13.14439757328 3102  106
 760.000000 7.28693017 800.000000 10.9072764 840.000000 8.212886127328 3102  107
 880.000000 11.5257214 920.000000 15.4499160 960.000000 10.74899377328 3102  108
 1000.00000 11.1231511 1050.00000 11.9925759 1100.00000 5.984656967328 3102  109
 1150.00000 10.5662126 1200.00000 5.66694035 1275.00000 7.972817937328 3102  110
 1350.00000 6.84970367 1425.00000 3.94062482 1500.00000 6.670263967328 3102  111
 1600.00000 7.73585158 1700.00000 5.55435412 1800.00000 4.376924827328 3102  112
 1900.00000 3.29392410 2000.00000 5.10309867 2100.00000 4.741574317328 3102  113
 2200.00000 3.99371469 2300.00000 4.76123365 2400.00000 4.110312007328 3102  114
 2550.00000 3.96018193 2700.00000 3.84546453 2800.00000 3.719538297328 3102  115
 3000.00000 3.56480851 3200.00000 3.42020191 3400.00000 3.290171237328 3102  116
 3600.00000 3.17244418 3800.00000 3.06523249 4000.00000 2.953255467328 3102  117
 4250.00000 2.83881742 4500.00000 2.73520855 4750.00000 2.640909807328 3102  118
 5000.00000 2.55276688 5250.00000 2.46994471 5500.00000 2.393665777328 3102  119
 5750.00000 2.32316452 6000.00000 2.22687328 6300.00000 2.116641587328 3102  120
 6600.00000 2.02192803 6900.00000 1.93913945 7200.00000 1.854396487328 3102  121
 7600.00000 1.76940004 8000.00000 1.69808711 8400.00000 1.635918127328 3102  122
 8800.00000 1.57933856 9200.00000 1.52759327 9600.00000 1.480066257328 3102  123
 10000.0000 1.43189194 10500.0000 1.38314808 11000.0000 1.338635517328 3102  124
 11500.0000 1.29780441 12000.0000 1.25135221 12750.0000 1.201025427328 3102  125
 13500.0000 1.15592384 14250.0000 1.11527758 15000.0000 1.073767227328 3102  126
 16000.0000 1.03080369 17000.0000 .992645464 18000.0000 .9584954647328 3102  127
 19000.0000 .927733250 20000.0000 .899932206 21000.0000 .8747316507328 3102  128
 22000.0000 .851713344 23000.0000 .830591817 24000.0000 .8064437147328 3102  129
 25500.0000 .778863836 27000.0000 .757494909 28000.0000 .7343349567328 3102  130
 30000.0000 .705214122 32000.0000 .678512513 34000.0000 .6544883327328 3102  131
 36000.0000 .632699881 38000.0000 .612803620 40000.0000 .5928294617328 3102  132
 42500.0000 .573149749 45000.0000 .555330999 47500.0000 .5391000637328 3102  133
 50000.0000 .524251643 52500.0000 .510599540 55000.0000 .4981823367328 3102  134
 57500.0000 .486453358 60000.0000 .474850613 63000.0000 .4634504147328 3102  135
 66000.0000 .453042284 69000.0000 .443183487 72000.0000 .4326541517328 3102  136
 76000.0000 .421497949 80000.0000 .411415842 84000.0000 .4023068867328 3102  137
 88000.0000 .393882846 92000.0000 .386197372 96000.0000 .3786307037328 3102  138
 100000.000 .367996212 105000.000 .360337163 110000.000 .3529996087328 3102  139
 115000.000 .346467800 120000.000 .338405346 127500.000 .3290613237328 3102  140
 135000.000 .318257519 142500.000 .302199463 150000.000 .2846383977328 3102  141
 160000.000 .268994128 170000.000 .256860181 180000.000 .2459742077328 3102  142
 190000.000 .235937498 200000.000 .227900885 210000.000 .2217447427328 3102  143
 220000.000 .216085735 230000.000 .210512679 240000.000 .2042224767328 3102  144
 255000.000 .197171727 270000.000 .191933730 280000.000 .1860831487328 3102  145
 300000.000 .177729548 320000.000 .168300375 340000.000 .1617396867328 3102  146
 360000.000 .157636629 380000.000 .153909773 400000.000 .1500486067328 3102  147
 425000.000 .146047239 450000.000 .142317376 475000.000 .1370232257328 3102  148
 500000.000 .129261694 525000.000 .125188204 550000.000 .1222412397328 3102  149
 575000.000 .119961829 600000.000 .117173378 630000.000 .1136535267328 3102  150
 660000.000 .110689504 690000.000 .107984233 720000.000 .1058681117328 3102  151
 760000.000 .104744875 800000.000 .104727328 840000.000 .1048473627328 3102  152
 880000.000 .104967397 920000.000 .105087431 960000.000 .1054821247328 3102  153
 1000000.00 .105899844 1100000.00 .101453980 1200000.00 .0970308707328 3102  154
 1300000.00 .093152354 1400000.00 .089688166 1500000.00 .0843624307328 3102  155
 1600000.00 .077620419 1700000.00 .071773871 1800000.00 .0666320467328 3102  156
 1900000.00 .062144851 2000000.00 .057693351 2100000.00 .0533494997328 3102  157
 2200000.00 .049514519 2300000.00 .046096349 2400000.00 .0430441537328 3102  158
 2500000.00 .039965962 2600000.00 .036888310 2700000.00 .0341533867328 3102  159
 2800000.00 .031702769 2900000.00 .029504405 3000000.00 .0270695227328 3102  160
 3100000.00 .024470771 3200000.00 .022186918 3300000.00 .0201851367328 3102  161
 3400000.00 .018408410 3500000.00 .016835710 3600000.00 .0154340117328 3102  162
 3700000.00 .014182623 3800000.00 .013064813 3900000.00 .0120582257328 3102  163
 4000000.00 .010776892 4100000.00 .009322457 4200000.00 .0080923817328 3102  164
 4300000.00 .007050960 4400000.00 .006159965 4500000.00 .0053985397328 3102  165
 4600000.00 .004745187 4700000.00 .004181665 4800000.00 .0036955027328 3102  166
 4900000.00 .003273923 5000000.00 .002816271 5100000.00 .0023504037328 3102  167
 5200000.00 .001969123 5300000.00 .001654538 5400000.00 .0013953337328 3102  168
 5500000.00 .001179810 5600000.00 .001000877 5700000.00 .0008514337328 3102  169
 5800000.00 .000726381 5900000.00 .000621363 6000000.00 .0005319557328 3102  170
 6100000.00 .000455780 6200000.00 .000391423 6300000.00 .0003370467328 3102  171
 6400000.00 .000290866 6500000.00 .000251612 6600000.00 .0002180957328 3102  172
 6700000.00 .000189461 6800000.00 .000164938 6900000.00 .0001438777328 3102  173
 7000000.00 .000126426 7100000.00 .000111945 7200000.00 9.93160E-57328 3102  174
 7300000.00 8.82150E-5 7400000.00 7.85053E-5 7500000.00 6.99745E-57328 3102  175
 7600000.00 6.24562E-5 7700000.00 5.58332E-5 7800000.00 4.99792E-57328 3102  176
 7900000.00 4.48090E-5 8000000.00 3.97481E-5 8100000.00 3.48806E-57328 3102  177
 8200000.00 3.06678E-5 8300000.00 2.70014E-5 8400000.00 2.38058E-57328 3102  178
 8500000.00 2.10222E-5 8600000.00 1.85956E-5 8700000.00 1.64654E-57328 3102  179
 8800000.00 1.46027E-5 8900000.00 1.29644E-5 9000000.00 1.14976E-57328 3102  180
 9100000.00 1.01769E-5 9200000.00 9.02338E-6 9300000.00 8.00673E-67328 3102  181
 9400000.00 7.11624E-6 9500000.00 6.33236E-6 9600000.00 5.64148E-67328 3102  182
 9700000.00 5.03184E-6 9800000.00 4.49326E-6 9900000.00 4.01735E-67328 3102  183
 10000000.0 3.61056E-6 10100000.0 3.26201E-6 10200000.0 2.94988E-67328 3102  184
 10300000.0 2.67066E-6 10400000.0 2.41987E-6 10500000.0 2.19506E-67328 3102  185
 10600000.0 1.99242E-6 10700000.0 1.81081E-6 10800000.0 1.64692E-67328 3102  186
 10900000.0 1.49895E-6 11000000.0 1.36998E-6 11100000.0 1.25708E-67328 3102  187
 11200000.0 1.15454E-6 11300000.0 1.06090E-6 11400000.0 9.75771E-77328 3102  188
 11500000.0 8.97808E-7 11600000.0 8.27136E-7 11700000.0 7.62379E-77328 3102  189
 11800000.0 7.02910E-7 11900000.0 6.48963E-7 12000000.0 6.04076E-77328 3102  190
 12100000.0 5.67200E-7 12200000.0 5.33022E-7 12300000.0 5.01074E-77328 3102  191
 12400000.0 4.71252E-7 12500000.0 4.43550E-7 12600000.0 4.17575E-77328 3102  192
 12700000.0 3.93213E-7 12800000.0 3.70602E-7 12900000.0 3.49426E-77328 3102  193
 13000000.0 3.30587E-7 13100000.0 3.13996E-7 13200000.0 2.98327E-77328 3102  194
 13300000.0 2.83547E-7 13400000.0 2.69619E-7 13500000.0 2.56409E-77328 3102  195
 13600000.0 2.43978E-7 13700000.0 2.32360E-7 13800000.0 2.21177E-77328 3102  196
 13900000.0 2.10728E-7 14000000.0 2.01228E-7 14100000.0 1.92650E-77328 3102  197
 14200000.0 1.84535E-7 14300000.0 1.76786E-7 14400000.0 1.69441E-77328 3102  198
 14500000.0 1.62470E-7 14600000.0 1.55761E-7 14700000.0 1.49437E-77328 3102  199
 14800000.0 1.43348E-7 14900000.0 1.37600E-7 15000000.0 1.31418E-77328 3102  200
 15100000.0 1.24932E-7 15200000.0 1.18796E-7 15300000.0 1.12997E-77328 3102  201
 15400000.0 1.07521E-7 15500000.0 1.02329E-7 15600000.0 9.74570E-87328 3102  202
 15700000.0 9.27964E-8 15800000.0 8.84000E-8 15900000.0 8.42572E-87328 3102  203
 16000000.0 8.06496E-8 16100000.0 7.75337E-8 16200000.0 7.45694E-87328 3102  204
 16300000.0 7.17256E-8 16400000.0 6.90170E-8 16500000.0 6.64320E-87328 3102  205
 16600000.0 6.39375E-8 16700000.0 6.15916E-8 16800000.0 5.92985E-87328 3102  206
 16900000.0 5.71001E-8 17000000.0 5.51630E-8 17100000.0 5.34235E-87328 3102  207
 17200000.0 5.17080E-8 17300000.0 5.01101E-8 17400000.0 4.85278E-87328 3102  208
 17500000.0 4.70063E-8 17600000.0 4.55502E-8 17700000.0 4.41732E-87328 3102  209
 17800000.0 4.28313E-8 17900000.0 4.14985E-8 18000000.0 4.03688E-87328 3102  210
 18100000.0 3.94019E-8 18200000.0 3.84351E-8 18300000.0 3.74837E-87328 3102  211
 18400000.0 3.65908E-8 18500000.0 3.57061E-8 18600000.0 3.48673E-87328 3102  212
 18700000.0 3.40452E-8 18800000.0 3.32291E-8 18900000.0 3.24595E-87328 3102  213
 19000000.0 3.16995E-8 19100000.0 3.09575E-8 19200000.0 3.02550E-87328 3102  214
 19300000.0 2.95540E-8 19400000.0 2.88663E-8 19500000.0 2.82189E-87328 3102  215
 19600000.0 2.75742E-8 19700000.0 2.69479E-8 19800000.0 2.63519E-87328 3102  216
 19900000.0 2.57564E-8 20000000.0 0.0                             7328 3102  217
                                                                  7328 3  099999
                                                                  7328 0  0    0
 7.31810E+4 1.79393E+2          0          0          0          1732833102    1
 0.000000+0 0.000000+0          0        102          0          1732833102    2
 0.000000+0 0.000000+0          0          1         74         37732833102    3
 1.000000-5 9.000000-4 1.000000+0 2.500000-3 5.000000+0 2.500000-3732833102    4
 1.000000+1 1.000000-2 2.000000+1 1.000000-2 3.000000+1 2.250000-2732833102    5
 5.000000+1 2.250000-2 7.000000+1 2.250000-2 1.000000+2 4.000000-2732833102    6
 2.000000+2 4.000000-2 3.000000+2 4.000000-2 5.000000+2 4.000000-2732833102    7
 7.000000+2 4.000000-2 1.000000+3 2.250000-2 2.000000+3 2.250000-2732833102    8
 3.000000+3 1.000000-2 5.000000+3 1.000000-2 7.000000+3 1.000000-2732833102    9
 1.000000+4 1.000000-2 2.000000+4 1.000000-2 3.000000+4 1.000000-2732833102   10
 5.000000+4 1.000000-2 7.000000+4 1.000000-2 1.000000+5 4.000000-2732833102   11
 2.000000+5 4.000000-2 3.000000+5 4.000000-2 5.000000+5 4.000000-2732833102   12
 7.000000+5 4.000000-2 1.000000+6 1.000000-2 2.000000+6 1.000000-2732833102   13
 3.000000+6 1.000000-2 4.000000+6 4.000000-2 6.000000+6 4.000000-2732833102   14
 7.000000+6 4.000000-2 1.000000+7 9.000000-2 1.500000+7 9.000000-2732833102   15
 2.000000+7 0.000000+0                                            732833102   16
                                                                  732833  099999
                                                                  7328 0  0    0
                                                                     0 0  0    0
 7.41860E+4 1.84357E+2          0          0         34         107443 1451    1
 0.0        0.0                 0          0          0          67443 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20027443 1451    3
 3.00000E+2 0.0                 1          0        199          47443 1451    4
 74-W -186 FEI,LANL+  EVAL-SEP01 K.I.Zolotarev,M.B.CHADWICK etal. 7443 1451    5
                      DIST-Feb2004                                7443 1451    6
----IRDF-2002         MATERIAL 7443                               7443 1451    7
-----INCIDENT NEUTRON DATA                                        7443 1451    8
------ENDF-6 FORMAT                                               7443 1451    9
***************************************************************** 7443 1451   10
 74-W -186 FEI        EVAL-Sep01 K.I.Zolotarev                    7443 1451   11
                      DIST-Jan04                                  7443 1451   12
----BROND-3           MATERIAL 7443         Revision 1, Jan. 2004 7443 1451   13
-----INCIDENT NEUTRON DATA                                        7443 1451   14
------ENDF-6 FORMAT                                               7443 1451   15
------Russian Reactor Dosimetry File RRDF-2002                    7443 1451   16
***************************************************************** 7443 1451   17
 **********   Start of (N,G) bibliographical component ********** 7443 1451   18
***************************************************************** 7443 1451   19
***************************************************************** 7443 1451   20
Authors of evaluation: K.I.Zolotarev and V.G.Pronyaev             7443 1451   21
***************************************************************** 7443 1451   22
                                                                  7443 1451   23
                    ----- MF=2 MT=151 -----                       7443 1451   24
                                                                  7443 1451   25
RESOLVED RESONANCE PARAMETERS                                     7443 1451   26
    Resolved MLBW resonance parameters up to  8.5 keV  were based 7443 1451   27
on data from ref.[1-2]. Spins of resonances, which were not iden- 7443 1451   28
tified, have been assigned by taking into account 2*J+1 law  and  7443 1451   29
approximate linear growth of the number of levels with given spin 7443 1451   30
and parity from energy. Average gamma-widths 0.05 eV (L=0 and L=1)7443 1451   31
were assigned to those resonances, widths for which were absent.  7443 1451   32
Fictitious resonances were added in the energy region 4 - 8.5 keV 7443 1451   33
to obtain  the average capture cross section values  observed  in 7443 1451   34
the experiments [3],[4],[5],[6].                                  7443 1451   35
                                                                  7443 1451   36
UNRESOLVED RESONANCE PARAMETERS                                   7443 1451   37
    Unresolved resonance parameters in  the region  8.5 - 100 keV 7443 1451   38
were evaluated  with using 'EVPAR' code (Hauser-Feshbach-Moldauer 7443 1451   39
statistical model)[7]. They were calculated from optimized fit to 7443 1451   40
the measured capture [4,5,6,8,9] and total [10,11] cross sections 7443 1451   41
data.  Average resolved resonance  parameters  have been  used as 7443 1451   42
zero approximation.  Contribution of  F-wave in the energy region 7443 1451   43
30 - 100 keV given as smoothed background cross section in File 3.7443 1451   44
                                                                  7443 1451   45
                    ----- MF=3 MT=102 -----                       7443 1451   46
    Capture cross sections from 1.000E-5 eV to 100 keV are recon- 7443 1451   47
structed from evaluated  MLBW resolved  and  unresolved resonance 7443 1451   48
parameters. Contribution of F-wave in the neutron energy interval 7443 1451   49
30 - 100 keV is added as described above.                         7443 1451   50
    Data base for the evaluation W-186(n,g)W-187 excitation func- 7443 1451   51
tion in the neutron energy range 100 keV - 20 MeV was formed from 7443 1451   52
microscopic experimental data [4-6],[8-9],[12-25] and data recei- 7443 1451   53
ved from theoretical model calculations. Experimental data [8-9], 7443 1451   54
[16-20], [22], [24] were corrected to the new standards.  Uncer-  7443 1451   55
tainty for cross section values measured by Bartolome et al. [4]  7443 1451   56
was evaluated as +-16%.  Theoretical model calculations  was done 7443 1451   57
by means of GNASH code [26].  New modified  version of GNASH  was 7443 1451   58
utilized for calculations [27].  Data from GNASH calculation were 7443 1451   59
dominant in the neutron energy range 4 - 20 MeV.                  7443 1451   60
    The evaluation  W-186(n,g)W-187  excitation function  in  the 7443 1451   61
energy range above 100 keV has been carried out within the frame- 7443 1451   62
work  of generalized least squares method , rational function was 7443 1451   63
used as model function [28]. Procedure of calculation recommended 7443 1451   64
cross section data was performed by means of PADE-2 code [29].    7443 1451   65
   Capture cross section at En=0.0253 eV and Resonance Integral   7443 1451   66
(0.5 to 2.0E+7 eV) from present evaluation are given below in the 7443 1451   67
Table 1. in a comparison with data from compilations [1] and [30].7443 1451   68
                                                      Table 1.    7443 1451   69
        --------------------------------------------------        7443 1451   70
          Parameters            Values, barn    References        7443 1451   71
        --------------------------------------------------        7443 1451   72
        Capture cross section   38.47 +- 0.85   This eval.        7443 1451   73
        at En=0.0253 eV         37.9  +- 0.6     [ 1]             7443 1451   74
                                37    +- 2       [30]             7443 1451   75
                                38.5  +- 0.5     [31]             7443 1451   76
        --------------------------------------------------        7443 1451   77
        Resonance Integral      482.2           This eval.        7443 1451   78
                                485   +- 15      [ 1]             7443 1451   79
                                485   +- 15      [30]             7443 1451   80
                                485   +- 15      [31]             7443 1451   81
        --------------------------------------------------        7443 1451   82
                                                                  7443 1451   83
                    ----- MF=33 MT=102-----                       7443 1451   84
    Uncertainties in  the evaluated excitation function  for the  7443 1451   85
reaction  W-186(n,g)W-187  are  given  in  the three  independent 7443 1451   86
matrixes.                                                         7443 1451   87
    In the energy range 1.000E-05 - 100 eV uncertainties are pre- 7443 1451   88
sented in the form of relative covariance matrix for the 14-neut- 7443 1451   89
ron energy groups (LB=5).  Eigenvalues  of this 6-th digits rela- 7443 1451   90
tive covariance matrix are the following:                         7443 1451   91
                                                                  7443 1451   92
    1.14625E-10    1.09510E-07    7.28111E-07    8.61003E-06      7443 1451   93
    4.80743E-05    5.34800E-05    5.91642E-05    6.60535E-05      7443 1451   94
    8.44288E-05    1.48138E-04    1.95936E-04    2.39607E-04      7443 1451   95
    8.15874E-04    8.38515E-03                                    7443 1451   96
                                                                  7443 1451   97
    In the energy range 0.1 - 8.5 keV  uncertainties are given in 7443 1451   98
the form  of diagonal matrix  of uncertainties  for 19-th neutron 7443 1451   99
energy intervals (LB=1)                                           7443 1451  100
    In the energy range  8.5 keV - 20 MeV  uncertainties are pre- 7443 1451  101
sented in the form of relative covariance matrix for the 24-neut- 7443 1451  102
ron energy groups (LB=5).  Eigenvalues  of this 6-th digits rela- 7443 1451  103
tive covariance matrix are the following:                         7443 1451  104
                                                                  7443 1451  105
    6.81049E-10    1.45633E-05    5.83401E-05    1.88615E-04      7443 1451  106
    6.00477E-04    7.08017E-04    9.54276E-04    1.08032E-03      7443 1451  107
    1.26144E-03    1.35976E-03    1.50022E-03    1.66258E-03      7443 1451  108
    1.66943E-03    2.15756E-03    2.87259E-03    3.83276E-03      7443 1451  109
    6.81420E-03    9.70769E-03    9.99331E-03    1.17664E-02      7443 1451  110
    1.48009E-02    1.93593E-02    2.04003E-02    2.26206E-01      7443 1451  111
                                                                  7443 1451  112
References :                                                      7443 1451  113
 1. S.F.Mughabghab et al.  Neutron Cross Sections, vol.1, part B, 7443 1451  114
    New York, Academic Press, 1984                                7443 1451  115
 2. S.I.Sukhoruchkin et al. Landolt Bornstein New Series, v.I/16B,7443 1451  116
    ed. H.Schopper, Springer, 1998, pp.w19-w23                    7443 1451  117
 3. S.V.Kapchigashev, Ju.P.Popov, F.L.Shapiro  EXFOR 40755.005    7443 1451  118
 4. Z.M.Bartolome et al.  Nucl. Sci. Eng., v.37, pp.137-156, 1969 7443 1451  119
 5. R.L.Macklin et al.  Nucl. Sci. Eng., v.84, p.98, June 1983    7443 1451  120
 6. M.V.Bokhovko et al.  Voprosy Atomnoj Nauki i Tekhniki, Ser.:  7443 1451  121
    Yadernye Konstanty, v.1, p.39, February 1986                  7443 1451  122
 7. G.N.Manturov et al.  Voprosy Atomnoy Nauki i Tekhniki, Ser.:  7443 1451  123
    Jadernye Konstanty, v.1, p.50, 1983                           7443 1451  124
 8. Yu.Ya.Stavisskii, V.A.Tolstikov   Atomnaja Energija, v.9,     7443 1451  125
    p.401, 1960                                                   7443 1451  126
 9. V.N.Kononov et al.  Yadernaja Fizika, v.4, no.2, p.282, 1966  7443 1451  127
10. P.T.Guenther. et al.  Phys. Rev. C., v.26, p.2433, 1982       7443 1451  128
11. V.N.Kononov  et al.  Sov J. of Nuclear Physics, v.46, part 1, 7443 1451  129
    p.51, July 1987                                               7443 1451  130
12. R.Allen et al.  Nature, v.161, p.727, May 1948                7443 1451  131
13. L.E.Beghian, H.H.Halban  Nature, v.163, p.366, March 1949     7443 1451  132
14. J.L.Perkin et al.  Proc. Phys. Soc., v.72, p.505, 1958        7443 1451  133
15. A.I.Leipunskij et al. Second UN Conf. on the Peaceful Uses of 7443 1451  134
    Atomic Energy, Geneva, 1-13 September 1958, v.15, p.50(2219)  7443 1451  135
16. M.V.Pasechnik et al.  Second UN Conf. on the Peaceful Uses of 7443 1451  136
    Atomic Energy, Geneva, 1-13 September 1958, v.15, p.18(2030)  7443 1451  137
17. A.E.Johnsrud et al.  Phys. Rev., v.116, p.927, 1959           7443 1451  138
18. G.G.Zaikin et al.  Jaderno-Fizicheskie Issledovanija (USSR    7443 1451  139
    progress report), v.6, p.103, 1968                            7443 1451  140
19. M.Lindner et al.  Nucl. Sci. Eng., v.59, p.381, April 1976    7443 1451  141
20. O.Schwerer et al.  Nucl. Phys., v.A264, p.105, June 1976      7443 1451  142
21. M.Valkonen  Report JU-RR-1/1976, Jyvaeskylae University, 1976 7443 1451  143
    M.Valkonen et al.  J. Inorg. Nucl. Chem., v.36, p.715, 1974   7443 1451  144
22. G.Magnusson et al.  Physica Scripta, v.21, p.21, January 1980 7443 1451  145
23. J.Voignier et al.  Report CEA-R-5089, August 1981 ;           7443 1451  146
    J.Voignier et al.  Nucl. Sci. Eng., v.93, p.43, 1986          7443 1451  147
24. Yu.N.Trofimov   1st International Conf. on Neutron Physics,   7443 1451  148
    Kiev, 14-16 September 1987, v.3, p.331                        7443 1451  149
25. Zhang Guohui, Lu Hanlin et al. Communication of Nuclear Data  7443 1451  150
    Progress, No. 23, Atomic Energy Press, Beijing, June, 2000    7443 1451  151
26. P.G.Young, E.D.Arthur  A Preequilibrium Statistical Nuclear   7443 1451  152
    Model Code for Calculation of Cross Section and Emission      7443 1451  153
    Spectra. Report LA-6947, Los Alamos, 1977                     7443 1451  154
27. E.L.Trykov, G.Ya.Tertychnyi  Private communication, IPPE,     7443 1451  155
    Obninsk, May 1999                                             7443 1451  156
28. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 7443 1451  157
    st's Meeting on Evaluation and Processing of Covariance Data, 7443 1451  158
    Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105  7443 1451  159
29. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          7443 1451  160
30. A.V.Ignatyuk et al.  Landolt Bornstein New Series, v.I/16A,   7443 1451  161
    Part 1, ed. H.Schopper, Springer, 1998, p.8-24                7443 1451  162
31. S.F.Mughabghab et al.  Termal Neutron Capture Cross Sections  7443 1451  163
    Resonance Integrals and G-factors, Report INDC(NDS)-440,      7443 1451  164
    IAEA, Vienna, February 2003                                   7443 1451  165
***************************************************************** 7443 1451  166
 **********    End of (N,G) bibliographical component  ********** 7443 1451  167
***************************************************************** 7443 1451  168
  74-W -186 LANL,ANL  EVAL-OCT96 M.B.CHADWICK,P.G.YOUNG,ARTHUR    7443 1451  169
 Ch96a,Ch96b,Ar80,Ch99DIST-SEP 1 REV1-                 20010926   7443 1451  170
----ENDF/B-VI         MATERIAL 7443                               7443 1451  171
  MF=3 MT=  1  Total Cross Section                                7443 1451  172
       MT=  2  Elastic Scattering Cross Section                   7443 1451  173
***************************************************************** 7443 1451  174
                                                                  7443 1451  175
 ***************** Program LINEAR (VERSION 2002-1) ***************7443 1451  176
 For All Data Greater than 1.0000E-10 barns in Absolute Value     7443 1451  177
 Data Linearized to Within an Accuracy of .100000000 per-cent     7443 1451  178
 ***************** Program RECENT (VERSION 2002-1) ***************7443 1451  179
 for All Data Greater than 1.0000E-10 barns in Absolute Value     7443 1451  180
 Data Linearized to within an Accuracy of .100000000 per-cent     7443 1451  181
 ***************** Program SIGMA1 (VERSION 2002-1) ***************7443 1451  182
 Data Doppler Broadened to 300.000000 Kelvin                      7443 1451  183
 for All Data Greater than 1.0000E-10 barns in Absolute Value     7443 1451  184
 Data Linearized to Within an Accuracy pf .100000000 per-cent     7443 1451  185
 ***************** Program FIXUP (Version 2002-1) ****************7443 1451  186
 Corrected ZA/AWR in All Sections-----------------------------Yes 7443 1451  187
 Corrected Thresholds-----------------------------------------Yes 7443 1451  188
 Extended Cross Sections to 20 MeV----------------------------No  7443 1451  189
 Allow Cross Section Deletion---------------------------------No  7443 1451  190
 Allow Cross Section Reconstruction---------------------------No  7443 1451  191
 Make All Cross Sections Non-Negative-------------------------Yes 7443 1451  192
 Delete Energies Not in Ascending Order-----------------------Yes 7443 1451  193
 Deleted Duplicate Points-------------------------------------Yes 7443 1451  194
 Check for Ascending MAT/MF/MT Order--------------------------Yes 7443 1451  195
 Check for Legal MF/MT Numbers--------------------------------Yes 7443 1451  196
 Allow Creation of Missing Sections---------------------------No  7443 1451  197
 Allow Insertion of Energy Points-----------------------------No  7443 1451  198
 Create Uniform Energy Grid-----------------------------------No  7443 1451  199
 Delete Section if Cross Section =0 at All Energies-----------Yes 7443 1451  200
 ***************** Program GROUPIE (VERSION 2002-1) **************7443 1451  201
 Unshielded Group Averages Using  640 Groups                      7443 1451  202
 Weighting Spectrum: Flat (Constant) Spectrum                     7443 1451  203
                                1        451        207          17443 1451  204
                                2        151          4          17443 1451  205
                                3        102        217          17443 1451  206
                               33        102         94          17443 1451  207
                                                                  7443 1  099999
                                                                  7443 0  0    0
 7.41860E+4 1.84357E+2          0          0          1          07443 2151    1
 7.41860E+4 1.00000E+0          0          0          1          07443 2151    2
 1.00000E-5 8.50000E+3          0          0          0          07443 2151    3
 0.0        7.64000E-1          0          0          0          07443 2151    4
                                                                  7443 2  099999
                                                                  7443 0  0    0
 7.41860E+4 1.84357E+2          0          0          0          07443 3102    1
 5.46700E+6 5.46700E+6          0          0          1        6417443 3102    2
        641          1                                            7443 3102    3
 .000100000 603.335846 .000105000 589.267631 .000110000 575.9026837443 3102    4
 .000115000 563.587364 .000120000 549.190298 .000127500 533.2169627443 3102    5
 .000135000 518.623372 .000142500 505.212229 .000150000 490.6976817443 3102    6
 .000160000 475.577316 .000170000 461.819668 .000180000 449.1912287443 3102    7
 .000190000 437.441542 .000200000 426.713841 .000210000 416.6208847443 3102    8
 .000220000 407.246173 .000230000 398.535864 .000240000 388.3117177443 3102    9
 .000255000 377.076879 .000270000 368.407585 .000280000 358.7570467443 3102   10
 .000300000 346.987888 .000320000 336.331282 .000340000 326.5715237443 3102   11
 .000360000 317.582189 .000380000 309.376115 .000400000 300.8208007443 3102   12
 .000425000 292.066023 .000450000 284.066608 .000475000 276.7330497443 3102   13
 .000500000 269.836551 .000525000 263.533426 .000550000 257.5790457443 3102   14
 .000575000 252.041159 .000600000 246.365181 .000630000 240.5260707443 3102   15
 .000660000 235.183230 .000690000 230.057942 .000720000 224.6043127443 3102   16
 .000760000 218.756748 .000800000 213.327421 .000840000 208.3517907443 3102   17
 .000880000 203.622726 .000920000 199.287405 .000960000 195.1354907443 3102   18
 .001000000 190.831817 .001050000 186.339264 .001100000 182.1277957443 3102   19
 .001150000 178.247247 .001200000 173.669665 .001275000 168.6387387443 3102   20
 .001350000 164.039287 .001425000 159.746960 .001500000 155.1870537443 3102   21
 .001600000 150.419482 .001700000 146.067368 .001800000 142.0423177443 3102   22
 .001900000 138.365382 .002000000 134.956017 .002100000 131.7566167443 3102   23
 .002200000 128.826606 .002300000 126.024764 .002400000 122.8276247443 3102   24
 .002550000 119.274676 .002700000 116.495377 .002800000 113.4751727443 3102   25
 .003000000 109.757167 .003200000 106.374065 .003400000 103.2810967443 3102   26
 .003600000 100.461353 .003800000 97.8587164 .004000000 95.14697857443 3102   27
 .004250000 92.3949345 .004500000 89.8831489 .004750000 87.53526427443 3102   28
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 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0744333102   43
 0.00000+ 0 0.00000+ 0 0.00000+ 0 3.45091- 3 2.80852- 3 2.21586- 3744333102   44
 2.33008- 3 2.24225- 3 2.24764- 3 2.35577- 3 2.31540- 3 2.07642- 3744333102   45
 2.17529- 3 2.13680- 3 2.17648- 3 2.03297- 3 2.64651- 3 3.36273- 3744333102   46
 3.80209- 3 4.16442- 3 4.30034- 3 4.28549- 3 4.27385- 3 4.24642- 3744333102   47
 4.25625- 3 4.79503- 3 6.22892- 3 3.12614- 3 2.51259- 3 2.15417- 3744333102   48
 2.31329- 3 2.19087- 3 2.31557- 3 2.35375- 3 1.99766- 3 2.16160- 3744333102   49
 2.08147- 3 2.14741- 3 1.99747- 3 2.58848- 3 3.38341- 3 3.69132- 3744333102   50
 4.04454- 3 4.30335- 3 4.25696- 3 4.15427- 3 4.16309- 3 4.24875- 3744333102   51
 4.68271- 3 6.14212- 3 2.98528- 3 2.49109- 3 2.01450- 3 2.27918- 3744333102   52
 2.30790- 3 2.18183- 3 2.07909- 3 2.06719- 3 2.08292- 3 2.08984- 3744333102   53
 1.97169- 3 2.57827- 3 3.16499- 3 3.74549- 3 4.08669- 3 4.07084- 3744333102   54
 4.10313- 3 4.19884- 3 4.12332- 3 4.04548- 3 4.68194- 3 6.00941- 3744333102   55
 3.17832- 3 2.66244- 3 2.07891- 3 2.30572- 3 2.33953- 3 1.94182- 3744333102   56
 2.11518- 3 2.03561- 3 2.09740- 3 1.95226- 3 2.53405- 3 3.31215- 3744333102   57
 3.60739- 3 3.96238- 3 4.21580- 3 4.16395- 3 4.06369- 3 4.07706- 3744333102   58
 4.15960- 3 4.58220- 3 6.01328- 3 3.40942- 3 2.54538- 3 2.21842- 3744333102   59
 2.21640- 3 1.99538- 3 2.04750- 3 2.01617- 3 2.05438- 3 1.93119- 3744333102   60
 2.51020- 3 3.18624- 3 3.62121- 3 3.94521- 3 4.06882- 3 4.06998- 3744333102   61
 4.06225- 3 4.02439- 3 4.03336- 3 4.55297- 3 5.90581- 3 3.67830- 3744333102   62
 2.41506- 3 2.22968- 3 2.01926- 3 2.06278- 3 2.05497- 3 2.07286- 3744333102   63
 1.94814- 3 2.54615- 3 3.17719- 3 3.67252- 3 4.02448- 3 4.07891- 3744333102   64
 4.08203- 3 4.12597- 3 4.07952- 3 4.04296- 3 4.61531- 3 5.96228- 3744333102   65
 4.07182- 3 3.04717- 3 2.72009- 3 2.85865- 3 2.82259- 3 2.84474- 3744333102   66
 2.72097- 3 3.56800- 3 4.52475- 3 5.12145- 3 5.62007- 3 5.79392- 3744333102   67
 5.76950- 3 5.76004- 3 5.72564- 3 5.73317- 3 6.46176- 3 8.39467- 3744333102   68
 5.20771- 3 3.71857- 3 3.46976- 3 3.46460- 3 3.50192- 3 3.41207- 3744333102   69
 4.46116- 3 5.64115- 3 6.44819- 3 7.01240- 3 7.20858- 3 7.22485- 3744333102   70
 7.22639- 3 7.14667- 3 7.15233- 3 8.09342- 3 1.04846- 2 4.89023- 3744333102   71
 3.75588- 3 3.59533- 3 3.56163- 3 3.47878- 3 4.58232- 3 5.68368- 3744333102   72
 6.55293- 3 7.26525- 3 7.33644- 3 7.29426- 3 7.39179- 3 7.34179- 3744333102   73
 7.25344- 3 8.27546- 3 1.07087- 2 4.83225- 3 3.76382- 3 3.75857- 3744333102   74
 3.69770- 3 4.82828- 3 6.14842- 3 6.95657- 3 7.58153- 3 7.84944- 3744333102   75
 7.84228- 3 7.80493- 3 7.74221- 3 7.77826- 3 8.75400- 3 1.13701- 2744333102   76
 5.08337- 3 3.78225- 3 3.58894- 3 4.74728- 3 6.10842- 3 6.75552- 3744333102   77
 7.47777- 3 7.81263- 3 7.71529- 3 7.63195- 3 7.64217- 3 7.70332- 3744333102   78
 8.58921- 3 1.12211- 2 4.38207- 3 3.75869- 3 4.78257- 3 6.12157- 3744333102   79
 6.88179- 3 7.50752- 3 7.79883- 3 7.77937- 3 7.72847- 3 7.67689- 3744333102   80
 7.72032- 3 8.67445- 3 1.12767- 2 5.79606- 3 4.87618- 3 5.89683- 3744333102   81
 6.84062- 3 7.53188- 3 7.58778- 3 7.57968- 3 7.69012- 3 7.61139- 3744333102   82
 7.51960- 3 8.59844- 3 1.11077- 2 1.05503- 2 9.17240- 3 8.44451- 3744333102   83
 9.82314- 3 1.03972- 2 1.00600- 2 9.92327- 3 1.00586- 2 1.01197- 2744333102   84
 1.12332- 2 1.47331- 2 1.82857- 2 1.56549- 2 1.18555- 2 1.18792- 2744333102   85
 1.32773- 2 1.33542- 2 1.24270- 2 1.25225- 2 1.45984- 2 1.84671- 2744333102   86
 2.38468- 2 2.09590- 2 1.38269- 2 1.27699- 2 1.50633- 2 1.52120- 2744333102   87
 1.36771- 2 1.66054- 2 2.12396- 2 2.73440- 2 2.31073- 2 1.57553- 2744333102   88
 1.37127- 2 1.58871- 2 1.66958- 2 1.70147- 2 2.33616- 2 2.84616- 2744333102   89
 2.33479- 2 1.68693- 2 1.48460- 2 1.68731- 2 1.83454- 2 2.35919- 2744333102   90
 2.69987- 2 2.38452- 2 1.67894- 2 1.47043- 2 1.94187- 2 2.35998- 2744333102   91
 2.63049- 2 2.09755- 2 1.50714- 2 1.83217- 2 2.41037- 2 2.35921- 2744333102   92
 1.97452- 2 1.67774- 2 2.36775- 2 2.31409- 2 2.15559- 2 2.28705- 2744333102   93
 3.01605- 2 2.94807- 2 4.61913- 2                                 744333102   94
                                                                  744333  099999
                                                                  7443 0  0    0
                                                                     0 0  0    0
 7.91970E+4 1.95274E+2          0          0         34         107925 1451    1
 0.0        0.0                 0          0          0          67925 1451    2
 1.00000E+0 3.00000E+7          0          0         10       20027925 1451    3
 3.00000E+2 0.0                 1          0        202          67925 1451    4
 79-Au-197 LANL/IRK   EVAL-JAN84 P.G.YOUNG,VONACH ET AL           7925 1451    5
                      DIST-Feb2004                                7925 1451    6
----IRDF-2002         MATERIAL 7925                               7925 1451    7
-----INCIDENT NEUTRON DATA                                        7925 1451    8
------ENDF-6 FORMAT                                               7925 1451    9
 *****************************************************************7925 1451   10
 79-AU-197 LANL       EVAL-JAN84 P.G.YOUNG                        7925 1451   11
 LA-10069-PR          DIST-SEP91 REV1-JUL91            19930129   7925 1451   12
----ENDF/B-VI         MATERIAL 7925         REVISION 1            7925 1451   13
 *****************************************************************7925 1451   14
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************7925 1451   15
DOSIMETRY                                                         7925 1451   16
******************************************************************7925 1451   17
                                                                  7925 1451   18
                  MOD1 OF ENDF/B-VI                               7925 1451   19
                                                                  7925 1451   20
     The following revisions were made for MOD1 of ENDF/B-VI:     7925 1451   21
                                                                  7925 1451   22
 1. MF=1,MT=451 - Comments were added regarding estimated         7925 1451   23
    (expanded) covariance for the Standards Cross Sections.       7925 1451   24
 2. MF=3,MT=102 - Q-value corrected.                              7925 1451   25
                                                                  7925 1451   26
 *****************************************************************7925 1451   27
++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++7925 1451   28
         MF/MT 2151, MF/MT 3 16 AND MF/MT 33 16 FROM FOLLOWING    7925 1451   29
         EVALUATION                                               7925 1451   30
                79-AU-197 IRK-VIENNA EVAL-APR90                   7925 1451   31
                                     DIST-JUN90                   7925 1451   32
                IRK-EVAL.NLIB 25  7925                            7925 1451   33
++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++7925 1451   34
*************** SUMMARY OF ENDF/B-VI EVALUATION ******************7925 1451   35
                                                                  7925 1451   36
   A new evaluation of all neutron and gamma-ray data above the   7925 1451   37
 resonance region is joined with the endf/b-v resolved resonance  7925 1451   38
 region evaluation and with the Version VI standard cross section 7925 1451   39
 for the (n,gamma) reaction below a neutron energy of 2.5 MeV.    7925 1451   40
                                                                  7925 1451   41
*************** GENERAL DESCRIPTION ******************************7925 1451   42
                                                                  7925 1451   43
              P.G.Young and E.D.Arthur                            7925 1451   44
                                                                  7925 1451   45
   the new evaluation for files 3,4,5,12,13,14,15 is based on     7925 1451   46
 statistical theory, hauser-feshbach, preequilibrium calculations 7925 1451   47
 with the comnuc and gnash codes (ref1,2). deformed optical poten-7925 1451   48
 tial of delaroche and ecis coupled-channel code were used to cal-7925 1451   49
 culate neutron transmission coefficients and total and elastic   7925 1451   50
 elastic cross sections (ref3,4). gamma-ray strength functions    7925 1451   51
 were obtained by fitting morgan n,xg data (ref5) at 0.4 and 6.5  7925 1451   52
 mev. calculated results were used for all major reactions except 7925 1451   53
 total cross section. for total, the theoretical cross section    7925 1451   54
 was used as prior in covariance analysis of experimental data    7925 1451   55
 using glucs code (ref6). more details on experimental data used  7925 1451   56
 are given below and in main reference for evaluation (ref 7).    7925 1451   57
                                                                  7925 1451   58
 **************************************************************** 7925 1451   59
                                                                  7925 1451   60
                        STANDARDS COVARIANCES                     7925 1451   61
                                                                  7925 1451   62
 Phase 1 reviewers of the ENDF/B-VI standards cross sections have 7925 1451   63
 expressed the concern that the uncertainties resulting from the  7925 1451   64
 combination of R-matrix and simultaneous evaluations might have  7925 1451   65
 led to uncertainties that are too small.  As a result, the       7925 1451   66
 Standards Subcommittee produced (at the May, 1990 CSEWG meeting) 7925 1451   67
 a set of expanded covariance estimates for the standard cross    7925 1451   68
 section reactions.  These uncertainties are estimates such that  7925 1451   69
 if a modern day experiment were performed on a given standard    7925 1451   70
 cross section using the best techniques, approximately 2/3 of    7925 1451   71
 the results should fall within these expanded uncertainties. The 7925 1451   72
 expanded uncertainties for the Au-197(n,gamma) cross section are 7925 1451   73
 given in the following table and are compared to values from the 7925 1451   74
 combined output of the standards covariance analysis:            7925 1451   75
                                                                  7925 1451   76
    Energy Range    Estimated Uncertainty    Combined Analysis    7925 1451   77
      (keV)              (percent)               (percent)        7925 1451   78
                                                                  7925 1451   79
    2.53E-05                 0.14                   0.14          7925 1451   80
     200 - 500               3.0                    1.31          7925 1451   81
     500 - 1000              3.5                    2.1           7925 1451   82
    1000 - 2500              4.5                    2.0           7925 1451   83
                                                                  7925 1451   84
                                                                  7925 1451   85
*************** mf=2 resonance parameters ************************7925 1451   86
                                                                  7925 1451   87
 mt=151    resolved resonance parameters    given from 1.0e-05ev  7925 1451   88
           to 2 kev based on ref8 and references therein          7925 1451   89
           and a bound level. some of the reson. spin assignments 7925 1451   90
           from ref9. from 2 to 4.827 kev the parameters are based7925 1451   91
           on macklin et al and hoffman et al normalized data.    7925 1451   92
           see refs 10 and 11.                                    7925 1451   93
           thermal cross sections are as follows:                 7925 1451   94
                capture = 98.71 b                                 7925 1451   95
                scattering = 6.84 b                               7925 1451   96
                total = 105.55 b                                  7925 1451   97
           the absorption resonance integral is 1559 b            7925 1451   98
                                                                  7925 1451   99
*************** mf=3 smooth neutron cross sections ***************7925 1451  100
                                                                  7925 1451  101
 mt=  1  total cross section.  based on glucs covariance analysis 7925 1451  102
    using deformed optical model calculation as the prior and     7925 1451  103
    experimental data from refs 12-22, 29 for fitting.            7925 1451  104
 mt=  2  elastic cross section.  difference of mt=1 and sum of    7925 1451  105
    all nonelastic cross sections. closely approximates theore-   7925 1451  106
    tical results.                                                7925 1451  107
 mt=102  (n,gamma) cross section.  below 2.5 MeV, adopted the     7925 1451  108
    ENDF/B-VI standard cross section (Ref.30,31) down to the      7925 1451  109
    resonance region.  At higher energies, the theoretical cal-   7925 1451  110
    culations were adjusted to agree with experimental data. A    7925 1451  111
    semi-direct component normalized to an average of experimental7925 1451  112
    data at 14 MeV was included above En = 6 MeV.                 7925 1451  113
    at higher energies, use theoretical calculations, which agree 7925 1451  114
    reasonably with available exp. data.  above 5 mev, calculation7925 1451  115
    includes semi-direct component normalized to average of       7925 1451  116
    14 mev data.                                                  7925 1451  117
                                                                  7925 1451  118
*************** mf=33 neutron cross section covariances **********7925 1451  119
                                                                  7925 1451  120
 mt=  1  total cross section covariance from glucs analysis.      7925 1451  121
                                                                  7925 1451  122
*************** references ***************************************7925 1451  123
                                                                  7925 1451  124
  1. c.l.dunford. ai-aec-12931(1970)                              7925 1451  125
  2. p.g.young, e.d.arthur, la-6947 (1977).                       7925 1451  126
  3. j.p.delaroche, harwell conference (1978)p.366.               7925 1451  127
  4. j.raynal, iaea smr-9/8 (1970).                               7925 1451  128
  5. g.l.morgan, e.newman, ornl-tm-4973 (1975).                   7925 1451  129
  6. d.m.hetrick, c.y.fu, ornl/tm-7341 (1980).                    7925 1451  130
  7. p.g.young, e.d.arthur, in la-10069-pr (1984)p.12.            7925 1451  131
  8. s.f.mughabghab and d.i.garber bnl-325,3rd edn,vol i(1973).   7925 1451  132
  9. a.lottin and a.jain conf on nuclear structure study with     7925 1451  133
          neutrons,budapest,1972 p34 and private communication.   7925 1451  134
 10. r.macklin et al. phys. rev/c 11,1270(1975) and private       7925 1451  135
          communication.                                          7925 1451  136
 11. m.m. hoffman et al. 71knoxville conf., 2, 868(1971)          7925 1451  137
 12. w.poenitz et al., nuc.sci.eng. 78, 333(1981).                7925 1451  138
 13. d.g.foster jr., d.glasgow, phys.rev. c3, 576(1971).          7925 1451  139
 14. k.k.seth,phys.letters,16,306(1965).                          7925 1451  140
 15. s.c.snowdon, phys.rev. 90, 615(1953).                        7925 1451  141
 16. j.f.whalen,anl-7210,16(1966).                                7925 1451  142
 17. n.nereson, phys.rev. 94, 1678(1954).                         7925 1451  143
 18. a.bratenahl et al., phys.rev. 110, 927(1958).                7925 1451  144
 19. j.p.conner,phys.rev.109,1268(1958).                          7925 1451  145
 20. j.h.coon,phys.rev.88,562(1952).                              7925 1451  146
 21. j.m.peterson,phys.rev.120,521(1960).                         7925 1451  147
 22. e.g.bilpuch,private communication(1959).                     7925 1451  148
 23. j.frehaut et al, proc. 10-50 mev conf, bnl-ncs-51245 (1980)  7925 1451  149
          page 399.                                               7925 1451  150
 24. l.r.veeser et al, phys.rev. c16, 1792(1977).                 7925 1451  151
 25. b.p.bayhurst et al, phys.rev. c12, 451(1975).                7925 1451  152
 26. r.j.prestwood and b.p.bayhurst,phys.rev.121,1438(1961).      7925 1451  153
 27. c.kalbach and f.mann, bnl-ncs-5/245,p.689 (1980).            7925 1451  154
 28. v.j.orphan et al, ga-10248 (1970).                           7925 1451  155
 29. d.c.larson, proc. 10-50 mev conf, bnl-ncs-51245 (1980) p.277.7925 1451  156
 30. A.Carlson et al., Nuc.Data for Basic & Applied Science,      7925 1451  157
     Santa Fe, NM (1985) p.1429.                                  7925 1451  158
 31. W.Poenitz, ANL-West, personnal communication (1989).         7925 1451  159
                                                                  7925 1451  160
******************************************************************7925 1451  161
                                                                  7925 1451  162
                                                                  7925 1451  163
                                                                  7925 1451  164
                                                                  7925 1451  165
 ***************** PROGRAM FIXUP (VERSION 86-2) ******************7925 1451  166
 *RECONSTRUCTED MT NUMBERS                                        7925 1451  167
   4 =+( 51, 91)                                                  7925 1451  168
 103 =+(700,718)                                                  7925 1451  169
 104 =+(720,738)                                                  7925 1451  170
 105 =+(740,758)                                                  7925 1451  171
 106 =+(760,778)                                                  7925 1451  172
 107 =+(780,798)                                                  7925 1451  173
 101 =+(102,114)                                                  7925 1451  174
  27 =+( 18, 18)+(101,101)                                        7925 1451  175
   3 =+(  4,  4)+(  6,  9)+( 16, 17)+( 22, 37)                    7925 1451  176
  19 =+( 18, 18)-( 20, 21)-( 38, 38)                              7925 1451  177
   1 =+(  2,  3)                                                  7925 1451  178
 ***************** Program LINEAR (VERSION 2002-1) ***************7925 1451  179
 For All Data Greater than 1.0000E-10 barns in Absolute Value     7925 1451  180
 Data Linearized to Within an Accuracy of .100000000 per-cent     7925 1451  181
 ***************** Program RECENT (VERSION 2002-1) ***************7925 1451  182
 for All Data Greater than 1.0000E-10 barns in Absolute Value     7925 1451  183
 Data Linearized to within an Accuracy of .100000000 per-cent     7925 1451  184
 ***************** Program SIGMA1 (VERSION 2002-1) ***************7925 1451  185
 Data Doppler Broadened to 300.000000 Kelvin                      7925 1451  186
 for All Data Greater than 1.0000E-10 barns in Absolute Value     7925 1451  187
 Data Linearized to Within an Accuracy pf .100000000 per-cent     7925 1451  188
 ***************** Program FIXUP (Version 2002-1) ****************7925 1451  189
 Corrected ZA/AWR in All Sections-----------------------------Yes 7925 1451  190
 Corrected Thresholds-----------------------------------------Yes 7925 1451  191
 Extended Cross Sections to 20 MeV----------------------------No  7925 1451  192
 Allow Cross Section Deletion---------------------------------No  7925 1451  193
 Allow Cross Section Reconstruction---------------------------No  7925 1451  194
 Make All Cross Sections Non-Negative-------------------------Yes 7925 1451  195
 Delete Energies Not in Ascending Order-----------------------Yes 7925 1451  196
 Deleted Duplicate Points-------------------------------------Yes 7925 1451  197
 Check for Ascending MAT/MF/MT Order--------------------------Yes 7925 1451  198
 Check for Legal MF/MT Numbers--------------------------------Yes 7925 1451  199
 Allow Creation of Missing Sections---------------------------No  7925 1451  200
 Allow Insertion of Energy Points-----------------------------No  7925 1451  201
 Create Uniform Energy Grid-----------------------------------No  7925 1451  202
 Delete Section if Cross Section =0 at All Energies-----------Yes 7925 1451  203
 ***************** Program GROUPIE (VERSION 2002-1) **************7925 1451  204
 Unshielded Group Averages Using  640 Groups                      7925 1451  205
 Weighting Spectrum: Flat (Constant) Spectrum                     7925 1451  206
                                1        451        212          27925 1451  207
                                2        151          4          07925 1451  208
                                3         16         43          17925 1451  209
                                3        102        217          27925 1451  210
                               33         16         71          17925 1451  211
                               33        102         26          17925 1451  212
                                                                  7925 1  099999
                                                                  7925 0  0    0
 7.91970E+4 1.95275E+2          0          0          1          07925 2151    1
 7.91970E+4 1.00000E+0          0          0          1          07925 2151    2
 1.00000E-5 5.00000E+3          0          0          0          07925 2151    3
 1.50000E+0 9.80000E-1          0          0          0          07925 2151    4
                                                                  7925 2  099999
                                                                  7925 0  0    0
 7.91970E+4 1.95274E+2          0          0          0          07925 3 16    1
-8.08000E+6-8.08000E+6          0          0          1        1207925 3 16    2
        120          1                                            7925 3 16    3
 8100000.00 .005579896 8200000.00 .023230150 8300000.00 .0417860347925 3 16    4
 8400000.00 .071166000 8500000.00 .104974000 8600000.00 .1404245007925 3 16    5
 8700000.00 .179890000 8800000.00 .220456917 8900000.00 .2812400007925 3 16    6
 9000000.00 .350293333 9100000.00 .419346667 9200000.00 .4888333337925 3 16    7
 9300000.00 .560920000 9400000.00 .633440000 9500000.00 .7059600007925 3 16    8
 9600000.00 .778480000 9700000.00 .851136750 9800000.00 .9246140007925 3 16    9
 9900000.00 .998228000 10000000.0 1.07184200 10100000.0 1.145456007925 3 16   10
 10200000.0 1.21760825 10300000.0 1.28099000 10400000.0 1.342910007925 3 16   11
 10500000.0 1.40483000 10600000.0 1.46675000 10700000.0 1.524579007925 3 16   12
 10800000.0 1.55786200 10900000.0 1.58705400 11000000.0 1.616246007925 3 16   13
 11100000.0 1.64543800 11200000.0 1.67711725 11300000.0 1.723720007925 3 16   14
 11400000.0 1.77281000 11500000.0 1.82190000 11600000.0 1.870990007925 3 16   15
 11700000.0 1.91616500 11800000.0 1.93785000 11900000.0 1.955620007925 3 16   16
 12000000.0 1.97339000 12100000.0 1.99116000 12200000.0 2.008416687925 3 16   17
 12300000.0 2.02259345 12400000.0 2.03625690 12500000.0 2.049920347925 3 16   18
 12600000.0 2.06358379 12700000.0 2.07724724 12800000.0 2.090910697925 3 16   19
 12900000.0 2.10411356 13000000.0 2.10718360 13100000.0 2.106108407925 3 16   20
 13200000.0 2.10503320 13300000.0 2.10395800 13400000.0 2.102882807925 3 16   21
 13500000.0 2.10180760 13600000.0 2.10313545 13700000.0 2.106866367925 3 16   22
 13800000.0 2.11048693 13900000.0 2.11168000 14000000.0 2.111880007925 3 16   23
 14100000.0 2.11336363 14200000.0 2.11798500 14300000.0 2.122594637925 3 16   24
 14400000.0 2.12380800 14500000.0 2.12363200 14600000.0 2.124854387925 3 16   25
 14700000.0 2.12949500 14800000.0 2.13413834 14900000.0 2.135423147925 3 16   26
 15000000.0 2.13533400 15100000.0 2.13524486 15200000.0 2.135155717925 3 16   27
 15300000.0 2.13506657 15400000.0 2.13497743 15500000.0 2.134888297925 3 16   28
 15600000.0 2.13479914 15700000.0 2.13272231 15800000.0 2.118719337925 3 16   29
 15900000.0 2.10272867 16000000.0 2.08673800 16100000.0 2.070747337925 3 16   30
 16200000.0 2.05475667 16300000.0 2.03876600 16400000.0 2.022775337925 3 16   31
 16500000.0 2.00678467 16600000.0 1.99079400 16700000.0 1.974803337925 3 16   32
 16800000.0 1.95881267 16900000.0 1.94282200 17000000.0 1.926831337925 3 16   33
 17100000.0 1.91084067 17200000.0 1.89294833 17300000.0 1.863646007925 3 16   34
 17400000.0 1.83244200 17500000.0 1.80123800 17600000.0 1.770034007925 3 16   35
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 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   12
 0.000000+0 2.376000-1 0.000000+0 6.262000-3 3.484000-3 3.121000-3792533 16   13
 2.486000-2 1.917000-2 1.580000-2 1.152000-2 5.503000-3 2.688000-3792533 16   14
 0.000000+0 8.017000-5 0.000000+0 9.314000-5 0.000000+0 1.030000-4792533 16   15
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   16
 0.000000+0 0.000000+0 0.000000+0 1.996000-2 0.000000+0 1.297000-3792533 16   17
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   18
 9.968000-4 0.000000+0 0.000000+0 3.167000-5 0.000000+0 0.000000+0792533 16   19
 5.607000-5 0.000000+0 1.065000-3 8.261000-4 0.000000+0 2.342000-3792533 16   20
 2.852000-3 3.357000-3 3.830000-3 0.000000+0 2.740000-3 1.399000-3792533 16   21
 1.102000-3 1.310000-3 1.010000-3 8.327000-4 6.070000-4 2.900000-4792533 16   22
 1.417000-4 0.000000+0 4.225000-6 0.000000+0 4.909000-6 0.000000+0792533 16   23
 5.428000-6 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   24
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.650000-3 7.759000-4792533 16   25
 7.287000-4 5.619000-4 4.632000-4 3.377000-4 1.613000-4 2.084000-4792533 16   26
 0.000000+0 2.350000-6 4.116000-6 2.731000-6 0.000000+0 1.031000-5792533 16   27
 0.000000+0 1.384000-4 1.074000-4 0.000000+0 3.044000-4 3.706000-4792533 16   28
 4.363000-4 4.977000-4 0.000000+0 8.240000-4 6.530000-4 5.035000-4792533 16   29
 4.151000-4 3.026000-4 1.446000-4 7.062000-5 0.000000+0 2.106000-6792533 16   30
 0.000000+0 2.447000-6 0.000000+0 2.705000-6 0.000000+0 0.000000+0792533 16   31
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   32
 0.000000+0 1.355000-2 5.748000-3 4.345000-3 3.316000-3 1.151000-3792533 16   33
 7.874000-4 2.620000-5 1.677000-5 2.424000-5 4.221000-5 2.431000-5792533 16   34
 6.131000-5 2.509000-4 2.602000-4 1.974000-4 6.057000-4 0.000000+0792533 16   35
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 8.846000-3 3.504000-3792533 16   36
 2.691000-3 8.876000-4 6.404000-4 2.408000-5 1.293000-5 2.227000-5792533 16   37
 3.591000-5 2.234000-5 5.315000-5 2.305000-4 2.391000-4 1.814000-4792533 16   38
 5.566000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   39
 5.155000-3 2.030000-3 7.317000-4 4.812000-4 1.441000-5 1.066000-5792533 16   40
 1.333000-5 2.488000-5 1.337000-5 3.556000-5 1.379000-4 1.431000-4792533 16   41
 1.085000-4 3.331000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   42
 0.000000+0 2.957000-3 5.334000-4 3.684000-4 1.255000-5 7.771000-6792533 16   43
 1.161000-5 1.992000-5 1.165000-5 2.903000-5 1.202000-4 1.247000-4792533 16   44
 9.458000-5 2.902000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   45
 0.000000+0 9.967000-4 1.245000-4 0.000000+0 3.713000-6 0.000000+0792533 16   46
 4.314000-6 0.000000+0 4.769000-6 0.000000+0 1.268000-4 0.000000+0792533 16   47
 0.000000+0 2.199000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   48
 5.889000-4 7.578000-6 1.814000-6 7.933000-6 6.584000-6 7.627000-6792533 16   49
 1.587000-5 1.079000-4 2.119000-4 2.050000-4 7.207000-5 2.340000-4792533 16   50
 2.849000-4 3.354000-4 3.826000-4 0.000000+0 1.742000-4 1.488000-4792533 16   51
 1.488000-4 1.488000-4 1.488000-4 1.488000-4 6.333000-6 6.335000-6792533 16   52
 6.361000-6 8.390000-6 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   53
 0.000000+0 1.664000-4 1.488000-4 1.488000-4 1.488000-4 1.488000-4792533 16   54
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   55
 0.000000+0 0.000000+0 0.000000+0 1.716000-4 1.488000-4 1.488000-4792533 16   56
 1.488000-4 3.214000-6 6.714000-6 5.151000-6 7.761000-6 7.435000-6792533 16   57
 9.052000-6 1.066000-5 1.216000-5 0.000000+0 1.690000-4 1.488000-4792533 16   58
 1.488000-4 3.014000-6 3.127000-6 2.372000-6 7.278000-6 0.000000+0792533 16   59
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.690000-4 1.488000-4792533 16   60
 6.608000-6 6.578000-6 6.832000-6 7.785000-6 0.000000+0 0.000000+0792533 16   61
 0.000000+0 0.000000+0 0.000000+0 1.904000-4 5.274000-6 1.145000-5792533 16   62
 8.791000-6 1.273000-5 1.316000-5 1.603000-5 1.886000-5 2.152000-5792533 16   63
 0.000000+0 6.799000-4 1.240000-4 1.451000-4 8.034000-5 0.000000+0792533 16   64
 0.000000+0 0.000000+0 0.000000+0 2.339000-4 7.292000-4 2.290000-4792533 16   65
 8.333000-5 3.463000-4 3.044000-4 3.583000-4 4.087000-4 0.000000+0792533 16   66
 5.244000-4 6.321000-5 1.939000-4 2.361000-4 2.779000-4 3.171000-4792533 16   67
 0.000000+0 1.660000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0792533 16   68
 0.000000+0 1.451000-3 6.695000-4 7.881000-4 8.991000-4 0.000000+0792533 16   69
 2.126000-3 9.595000-4 1.095000-3 0.000000+0 2.659000-3 1.288000-3792533 16   70
 0.000000+0 3.057000-3 0.000000+0 1.717000-3                      792533 16   71
                                                                  792533  099999
 7.91970E+4 1.95274E+2          0          0          0          1792533102    1
 0.000000+0 0.000000+0          0        102          0          2792533102    2
 0.000000+0 0.000000+0          0          1          8          4792533102    3
 1.000000-5 0.000000+0 2.900000+6 5.000000-2 1.000000+7 6.250000-2792533102    4
 2.000000+7 0.000000+0                                            792533102    5
 0.000000+0 0.000000+0          1          5        120         15792533102    6
 1.000000-5 3.000000-1 2.000000+3 1.000000+4 3.750000+4 9.000000+4792533102    7
 1.350000+5 2.050000+5 2.750000+5 4.125000+5 6.250000+5 9.500000+5792533102    8
 1.325000+6 1.900000+6 2.900000+6 1.968800-6 1.968800-6 1.197701-7792533102    9
 1.277322-7 1.199737-7 1.180243-7 1.210327-7 1.175025-7 1.184462-7792533102   10
 1.362774-7 1.098021-7 1.079868-7 1.089638-7 9.914542-8 2.968800-6792533102   11
 1.197701-7 1.277322-7 1.199737-7 1.180243-7 1.210327-7 1.175025-7792533102   12
 1.184462-7 1.362774-7 1.098021-7 1.079868-7 1.089638-7 9.914542-8792533102   13
 1.094560-4 4.577940-5 4.677039-5 3.948904-5 3.768945-5 3.747630-5792533102   14
 3.690735-5 3.428047-5 3.338854-5 3.229846-5 3.154064-5 2.637712-5792533102   15
 6.056941-5 4.202671-5 3.750888-5 3.574985-5 3.503839-5 3.439512-5792533102   16
 3.204558-5 3.144094-5 3.085597-5 2.984776-5 2.493463-5 6.285997-5792533102   17
 4.547523-5 4.201196-5 4.049420-5 3.979974-5 3.715363-5 3.659218-5792533102   18
 3.509315-5 3.465730-5 2.895877-5 8.021999-5 4.906673-5 4.591913-5792533102   19
 4.475850-5 4.261771-5 4.283861-5 4.025727-5 4.041204-5 3.382565-5792533102   20
 8.028292-5 5.304576-5 4.689840-5 4.483827-5 4.540301-5 4.299516-5792533102   21
 4.362940-5 3.699681-5 9.958098-5 5.534255-5 4.876851-5 5.031469-5792533102   22
 4.706249-5 4.804336-5 4.072953-5 9.094943-5 5.454792-5 5.269018-5792533102   23
 4.994396-5 5.121352-5 4.343583-5 8.936425-5 5.920198-5 5.242733-5792533102   24
 5.357873-5 4.570034-5 1.241536-4 6.756325-5 6.367727-5 5.555147-5792533102   25
 1.336240-4 7.281097-5 5.539927-5 1.846612-4 8.162500-5 2.399631-4792533102   26
                                                                  792533  099999
                                                                  7925 0  0    0
                                                                     0 0  0    0
 8.01990E+4 1.97259E+2          0          0         34         108034 1451    1
 0.0        0.0                 0          0          0          68034 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20028034 1451    3
 3.00000E+2 0.0                 1          0         78          58034 1451    4
 80-Hg-199 JAERI      EVAL-MAR90 K.SAKURAI                        8034 1451    5
                      DIST-Feb2004                                8034 1451    6
----IRDF-2002         MATERIAL 8034                               8034 1451    7
-----INCIDENT NEUTRON DATA                                        8034 1451    8
------ENDF-6 FORMAT                                               8034 1451    9
***************************************************************   8034 1451   10
 80-HG-199 JAERI      EVAL-MAR90 K.SAKURAI                        8034 1451   11
                      DIST-JUL91                                  8034 1451   12
----JENDL/D-99        MATERIAL 8034                               8034 1451   13
***************************************************************   8034 1451   14
HISTORY                                                           8034 1451   15
90-03  EVALUATION WAS MADE BY K. SAKURA(JAERI).                   8034 1451   16
90-10  COMPILED TO JENDL DOSIMETRY FILE VERSION 1.                8034 1451   17
91-07  DESCRIPTIVE DATA WERE ADDED.                               8034 1451   18
                                                                  8034 1451   19
            ===== POINT-WISE DATA FILE =====                      8034 1451   20
                                                                  8034 1451   21
 <DOSIMETRY CROSS SECTION>                                        8034 1451   22
      HG-199 (N,N')HG-199M (HALF-LIFE = 42.6 M)                   8034 1451   23
                                                                  8034 1451   24
MF=1  GENERAL INFORMATION                                         8034 1451   25
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          8034 1451   26
                                                                  8034 1451   27
MF=2  RESONANCE PARAMETERS                                        8034 1451   28
 MT=151  PARAMETERS                                               8034 1451   29
     ONLY SPIN AND SCATTERING RADIUS ARE GIVEN.                   8034 1451   30
                                                                  8034 1451   31
MF=3   NEUTRON CROSS SECTIONS                                     8034 1451   32
 MT=51  HG-199(N,N')HG-199M CROSS SECTION                         8034 1451   33
     ISOMERIC STATE = 0.531 MEV 13/2+, HALF-LIFE = 42.6 M         8034 1451   34
     EVALUATION WAS BASED ON THE EXPERIMENTAL DATA REPORTED IN    8034 1451   35
     REF./1/.                                                     8034 1451   36
                                                                  8034 1451   37
MF=33  COVARIANCES OF NEUTRON CROSS SECTIONS                      8034 1451   38
 MT=51                                                            8034 1451   39
    ESTIMATED FROM THE EXPERIMENTAL DATA.                         8034 1451   40
                                                                  8034 1451   41
REFERENCE                                                         8034 1451   42
 1) SAKURAI K., ET AL.: J. NUCL. SCI. TECHNOL., 19, 775 (1982).   8034 1451   43
                                                                  8034 1451   44
***************************************************************   8034 1451   45
                    ----- MF=3 MT=51  -----                       8034 1451   46
  For the IRDF-2002 file this reaction was converted at           8034 1451   47
  IAEA/NDS.                                                       8034 1451   48
  The reaction MF/MT=3/51 was converted to MF/MT=10/ 4            8034 1451   49
  The corresponding co-variance files were also converted         8034 1451   50
  The reaction MF/MT=33/51 was converted to MF/MT=40/ 4           8034 1451   51
***************************************************************   8034 1451   52
 The threshold energy was recalculated from 5.25000+5 to          8034 1451   53
 5.33691+5 to satisfy code FIZCON criteria                        8034 1451   54
                                                                  8034 1451   55
                                                                  8034 1451   56
***************************************************************   8034 1451   57
 ***************** Program LINEAR (VERSION 2002-1) ***************8034 1451   58
 For All Data Greater than 1.0000E-10 barns in Absolute Value     8034 1451   59
 Data Linearized to Within an Accuracy of .100000000 per-cent     8034 1451   60
 ***************** Program SIGMA1 (VERSION 2002-1) ***************8034 1451   61
 Data Doppler Broadened to 300.000000 Kelvin                      8034 1451   62
 for All Data Greater than 1.0000E-10 barns in Absolute Value     8034 1451   63
 Data Linearized to Within an Accuracy pf .100000000 per-cent     8034 1451   64
 ***************** Program FIXUP (Version 2002-1) ****************8034 1451   65
 Corrected ZA/AWR in All Sections-----------------------------Yes 8034 1451   66
 Corrected Thresholds-----------------------------------------Yes 8034 1451   67
 Extended Cross Sections to 20 MeV----------------------------No  8034 1451   68
 Allow Cross Section Deletion---------------------------------No  8034 1451   69
 Allow Cross Section Reconstruction---------------------------No  8034 1451   70
 Make All Cross Sections Non-Negative-------------------------Yes 8034 1451   71
 Delete Energies Not in Ascending Order-----------------------Yes 8034 1451   72
 Deleted Duplicate Points-------------------------------------Yes 8034 1451   73
 Check for Ascending MAT/MF/MT Order--------------------------Yes 8034 1451   74
 Check for Legal MF/MT Numbers--------------------------------Yes 8034 1451   75
 Allow Creation of Missing Sections---------------------------No  8034 1451   76
 Allow Insertion of Energy Points-----------------------------No  8034 1451   77
 Create Uniform Energy Grid-----------------------------------No  8034 1451   78
 Delete Section if Cross Section =0 at All Energies-----------Yes 8034 1451   79
 ***************** Program GROUPIE (VERSION 2002-1) **************8034 1451   80
 Unshielded Group Averages Using  640 Groups                      8034 1451   81
 Weighting Spectrum: Flat (Constant) Spectrum                     8034 1451   82
                                1        451         87          08034 1451   83
                                2        151          4          08034 1451   84
                                8          4          2          08034 1451   85
                               10          4         72          08034 1451   86
                               40          4         17          08034 1451   87
                                                                  8034 1  099999
                                                                  8034 0  0    0
 8.01990E+4 1.97259E+2          0          0          1          08034 2151    1
 8.01990E+4 1.00000E+0          0          0          1          08034 2151    2
 0.0        0.0                 0          0          0          08034 2151    3
 5.00000E-1 1.03000E+0          0          0          0          08034 2151    4
                                                                  8034 2  099999
                                                                  8034 0  0    0
 8.01990E+4 1.97259E+2          0          0          1          18034 8  4    1
 8.01990E+4 0.000000+0         10          0          0          08034 8  4    2
                                                                  8034 8  099999
                                                                  8034 0  0    0
 8.01990E+4 1.97259E+2          0          0          1          0803410  4    1
 0.0       -5.30999E+5      80199          0          1        205803410  4    2
        205          1                                            803410  4    3
 525000.000 .000774677 550000.000 .004195311 575000.000 .007835936803410  4    4
 600000.000 .011840624 630000.000 .016209374 660000.000 .020578124803410  4    5
 690000.000 .024946875 720000.000 .030024219 760000.000 .035400000803410  4    6
 800000.000 .040600000 840000.000 .045800000 880000.000 .051000000803410  4    7
 920000.000 .056200000 960000.000 .061400000 1000000.00 .071400000803410  4    8
 1100000.00 .086200000 1200000.00 .102100000 1300000.00 .124600000803410  4    9
 1400000.00 .148200000 1500000.00 .174000000 1600000.00 .202000000803410  4   10
 1700000.00 .229000000 1800000.00 .250000000 1900000.00 .270000000803410  4   11
 2000000.00 .290000000 2100000.00 .310000000 2200000.00 .329250000803410  4   12
 2300000.00 .344000000 2400000.00 .358000000 2500000.00 .375000000803410  4   13
 2600000.00 .395000000 2700000.00 .414250000 2800000.00 .429000000803410  4   14
 2900000.00 .443000000 3000000.00 .457000000 3100000.00 .471000000803410  4   15
 3200000.00 .484000000 3300000.00 .491000000 3400000.00 .497000000803410  4   16
 3500000.00 .506000000 3600000.00 .518000000 3700000.00 .529500000803410  4   17
 3800000.00 .538000000 3900000.00 .546000000 4000000.00 .554000000803410  4   18
 4100000.00 .562000000 4200000.00 .569500000 4300000.00 .574000000803410  4   19
 4400000.00 .578000000 4500000.00 .582000000 4600000.00 .586000000803410  4   20
 4700000.00 .590000000 4800000.00 .594000000 4900000.00 .598000000803410  4   21
 5000000.00 .600400000 5100000.00 .601200000 5200000.00 .602300000803410  4   22
 5300000.00 .605200000 5400000.00 .608400000 5500000.00 .612000000803410  4   23
 5600000.00 .616000000 5700000.00 .619550000 5800000.00 .620400000803410  4   24
 5900000.00 .620800000 6000000.00 .622900000 6100000.00 .626700000803410  4   25
 6200000.00 .630500000 6300000.00 .634300000 6400000.00 .638100000803410  4   26
 6500000.00 .640000000 6600000.00 .640000000 6700000.00 .640000000803410  4   27
 6800000.00 .640000000 6900000.00 .640000000 7000000.00 .640000000803410  4   28
 7100000.00 .640000000 7200000.00 .640000000 7300000.00 .640000000803410  4   29
 7400000.00 .640000000 7500000.00 .640000000 7600000.00 .640000000803410  4   30
 7700000.00 .640000000 7800000.00 .640000000 7900000.00 .640000000803410  4   31
 8000000.00 .637000000 8100000.00 .631000000 8200000.00 .625625000803410  4   32
 8300000.00 .624000000 8400000.00 .623000000 8500000.00 .622000000803410  4   33
 8600000.00 .621000000 8700000.00 .619625000 8800000.00 .616000000803410  4   34
 8900000.00 .612000000 9000000.00 .606000000 9100000.00 .598000000803410  4   35
 9200000.00 .590500000 9300000.00 .586000000 9400000.00 .582000000803410  4   36
 9500000.00 .576000000 9600000.00 .568000000 9700000.00 .559500000803410  4   37
 9800000.00 .548000000 9900000.00 .536000000 10000000.0 .526000000803410  4   38
 10100000.0 .518000000 10200000.0 .510500000 10300000.0 .506000000803410  4   39
 10400000.0 .502000000 10500000.0 .494000000 10600000.0 .482000000803410  4   40
 10700000.0 .470500000 10800000.0 .462000000 10900000.0 .454000000803410  4   41
 11000000.0 .442000000 11100000.0 .426000000 11200000.0 .410500000803410  4   42
 11300000.0 .398000000 11400000.0 .386000000 11500000.0 .374000000803410  4   43
 11600000.0 .362000000 11700000.0 .349000000 11800000.0 .330000000803410  4   44
 11900000.0 .310000000 12000000.0 .296000000 12100000.0 .288000000803410  4   45
 12200000.0 .279500000 12300000.0 .268000000 12400000.0 .256000000803410  4   46
 12500000.0 .244000000 12600000.0 .232000000 12700000.0 .220500000803410  4   47
 12800000.0 .212000000 12900000.0 .204000000 13000000.0 .196000000803410  4   48
 13100000.0 .188000000 13200000.0 .180500000 13300000.0 .176000000803410  4   49
 13400000.0 .172000000 13500000.0 .168000000 13600000.0 .164000000803410  4   50
 13700000.0 .160000000 13800000.0 .156000000 13900000.0 .152000000803410  4   51
 14000000.0 .148000000 14100000.0 .144000000 14200000.0 .140000000803410  4   52
 14300000.0 .136000000 14400000.0 .132000000 14500000.0 .128000000803410  4   53
 14600000.0 .124000000 14700000.0 .120250000 14800000.0 .118000000803410  4   54
 14900000.0 .116000000 15000000.0 .114000000 15100000.0 .112000000803410  4   55
 15200000.0 .110000000 15300000.0 .108000000 15400000.0 .106000000803410  4   56
 15500000.0 .104600000 15600000.0 .103800000 15700000.0 .102950000803410  4   57
 15800000.0 .101800000 15900000.0 .100600000 16000000.0 .099600000803410  4   58
 16100000.0 .098800000 16200000.0 .098050000 16300000.0 .097600000803410  4   59
 16400000.0 .097200000 16500000.0 .096400000 16600000.0 .095200000803410  4   60
 16700000.0 .093950000 16800000.0 .092400000 16900000.0 .090800000803410  4   61
 17000000.0 .089800000 17100000.0 .089400000 17200000.0 .089000000803410  4   62
 17300000.0 .088600000 17400000.0 .088200000 17500000.0 .087800000803410  4   63
 17600000.0 .087400000 17700000.0 .087000000 17800000.0 .086600000803410  4   64
 17900000.0 .086200000 18000000.0 .085800000 18100000.0 .085400000803410  4   65
 18200000.0 .085000000 18300000.0 .084600000 18400000.0 .084200000803410  4   66
 18500000.0 .083800000 18600000.0 .083400000 18700000.0 .083000000803410  4   67
 18800000.0 .082600000 18900000.0 .082200000 19000000.0 .081800000803410  4   68
 19100000.0 .081400000 19200000.0 .081050000 19300000.0 .081000000803410  4   69
 19400000.0 .081000000 19500000.0 .080800000 19600000.0 .080400000803410  4   70
 19700000.0 .080050000 19800000.0 .080000000 19900000.0 .080000000803410  4   71
 20000000.0 0.0                                                   803410  4   72
                                                                  803410  099999
                                                                  8034 0  0    0
 8.01990E+4 1.97259E+2          0          0          1          0803440  4    1
 0.000000+0-5.309990+5          0          0          0          1803440  4    2
 1.000000+1 0.000000+0          0          4          0          2803440  4    3
 0.000000+0 0.000000+0          0          1         62         31803440  4    4
 1.000000-5 0.000000+0 5.250000+5 2.464000-1 7.500000+5 8.640000-2803440  4    5
 1.000000+6 1.600000-2 2.000000+6 1.600000-2 2.250000+6 2.200000-2803440  4    6
 3.000000+6 2.200000-2 3.500000+6 1.600000-2 4.000000+6 1.600000-2803440  4    7
 5.000000+6 1.600000-2 6.000000+6 1.600000-2 7.000000+6 1.600000-2803440  4    8
 7.250000+6 8.640000-2 8.000000+6 8.640000-2 9.000000+6 8.640000-2803440  4    9
 1.000000+7 8.640000-2 1.100000+7 8.640000-2 1.200000+7 8.640000-2803440  4   10
 1.300000+7 8.640000-2 1.325000+7 3.640000-2 1.375000+7 6.400000-3803440  4   11
 1.400000+7 6.400000-3 1.450000+7 3.640000-2 1.500000+7 3.640000-2803440  4   12
 1.525000+7 8.640000-2 1.600000+7 8.640000-2 1.650000+7 2.464000-1803440  4   13
 1.700000+7 2.464000-1 1.800000+7 2.464000-1 1.900000+7 2.464000-1803440  4   14
 2.000000+7 0.000000+0                                            803440  4   15
 0.000000+0 0.000000+0          0          1          6          3803440  4   16
 1.000000-5 0.000000+0 5.250000+5 3.600000-3 2.000000+7 0.000000+0803440  4   17
                                                                  803440  099999
                                                                  8034 0  0    0
                                                                     0 0  0    0
 8.22040E+4 2.02220E+2          0          0         34         108225 1451    1
 0.0        0.0                 0          0          0          68225 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20028225 1451    3
 3.00000E+2 0.0                 1          0        147          58225 1451    4
 82-Pb-204 FEI        EVAL-Oct01 K.I.Zolotarev                    8225 1451    5
                      DIST-Feb2004                                8225 1451    6
----IRDF-2002         MATERIAL 8225                               8225 1451    7
-----INCIDENT NEUTRON DATA                                        8225 1451    8
------ENDF-6 FORMAT                                               8225 1451    9
***************************************************************** 8225 1451   10
 82-Pb-204 FEI        EVAL-Oct01 K.I.Zolotarev                    8225 1451   11
                      DIST-Oct01                       20011014   8225 1451   12
----BROND-2           MATERIAL 8225                               8225 1451   13
------Russian Reactor Dosimetry File RRDF-2002                    8225 1451   14
***************************************************************** 8225 1451   15
                    ----- MF=3 MT=71  -----                       8225 1451   16
  For the IRDF-2002 file this reaction was converted at IAEA/NDS  8225 1451   17
  The reaction MF/MT=3/71 was converted to MF/MT=10/ 4            8225 1451   18
  The corresponding co-variance files were also converted         8225 1451   19
  The reaction MF/MT=33/71 was converted to MF/MT=40/ 4           8225 1451   20
***************************************************************** 8225 1451   21
Author  of evaluation: K.I.Zolotarev                              8225 1451   22
***************************************************************** 8225 1451   23
                                                                  8225 1451   24
                    ----- MF=3 MT=71  -----                       8225 1451   25
                                                                  8225 1451   26
    In the section MT= 71 are given evaluated  cross section data 8225 1451   27
of neutron inelastic excitation of the 67.2-min isomeric state in 8225 1451   28
in the  lead-204 in the energy range  from threshold  to  20 MeV. 8225 1451   29
The isomeric state is the 21-excited level in Pb-204.  This level 8225 1451   30
has energy 2185.79 keV  with spin and parity 9- [1].              8225 1451   31
    Data base for the evaluation Pb-204(n,n')Pb-204m  excitation  8225 1451   32
function was formed from microscopic experimental data [2-9] and  8225 1451   33
data received from theoretical model calculations. Experimental   8225 1451   34
data [3-9] were corrected to the new standards. Data of Decowski  8225 1451   35
et al. [6] were renormalized also to the result of precise measu- 8225 1451   36
rements of Ryves et al. at 14.3 MeV [8]. Uncertainty for cross    8225 1451   37
section value measured by Bornemisza-Pauspertl et al. at 2.80 MeV 8225 1451   38
[2] was evaluated as +-35 %.  Theoretical model calculations was  8225 1451   39
done by means of GNASH code [10]. New modified  version of GNASH  8225 1451   40
was used for calculations [11].                                   8225 1451   41
    The evaluation Pb-204(n,n')Pb-204m excitation function  from  8225 1451   42
threshold to 20 MeV has been carried out within the framework of  8225 1451   43
generalized least squares method , rational function was used as  8225 1451   44
model function [12]. Procedure of calculation recommended cross   8225 1451   45
section data was performed by means of PADE-2 code [13].          8225 1451   46
    Integral experimental data for U-235 neutron fission spectrum 8225 1451   47
[14,15] and Cf-252 spontaneous fission neutron spectrum [16,17]   8225 1451   48
was used for testing evaluated Pb-204(n,n')Pb-204m excitation fun-8225 1451   49
ction. Data for U-235 thermal fission neutron spectrum and Cf-252 8225 1451   50
spontaneous fission neutron spectrum were taken from ref.[18] and 8225 1451   51
[19],  respectively.  The  results  of  testing are given in  the 8225 1451   52
table 1.                                                          8225 1451   53
                                                     Table 1.     8225 1451   54
 ---------------------------------------------------------------  8225 1451   55
    TYPE OF SPECTRUM   I <CS>,MB (calc.) I   <CS>, MB (measured)  8225 1451   56
 ----------------------I-----------------I----------------------  8225 1451   57
                       I                 I                        8225 1451   58
 U-235 neutron fission I   17.770        I 18.900 +- 2.000 [14]   8225 1451   59
                       I                 I 19.010 +- 1.536 [15]   8225 1451   60
                       I                 I                        8225 1451   61
 ----------------------I-----------------I----------------------  8225 1451   62
                       I                 I                        8225 1451   63
 CF-252 spont. fission I   20.373        I 20.900 +- 1.202 [16]   8225 1451   64
                       I                 I 20.850 +- 0.920 [17]   8225 1451   65
 ---------------------------------------------------------------  8225 1451   66
                                                                  8225 1451   67
                    ----- MF=33 MT=71 -----                       8225 1451   68
    Uncertainties in  the evaluated excitation function  for the  8225 1451   69
reaction  Pb-204(n,n')Pb-204m  are given  in the form of relative 8225 1451   70
covariance matrix for the 32-neutron energy groups (LB=5).  Cova- 8225 1451   71
riance matrix of uncertainties was calculated simultaneously with 8225 1451   72
recommended cross section data by means of PADE-2 code.           8225 1451   73
    Eigenvalues  of the  6-th digits  relative covariance matrix  8225 1451   74
given in the 33-file are the following:                           8225 1451   75
    2.56972E-09    3.22598E-09    3.49414E-09    4.00985E-09      8225 1451   76
    4.91484E-09    5.78671E-09    6.70005E-09    8.71427E-09      8225 1451   77
    1.03160E-08    1.33154E-08    1.55381E-08    2.07583E-08      8225 1451   78
    2.40281E-08    3.05913E-08    4.05801E-08    4.76532E-08      8225 1451   79
    5.93691E-08    9.33863E-08    1.58183E-07    2.72581E-06      8225 1451   80
    1.76176E-04    7.87730E-04    1.22783E-03    2.11803E-03      8225 1451   81
    3.22408E-03    4.16999E-03    4.89344E-03    1.08231E-02      8225 1451   82
    2.01870E-02    3.34051E-02    7.41942E-02                     8225 1451   83
                                                                  8225 1451   84
References :                                                      8225 1451   85
 1. R.B.Firestone   Table of Isotopes, Eighth edition, Vol. 1,    8225 1451   86
    John Wiley & Sons, Inc., New York, 1995                       8225 1451   87
 2. P.Bornemisza-Pauspertl, J.Karolyi, G.Peto Atomki Kozl., v.10, 8225 1451   88
    no.2, p.112, July 1968                                        8225 1451   89
 3. J.Csikai, G.Peto  Acta Phys. Hung., v.23, p.87, May 1967      8225 1451   90
 4. A.K.Hankla, R.W.Fink, J.H.Hamilton  Nucl. Phys., v.A180,      8225 1451   91
    p.157, January 1972                                           8225 1451   92
 5. G.N.Maslov, F.Nasyrov, N.F.Pashkin Yadernye Konstanty, v.9,   8225 1451   93
    p.50, Obninsk, 1972                                           8225 1451   94
 6. P.Decowski et al.  Nucl. Phys., v.A204, p.121, April 1973     8225 1451   95
 7. D.L.Smith, J.W.Meadows  Report ANL-NDM-37, December 1977      8225 1451   96
 8. T.B.Ryves, P.Kolkowski, A.C.Hooley  Annals Nucl. Energy,      8225 1451   97
    v.17, p.107, 1990                                             8225 1451   98
 9. I.Kimura, K.Kobayashi  Nucl. Sci. Eng., v.106, p.332, 1990    8225 1451   99
10. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear    8225 1451  100
    Model Code for Calculation of Cross Section and Emission      8225 1451  101
    Spectra. Report LA-6947, Los Alamos, 1977                     8225 1451  102
11. E.L.Trykov, G.Ya.Tertychnyi  Private communication, IPPE,     8225 1451  103
    Obninsk, May 1999                                             8225 1451  104
12. S.Badikov,N.Rabotnov,K.Zolotarev Proc. of NEANSC Specialist's 8225 1451  105
    Meeting on Evaluation and Processing of Covariance Data, Oak  8225 1451  106
    Ridge , USA, 7-9 September 1992, OECD, Paris, 1993, p.105     8225 1451  107
13. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          8225 1451  108
14. I.Kimura, K.Kobayashi, T.Shibata  Nucl. Sci. Technol., v.8,   8225 1451  109
    p.59, February 1971                                           8225 1451  110
15. A.K.Brodskaja et al.  Jadernyje Konstanty, no.23, v.4,        8225 1451  111
    October 1976                                                  8225 1451  112
16. J.Csikai, Z.Dezso  Proc. Educational Seminar on the use of    8225 1451  113
    Cf-252, Karlsruhe, 14-18 April 1975, p.29                     8225 1451  114
17. K.Kobayashi et al.  Report KURRI-AR-17, p.15, 1984  ;         8225 1451  115
    K.Kobayashi et al.  Progress Report NEANDC(J)-106/U, p.41,    8225 1451  116
    September 1984                                                8225 1451  117
18. L.W.Weston et al. Evaluated Neutron Data File for U-235,      8225 1451  118
    ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989    8225 1451  119
19. W.Mannhart  Report IAEA-TECDOC-410, IAEA, Vienna, 1987, p158  8225 1451  120
***************************************************************** 8225 1451  121
 File 2 added to the pointwise file containing only the effective 8225 1451  122
 scattering radius with no resonance parameters given.            8225 1451  123
 Taken from JENDL-3.2                                             8225 1451  124
                                                                  8225 1451  125
***************************************************************** 8225 1451  126
 ***************** Program LINEAR (VERSION 2002-1) ***************8225 1451  127
 For All Data Greater than 1.0000E-10 barns in Absolute Value     8225 1451  128
 Data Linearized to Within an Accuracy of .100000000 per-cent     8225 1451  129
 ***************** Program SIGMA1 (VERSION 2002-1) ***************8225 1451  130
 Data Doppler Broadened to 300.000000 Kelvin                      8225 1451  131
 for All Data Greater than 1.0000E-10 barns in Absolute Value     8225 1451  132
 Data Linearized to Within an Accuracy pf .100000000 per-cent     8225 1451  133
 ***************** Program FIXUP (Version 2002-1) ****************8225 1451  134
 Corrected ZA/AWR in All Sections-----------------------------Yes 8225 1451  135
 Corrected Thresholds-----------------------------------------Yes 8225 1451  136
 Extended Cross Sections to 20 MeV----------------------------No  8225 1451  137
 Allow Cross Section Deletion---------------------------------No  8225 1451  138
 Allow Cross Section Reconstruction---------------------------No  8225 1451  139
 Make All Cross Sections Non-Negative-------------------------Yes 8225 1451  140
 Delete Energies Not in Ascending Order-----------------------Yes 8225 1451  141
 Deleted Duplicate Points-------------------------------------Yes 8225 1451  142
 Check for Ascending MAT/MF/MT Order--------------------------Yes 8225 1451  143
 Check for Legal MF/MT Numbers--------------------------------Yes 8225 1451  144
 Allow Creation of Missing Sections---------------------------No  8225 1451  145
 Allow Insertion of Energy Points-----------------------------No  8225 1451  146
 Create Uniform Energy Grid-----------------------------------No  8225 1451  147
 Delete Section if Cross Section =0 at All Energies-----------Yes 8225 1451  148
 ***************** Program GROUPIE (VERSION 2002-1) **************8225 1451  149
 Unshielded Group Averages Using  640 Groups                      8225 1451  150
 Weighting Spectrum: Flat (Constant) Spectrum                     8225 1451  151
                                1        451        156          18225 1451  152
                                2        151          4          18225 1451  153
                                8          4          2          18225 1451  154
                               10          4         63          18225 1451  155
                               40          4         98          18225 1451  156
                                                                  8225 1  099999
                                                                  8225 0  0    0
 8.22040E+4 2.02221E+2          0          0          1          08225 2151    1
 8.22040+ 4 1.00000+ 0          0          0          1          08225 2151    2
 1.00000- 5 5.00000+ 4          0          0          0          08225 2151    3
 0.00000+ 0 8.50000- 1          0          0          0          08225 2151    4
                                                                  8225 2  099999
                                                                  8225 0  0    0
 8.22040E+4 2.02220E+2          0          0          1          18225 8  4    1
 8.22040E+4 0.000000+0         10          0          0          08225 8  4    2
                                                                  8225 8  099999
                                                                  8225 0  0    0
 8.22040E+4 2.02220E+2          0          0          1          0822510  4    1
 0.0       -2.18579E+6      82204          0          1        180822510  4    2
        180          1                                            822510  4    3
 2100000.00 1.34936E-8 2200000.00 3.51923E-5 2300000.00 .000189196822510  4    4
 2400000.00 .001283871 2500000.00 .004581835 2600000.00 .008006575822510  4    5
 2700000.00 .011515626 2800000.00 .015279183 2900000.00 .019236602822510  4    6
 3000000.00 .023323413 3100000.00 .027458638 3200000.00 .031593863822510  4    7
 3300000.00 .035729088 3400000.00 .039819900 3500000.00 .043866300822510  4    8
 3600000.00 .047857600 3700000.00 .051793800 3800000.00 .055666950822510  4    9
 3900000.00 .059477050 4000000.00 .063287150 4100000.00 .067032108822510  4   10
 4200000.00 .070711925 4300000.00 .074391742 4400000.00 .078071558822510  4   11
 4500000.00 .081751375 4600000.00 .085431192 4700000.00 .089118290822510  4   12
 4800000.00 .092812670 4900000.00 .096507050 5000000.00 .100201430822510  4   13
 5100000.00 .103895810 5200000.00 .107668750 5300000.00 .111520250822510  4   14
 5400000.00 .115371750 5500000.00 .119223250 5600000.00 .123175167822510  4   15
 5700000.00 .127227500 5800000.00 .131279833 5900000.00 .135442167822510  4   16
 6000000.00 .139714500 6100000.00 .143986833 6200000.00 .148383667822510  4   17
 6300000.00 .152905000 6400000.00 .157426333 6500000.00 .162078000822510  4   18
 6600000.00 .166860000 6700000.00 .171642000 6800000.00 .176562375822510  4   19
 6900000.00 .181621125 7000000.00 .186679875 7100000.00 .191738625822510  4   20
 7200000.00 .196883429 7300000.00 .202114286 7400000.00 .207345143822510  4   21
 7500000.00 .212576000 7600000.00 .217806857 7700000.00 .223037714822510  4   22
 7800000.00 .228268571 7900000.00 .233326500 8000000.00 .238211500822510  4   23
 8100000.00 .243096500 8200000.00 .247725500 8300000.00 .252098500822510  4   24
 8400000.00 .256166250 8500000.00 .259928750 8600000.00 .263295750822510  4   25
 8700000.00 .266267250 8800000.00 .268757750 8900000.00 .270767250822510  4   26
 9000000.00 .272370000 9100000.00 .273276000 9200000.00 .273592000822510  4   27
 9300000.00 .273302000 9400000.00 .272398000 9500000.00 .270881000822510  4   28
 9600000.00 .268761000 9700000.00 .266057500 9800000.00 .262672250822510  4   29
 9900000.00 .258890750 10000000.0 .254652250 10100000.0 .249956750822510  4   30
 10200000.0 .244904750 10300000.0 .239496250 10400000.0 .233798500822510  4   31
 10500000.0 .227811500 10600000.0 .221824500 10700000.0 .215712667822510  4   32
 10800000.0 .209476000 10900000.0 .203239333 11000000.0 .197002667822510  4   33
 11100000.0 .190766000 11200000.0 .184529333 11300000.0 .178482167822510  4   34
 11400000.0 .172624500 11500000.0 .166766833 11600000.0 .161108750822510  4   35
 11700000.0 .155650250 11800000.0 .150372000 11900000.0 .145274000822510  4   36
 12000000.0 .140363250 12100000.0 .135639750 12200000.0 .131102750822510  4   37
 12300000.0 .126752250 12400000.0 .122582250 12500000.0 .118592750822510  4   38
 12600000.0 .114774500 12700000.0 .111127500 12800000.0 .107640500822510  4   39
 12900000.0 .104313500 13000000.0 .101134025 13100000.0 .098102075822510  4   40
 13200000.0 .095205225 13300000.0 .092443475 13400000.0 .089804450822510  4   41
 13500000.0 .087288150 13600000.0 .084882850 13700000.0 .082588550822510  4   42
 13800000.0 .080394125 13900000.0 .078299575 14000000.0 .076294725822510  4   43
 14100000.0 .074379575 14200000.0 .072544700 14300000.0 .070790100822510  4   44
 14400000.0 .069123583 14500000.0 .067545150 14600000.0 .065966717822510  4   45
 14700000.0 .064479067 14800000.0 .063082200 14900000.0 .061685333822510  4   46
 15000000.0 .060364750 15100000.0 .059120450 15200000.0 .057876150822510  4   47
 15300000.0 .056695800 15400000.0 .055579400 15500000.0 .054463000822510  4   48
 15600000.0 .053400017 15700000.0 .052390450 15800000.0 .051380883822510  4   49
 15900000.0 .050415850 16000000.0 .049495350 16100000.0 .048574850822510  4   50
 16200000.0 .047696513 16300000.0 .046860338 16400000.0 .046024163822510  4   51
 16500000.0 .045187988 16600000.0 .044389788 16700000.0 .043629563822510  4   52
 16800000.0 .042869338 16900000.0 .042109113 17000000.0 .041380440822510  4   53
 17100000.0 .040683320 17200000.0 .039986200 17300000.0 .039289080822510  4   54
 17400000.0 .038591960 17500000.0 .037920742 17600000.0 .037275425822510  4   55
 17700000.0 .036630108 17800000.0 .035984792 17900000.0 .035339475822510  4   56
 18000000.0 .034694158 18100000.0 .034066842 18200000.0 .033457525822510  4   57
 18300000.0 .032848208 18400000.0 .032238892 18500000.0 .031629575822510  4   58
 18600000.0 .031020258 18700000.0 .030410942 18800000.0 .029801625822510  4   59
 18900000.0 .029192308 19000000.0 .028582992 19100000.0 .027973675822510  4   60
 19200000.0 .027364358 19300000.0 .026751850 19400000.0 .026136150822510  4   61
 19500000.0 .025520450 19600000.0 .024904750 19700000.0 .024289050822510  4   62
 19800000.0 .023673350 19900000.0 .023057650 20000000.0 0.0       822510  4   63
                                                                  822510  099999
                                                                  8225 0  0    0
 8.22040E+4 2.02220E+2          0          0          1          0822540  4    1
 0.000000+0-2.185790+6          0          0          0          1822540  4    2
 1.000000+1 0.000000+0          0          4          0          1822540  4    3
 0.000000+0 0.000000+0          1          5        561         33822540  4    4
 1.000000-5 2.100000+6 2.500000+6 3.000000+6 3.500000+6 4.000000+6822540  4    5
 4.500000+6 5.000000+6 5.500000+6 6.000000+6 6.500000+6 7.000000+6822540  4    6
 7.500000+6 8.000000+6 8.500000+6 9.000000+6 9.500000+6 1.000000+7822540  4    7
 1.050000+7 1.100000+7 1.150000+7 1.200000+7 1.250000+7 1.300000+7822540  4    8
 1.350000+7 1.400000+7 1.450000+7 1.500000+7 1.600000+7 1.700000+7822540  4    9
 1.800000+7 1.900000+7 2.000000+7 0.000000+0 0.000000+0 0.000000+0822540  4   10
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0822540  4   11
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0822540  4   12
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0822540  4   13
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0822540  4   14
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 6.053160-3822540  4   15
 4.115730-3 3.116670-3 2.961290-3 3.015440-3 3.068430-3 3.122180-3822540  4   16
 3.191450-3 3.270380-3 3.330530-3 3.323760-3 3.189580-3 2.873690-3822540  4   17
 2.362520-3 1.719920-3 1.085450-3 6.067590-4 3.537590-4 2.953430-4822540  4   18
 3.452160-4 4.185990-4 4.610410-4 4.510900-4 3.914730-4 2.986660-4822540  4   19
 1.946180-4 7.102620-5 3.340260-5 2.090940-4 5.777680-4 9.758000-4822540  4   20
 3.652730-3 3.188180-3 2.741690-3 2.500020-3 2.391720-3 2.370940-3822540  4   21
 2.404200-3 2.459540-3 2.501280-3 2.488020-3 2.375450-3 2.128100-3822540  4   22
 1.741980-3 1.267890-3 8.067540-4 4.607600-4 2.752690-4 2.260360-4822540  4   23
 2.528310-4 2.982150-4 3.260610-4 3.223460-4 2.886880-4 2.352530-4822540  4   24
 1.753850-4 1.054310-4 8.819490-5 1.980940-4 4.282670-4 7.023930-4822540  4   25
 4.090330-3 3.809350-3 3.084810-3 2.409280-3 1.945010-3 1.713110-3822540  4   26
 1.675720-3 1.764700-3 1.891470-3 1.955560-3 1.864770-3 1.574250-3822540  4   27
 1.129950-3 6.693000-4 3.455270-4 2.288620-4 2.783260-4 3.939740-4822540  4   28
 4.826620-4 4.913870-4 4.094080-4 2.562070-4 6.726690-5-1.174300-4822540  4   29
-2.960370-4-2.652780-4 1.334280-4 7.404230-4 9.977190-4 4.192280-3822540  4   30
 3.615200-3 2.756360-3 2.026880-3 1.585040-3 1.448570-3 1.554920-3822540  4   31
 1.788280-3 1.997760-3 2.028940-3 1.784090-3 1.295080-3 7.395430-4822540  4   32
 3.407490-4 2.168620-4 3.235160-4 5.202110-4 6.678800-4 6.838410-4822540  4   33
 5.497210-4 2.955960-4-2.127310-5-3.347490-4-6.455630-4-6.120310-4822540  4   34
 4.206840-5 1.036910-3 1.369200-3 3.337220-3 2.715200-3 2.122560-3822540  4   35
 1.728440-3 1.573850-3 1.622850-3 1.787280-3 1.942730-3 1.955000-3822540  4   36
 1.731610-3 1.287780-3 7.683660-4 3.690520-4 2.055300-4 2.548860-4822540  4   37
 4.047030-4 5.353800-4 5.700850-4 4.849860-4 2.980360-4 5.201480-5822540  4   38
-2.007100-4-4.671060-4-4.766410-4 1.753560-5 8.191410-4 1.160780-3822540  4   39
 2.441450-3 2.138780-3 1.913630-3 1.799600-3 1.783420-3 1.818670-3822540  4   40
 1.835170-3 1.754800-3 1.523250-3 1.151680-3 7.327830-4 3.941010-4822540  4   41
 2.161850-4 1.927320-4 2.578620-4 3.363690-4 3.757390-4 3.541240-4822540  4   42
 2.748900-4 1.572480-4 2.758470-5-1.228700-4-1.583610-4 7.210250-5822540  4   43
 5.022620-4 7.992990-4 2.109570-3 2.066140-3 2.021340-3 1.971810-3822540  4   44
 1.901400-3 1.785200-3 1.597680-3 1.328150-3 9.989460-4 6.686560-4822540  4   45
 4.053520-4 2.473360-4 1.879950-4 1.923760-4 2.219010-4 2.487100-4822540  4   46
 2.586200-4 2.484210-4 2.218820-4 1.863140-4 1.365060-4 1.095370-4822540  4   47
 1.667880-4 3.241550-4 5.620980-4 2.162730-3 2.194410-3 2.155060-3822540  4   48
 2.038730-3 1.841680-3 1.568570-3 1.241280-3 9.033450-4 6.092850-4822540  4   49
 3.991440-4 2.794760-4 2.286070-4 2.165530-4 2.199510-4 2.258760-4822540  4   50
 2.293520-4 2.297220-4 2.280340-4 2.256590-4 2.235460-4 2.278300-4822540  4   51
 2.511290-4 3.214710-4 5.141590-4 2.294750-3 2.304690-3 2.209580-3822540  4   52
 2.000860-3 1.685430-3 1.297840-3 9.040340-4 5.809970-4 3.773200-4822540  4   53
 2.890450-4 2.741090-4 2.853540-4 2.918090-4 2.816490-4 2.560570-4822540  4   54
 2.222490-4 1.886790-4 1.625550-4 1.497200-4 1.850350-4 2.819620-4822540  4   55
 4.279470-4 6.049040-4 2.388890-3 2.371990-3 2.220610-3 1.918710-3822540  4   56
 1.490500-3 1.015220-3 6.062410-4 3.509160-4 2.609900-4 2.810290-4822540  4   57
 3.363160-4 3.716400-4 3.626150-4 3.095780-4 2.269990-4 1.346430-4822540  4   58
 5.186300-5-1.528340-5 2.768240-5 2.366830-4 5.416980-4 7.380010-4822540  4   59
 2.467190-3 2.428130-3 2.199940-3 1.775320-3 1.228460-3 7.049070-4822540  4   60
 3.457620-4 2.030410-4 2.266640-4 3.197410-4 3.976080-4 4.138000-4822540  4   61
 3.586830-4 2.474170-4 1.074840-4-3.066840-5-1.670910-4-1.540770-4822540  4   62
 1.281860-4 5.757270-4 8.242120-4 2.528710-3 2.427200-3 2.072030-3822540  4   63
 1.508680-3 8.913110-4 4.070610-4 1.622030-4 1.370690-4 2.335570-4822540  4   64
 3.469890-4 4.076110-4 3.881820-4 2.944740-4 1.518610-4-6.200680-6822540  4   65
-1.906720-4-2.405740-4 2.059410-5 5.092830-4 8.361200-4 2.481690-3822540  4   66
 2.270140-3 1.789640-3 1.165110-3 5.959140-4 2.350450-4 1.130070-4822540  4   67
 1.604110-4 2.761000-4 3.777720-4 4.198440-4 3.906200-4 3.019850-4822540  4   68
 1.787130-4-1.924600-7-1.140470-4 3.356710-5 4.377700-4 8.644110-4822540  4   69
 2.257900-3 1.980930-3 1.497860-3 9.664880-4 5.494970-4 3.256820-4822540  4   70
 2.785150-4 3.407000-4 4.403740-4 5.251840-4 5.676180-4 5.611320-4822540  4   71
 5.135370-4 4.034660-4 2.809920-4 3.093840-4 5.829890-4 1.137240-3822540  4   72
 2.000580-3 1.826280-3 1.520870-3 1.195250-3 9.411980-4 7.950340-4822540  4   73
 7.457830-4 7.605310-4 8.046270-4 8.515680-4 8.855910-4 9.006540-4822540  4   74
 8.918920-4 8.697480-4 9.247820-4 1.198590-3 1.930540-3 2.069600-3822540  4   75
 2.170730-3 2.127140-3 1.982240-3 1.792810-3 1.603980-3 1.442320-3822540  4   76
 1.319490-3 1.238160-3 1.196730-3 1.192270-3 1.252010-3 1.444090-3822540  4   77
 1.791820-3 2.368020-3 3.354430-3 2.757910-3 3.136490-3 3.244060-3822540  4   78
 3.107020-3 2.801640-3 2.414680-3 2.021720-3 1.679890-3 1.427830-3822540  4   79
 1.288530-3 1.324970-3 1.778140-3 2.659800-3 3.857740-3 5.178410-3822540  4   80
 3.951380-3 4.381340-3 4.382000-3 4.025400-3 3.439110-3 2.759100-3822540  4   81
 2.104450-3 1.567490-3 1.212250-3 1.125220-3 1.782580-3 3.259190-3822540  4   82
 5.214970-3 6.909040-3 5.098540-3 5.270890-3 4.939470-3 4.244030-3822540  4   83
 3.358470-3 2.449770-3 1.657290-3 1.085100-3 8.215140-4 1.550350-3822540  4   84
 3.460510-3 6.039040-3 8.070540-3 5.590640-3 5.343050-3 4.654550-3822540  4   85
 3.706320-3 2.684930-3 1.754210-3 1.042510-3 6.194140-4 1.274620-3822540  4   86
 3.314340-3 6.172660-3 8.424730-3 5.207660-3 4.630850-3 3.773000-3822540  4   87
 2.808770-3 1.897690-3 1.169280-3 6.629810-4 1.141720-3 2.986270-3822540  4   88
 5.708020-3 8.000890-3 4.237350-3 3.594190-3 2.838430-3 2.099130-3822540  4   89
 1.484160-3 1.003900-3 1.272530-3 2.672740-3 4.889680-3 7.008540-3822540  4   90
 3.241590-3 2.798940-3 2.346960-3 1.954760-3 1.616460-3 1.713150-3822540  4   91
 2.545590-3 4.012270-3 5.735180-3 2.716800-3 2.616640-3 2.520100-3822540  4   92
 2.426860-3 2.449610-3 2.727590-3 3.350830-3 4.472360-3 2.879730-3822540  4   93
 3.109940-3 3.340090-3 3.428280-3 3.287320-3 3.123280-3 3.473200-3822540  4   94
 3.658080-3 4.259390-3 4.573780-3 4.243340-3 3.475180-3 2.932480-3822540  4   95
 5.424620-3 6.383490-3 6.350240-3 5.263230-3 3.318230-3 8.625060-3822540  4   96
 1.000150-2 9.656750-3 6.041350-3 1.365320-2 1.538780-2 1.111050-2822540  4   97
 1.989260-2 1.732600-2 2.174600-2                                 822540  4   98
                                                                  822540  099999
                                                                  8225 0  0    0
                                                                     0 0  0    0
 9.02320E+4 2.30044E+2          0          1         34         109040 1451    1
 0.0        1.00000E+0          0          0          0          69040 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20029040 1451    3
 3.00000E+2 0.0                 1          0        208          69040 1451    4
 90-Th-232 BNL,ANL+   EVAL-DEC77 BHAT,SMITH,LEONARD,DESAUSSURE+   9040 1451    5
                      DIST-Feb2004                                9040 1451    6
----IRDF-2002         MATERIAL 9040                               9040 1451    7
-----INCIDENT NEUTRON DATA                                        9040 1451    8
------ENDF-6 FORMAT                                               9040 1451    9
******************************************************************9040 1451   10
 90-TH-232 BNL,ANL+   EVAL-DEC77 BHAT,SMITH,LEONARD,DESAUSSURE+   9040 1451   11
                      DIST-FEB90                       19900205   9040 1451   12
----ENDF/B-VI         MATERIAL 9040                               9040 1451   13
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************9040 1451   14
DOSIMETRY                                                         9040 1451   15
******************************************************************9040 1451   16
 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC             9040 1451   17
 *         *          *          *          *          *         *9040 1451   18
                                                                  9040 1451   19
 PRINCIPAL EVALUATORS- J.W.MEADOWS,W.P.POENITZ,A.B.SMITH,D.L.SMITH9040 1451   20
                       AND J.F.WHALEN(ANL)                        9040 1451   21
                       R.J.HOWERTON(LLL)                          9040 1451   22
                       B.R.LEONARD ET.AL.(BNW)                    9040 1451   23
                       G.DE SAUSSURE,R.L.MACKLIN AND R.GWIN(ORNL) 9040 1451   24
                       D.K. OLSEN (ORNL)                          9040 1451   25
 THIS EVALUATION ASSEMBLED BY M.R.BHAT(BNL) USING THE FOLLOWING   9040 1451   26
 EVALUATIONS                                                      9040 1451   27
                                                                  9040 1451   28
      NU-BAR(PROMPT) - R.GWIN(ORNL)(REF 4)                        9040 1451   29
      DELAYED NEUTRONS -M.BRADY AND T.ENGLAND (REF 5)             9040 1451   30
      ENERGY RELEASE IN FISSION - R.SHER ET.AL.(STANFORD)(REF 6)  9040 1451   31
      THERMAL RANGE - B.R.LEONARD JR.ET.AL.(REF 2) WITH CHANGES BY9040 1451   32
                      M.R.BHAT(REF 31)                            9040 1451   33
      RESOLVED RESONANCE REGION - D.K. OLSEN (REF 37)             9040 1451   34
                                                                  9040 1451   35
      UNRESOLVED RESONANCE REGION - G.DE SAUSSURE AND R.L.MACKLIN 9040 1451   36
                       (REF 3)WITH CHANGES BY M.R.BHAT(REF 31)    9040 1451   37
      SMOOTH CROSS-SECTIONS 50KEV TO 20MEV -                      9040 1451   38
      TOTAL - A.B.SMITH(ANL)(REF1)                                9040 1451   39
      FISSION - W.P.POENITZ(ANL)(REF1)                            9040 1451   40
      CAPTURE - W.P.POENITZ(ANL)(REF1)                            9040 1451   41
      INELASTIC AND OTHER CROSS-SECTIONS - J.W.MEADOWS ET.AL.(ANL)9040 1451   42
                                                            (REF1)9040 1451   43
      FISSION NEUTRON SPECTRUM - M.R.BHAT(BNL) (REF 31)           9040 1451   44
      GAMMA-RAY PRODUCTION - R.J.HOWERTON(LLL)                    9040 1451   45
                                                                  9040 1451   46
                             MF = 1                               9040 1451   47
                                                                  9040 1451   48
 MT=452(NU-BAR TOTAL) CONSISTENT WITH MT=455 AND MT=456           9040 1451   49
 MT=455(DELAYED NEUTRON YIELDS) (REF 5)                           9040 1451   50
 MT=456(PROMPT NU-BAR) BASED ON CF-252 NU-BAR(PROMPT)=3.757       9040 1451   51
      EVALUATION BY GWIN(ORNL) BASED ON A STRAIGHT LINE LEAST-    9040 1451   52
      SQUARES FIT TO THE AVAILABLE DATA LISTED IN REF.4.          9040 1451   53
 MT=458(ENERGY RELEASE IN FISSION)EVALUATION BY R.SHER ET.AL(STAN-9040 1451   54
      FORD)(REF 6)                                                9040 1451   55
                                                                  9040 1451   56
                             MF = 2                               9040 1451   57
                                                                  9040 1451   58
 RESOLVED RESONANCE REGION - D.K. OLSEN (REF 37) RESONANCE        9040 1451   59
      PARAMETERS ARE UNCERTAINTY WEIGHTED AVERAGE OF AVAILABLE    9040 1451   60
      DATA AND THE TWO BOUND RESONANCES OF REF 2 WITH MF=3 FILES  9040 1451   61
      FOR TRUNCATION, MISSED P-WAVES, 1/V CAPTURE, AND SMOOTH     9040 1451   62
      CONNECTION TO THE END OF THE THERMAL REGION CROSS SECTIONS  9040 1451   63
      AT 5 EV. AVERAGE CAPTURE WIDTH = 2.44 X 10-2 EV, S-WAVE     9040 1451   64
      STRENGTH FUNCTION = 0.826 X 10-4, P-WAVE STRENGTH FUNCTION  9040 1451   65
      ASSUMED = 1.6 X 10-4, 5 TO 4000 EV INFINITLY DILUTE CAPTURE 9040 1451   66
      RESONANCE INTEGRAL = 81.58 B.                               9040 1451   67
                                                                  9040 1451   68
 UNRESOLVED RESONANCE REGION - G.DE SAUSSURE AND R.L.MACKLIN(REF3)9040 1451   69
      EVALUATION OF CAPTURE CROSS-SECTION USED FROM 4 TO 25KEV.   9040 1451   70
      ABOVE 25KEV THIS WAS JOINED SMOOTHLY TO THE POENITZ EVALUAT-9040 1451   71
      ION FROM 40KEV TO 50KEV. THESE WERE THEN FITTED USING THE   9040 1451   72
      CODE UR(REF30) TO GIVE THE UNRESOLVED RESONANCE             9040 1451   73
      PARAMETERS. IN THIS FIT THE S- AND D-WAVE PARAMETERS WERE   9040 1451   74
      KEPT CONSTANT AT THE VALUES GIVEN BY DE SAUSSURE AND MACKLIN9040 1451   75
      THE P-WAVE GAMMA WIDTH WAS INCREASED TO 2.52E-02EV AND THE  9040 1451   76
      P-WAVE REDUCED NEUTRON WIDTH VARIED TO FIT THE CAPTURE      9040 1451   77
      CROSS-SECTION.                                              9040 1451   78
      THE CAPTURE CROSS-SECTION INPUT USED TO EXTRACT THE         9040 1451   79
      UNRESOLVED RESONANCE PARAMETERS IN FILE 2/151 ARE GIVEN HERE9040 1451   80
      FROM 4KEV TO 50KEV AT 1KEV INTERVAL. THESE ARE -            9040 1451   81
      1.130,0.982,0.908,0.850,0.803,0.764,0.730,0.702,0.677,0.655,9040 1451   82
      0.636,0.618,0.601,0.585,0.571,0.557,0.545,0.533,0.521,0.511,9040 1451   83
      0.500,0.491,0.482,0.473,0.465,0.459,0.452,0.448,0.443,0.439,9040 1451   84
      0.435,0.431,0.429,0.426,0.424,0.422,0.420,0.420,0.420,0.420,9040 1451   85
      0.417,0.414,0.411,0.407,0.401,0.395,0.390.                  9040 1451   86
                                                                  9040 1451   87
                             MF = 3                               9040 1451   88
                                                                  9040 1451   89
 THERMAL REGION(1.0E-05 TO 5.0EV) - MAINLY BASED ON LEONARD(REF 2)9040 1451   90
      EVALUATION WITH THE FOLLOWING CHANGES. THE CAPTURE CROSS-   9040 1451   91
      SECTION IN REF 2 NORMALISED TO 7.40B AT 2.53E-02 EV AND USED9040 1451   92
      FROM 1.0E-05EV TO 2.53E-02EV. FROM 2.6E-02EV TO 14EV THE FIT9040 1451   93
      TO THEIR CAPTURE DATA BY CHRIEN AND LIOU(REF 32) USED. THE  9040 1451   94
      SCATTERING CROSS-SECTION WAS CHANGED TO ACCOMMODATE CHANGES 9040 1451   95
      IN CAPTURE USING TOTAL SLIGHTLY MODIFIED FROM THAT GIVEN IN 9040 1451   96
      REF 2. THESE SMALL CHANGES ARE DESCRIBED IN REF 31.         9040 1451   97
      2.53E-02EV CROSS-SECTION   CAPTURE    7.4 B                 9040 1451   98
      DILUTE CAPTURE RESONANCE INTEGRAL    86.1 B                 9040 1451   99
      (0.5 TO 2.0E+07 EV)                                         9040 1451  100
 TOTAL CROSS-SECTION FROM 50KEV TO 20MEV - A.B.SMITH(ANL)(REF1)   9040 1451  101
      MAINLY BASED ON REF9-13 FROM 0.025 TO 1 MEV,FROM 1 TO 5MEV  9040 1451  102
      BASED ON REF 9-11,14-16.FROM 5 TO 15MEV EVALUATION BASED ON 9040 1451  103
      REF11,15,17.FROM 15 TO 20MEV EVALUATION BASED ON NUCLEAR    9040 1451  104
      MODEL CALCULATIONS DESCRIBED IN REF18 AND 19.TOTAL CROSS-   9040 1451  105
      SECTION MODIFIED BY ABOUT 3PER-CENT BETWEEN 50 TO 150KEV    9040 1451  106
      JOIN SMOOTHLY WITH THAT CALCULATED FROM THE UNRESOLVED      9040 1451  107
      RESONANCE PARAMETERS BELOW 50KEV.                           9040 1451  108
 ELASTIC SCATTERING CROSS-SECTION FROM 50KEV TO 20MEV OBTAINED AS 9040 1451  109
      THE DIFFERENCE BETWEEN TOTAL AND OTHER PARTIAL CROSSSECTIONS9040 1451  110
 FISSION CROSS-SECTION UP TO 20MEV - W.P.POENITZ(REF1) DETAILS OF 9040 1451  111
      THE EVALUATION AND THE DATA SETS USED ARE IN REF1.          9040 1451  112
      FISSION CROSS-SECTION CHANGED TO BE CONSISTENT WITH         9040 1451  113
      U-235(N,F) EVALUATION GIVEN IN REF 33                       9040 1451  114
 CAPTURE CROSS-SECTION 50KEV -20MEV - W.P.POENITZ. DETAILS OF THE 9040 1451  115
      EVALUATION AND THE DATA SETS USED ARE GIVEN IN REF1.        9040 1451  116
      CAPTURE CROSS-SECTION CHANGED TO BE CONSISTENT WITH         9040 1451  117
      U-235(N,F) EVALUATION GIVEN IN REF 33                       9040 1451  118
 INELASTIC SCATTERING CROSS-SECTIONS - J.W.MEADOWS ET.AL.(REF 1)  9040 1451  119
      EVALUATION BASED MAINLY ON THE DATA IN REF 20-25. INTER-    9040 1451  120
      POLATED BETWEEN EXPERIMENTAL DATA AND EXTRAPOLATED TO 20MEV 9040 1451  121
      USING COUPLED CHANNEL NUCLEAR MODEL CALCULATIONS OF REF26.  9040 1451  122
 (N,2N) AND (N,3N) CROSS-SECTIONS - J.W.MEADOWS ET.AL.(REF1)      9040 1451  123
      EXPERIMENTAL DATA USED(REF1) RENORMALISED TO A COMMON SET OF9040 1451  124
      STANDARDS BEFORE EVALUATION.                                9040 1451  125
                                                                  9040 1451  126
                              MF = 33                             9040 1451  127
  MT = 18,102 BASED ON ERROR ESTIMATES IN THESE CROSS SECTIONS IN 9040 1451  128
  REF. 32,1                                                       9040 1451  129
                                                                  9040 1451  130
                       PRINCIPAL REFERENCES                       9040 1451  131
                                                                  9040 1451  132
 1 J.W.MEADOWS,W.P.POENITZ,A.B.SMITH,D.L.SMITH,J.F.WHALEN AND     9040 1451  133
   R.J.HOWERTON ANL/NDM-35(FEB.1978)                              9040 1451  134
 2 D.F.NEWMAN,B.R.LEONARD JR.ET.AL. EPRI NP-222,MAY1977           9040 1451  135
 3 G.DE SAUSSURE AND R.L.MACKLIN ORNL/TM-6161(ENDF-255)DEC.1977   9040 1451  136
 4 R.GWIN ORNL/TM-6245(ENDF-262)MAY1978.                          9040 1451  137
 5 M.C.BRADY AND T.R.ENGLAND NSE 103,129(1989)                    9040 1451  138
   **DATA INSERTED INTO FILE AT BNL**                             9040 1451  139
 6. R.SHER + C.BECK EPRI 1771/81 + REV. 1/83 + PC TO MAGURNO 2/83 9040 1451  140
 7 S.F.MUGHABGHAB AND D.I.GARBER,BNL-325(3RD EDN)1973             9040 1451  141
 8 H.DERRIEN,NEANDC(E)163U(1975)                                  9040 1451  142
 9 J.F.WHALEN AND A.B.SMITH,NUC.SCI.AND ENG.67,129(1978)          9040 1451  143
 10J.MEADOWS,A.SMITH AND J.WHALEN,PRIV.COMM.1977                  9040 1451  144
 11U.FASOLI ET.AL.NUCL.PHYS.A151,369(1970)                        9040 1451  145
 12M.DIVADEENAM ET.AL. DISS.ABS.28,3834(1968)                     9040 1451  146
 13C.UTTLEY ET.AL.66PARIS,1,165,1966                              9040 1451  147
 14L.GREEN ET.AL.PROC.CONF.ON NUCL.CROSS-SECTIONS AND TECHNOLOGY, 9040 1451  148
                                 KNOXVILLE,1,325(1971)            9040 1451  149
 15D.FOSTER ET.AL.PRIV.COMM(1967)                                 9040 1451  150
 16R.BATCHELOR ET.AL.NUCL.PHYS.65,236(1956)                       9040 1451  151
 17J.COON ET.AL.PHYS.REV.88,562(1952)                             9040 1451  152
 18P.GUENTHER ET.AL.ACCEPTED FOR PUBLICATION NUC.SCI.AND ENG.(19779040 1451  153
 19C.PHILIS ET.AL. ANL/NDM-28(1977)                               9040 1451  154
 20A.SMITH PHYS.REV.126,718(1962)                                 9040 1451  155
 21W.MCMURRAY ET.AL.SOUTHERN UNIV.NUCLEAR INST.REPORT,SUNI-41(19759040 1451  156
 22J.HAOUAT ETAL.PROC.INER.CONF.ON INTERACTIONS OF NEUTRONS WITH  9040 1451  157
                                 NUCLEI,CONF-760715(1976)         9040 1451  158
 23R.BATCHELOR AND J.TOWLE,NUCL.PHYS.65,236(1965)                 9040 1451  159
 24R.BATCHELOR AND J.TOWLE,PROC.PHYS.SOC.73,193(1959)             9040 1451  160
 25A.SMITH,PRIV.COMM,1970 AND 1977                                9040 1451  161
 26A.SMITH ET.AL.ACCEPTED FOR PUBLICATION NUC.SCI.AND ENG.(1977)  9040 1451  162
 27M.SEGEV.ET.AL.TRANS.AM.NUCL.SOC,22,679(1975)AND PRIV.COMM(1976)9040 1451  163
 28R.J.HOWERTON AND R.J.DOYAS,NUCL.SCI AND ENG,46,414(1971)       9040 1451  164
 29YU.A.VASIL'EV ET.AL.PHYSICS OF NUCLEAR FISSION,N.A.PERFILOV AND9040 1451  165
   V.P.EISMONT(EDS),ISRAEL PROGRAM OF SCI.TRANS.JERUSALEM(1964)   9040 1451  166
 30E.M.PENNINGTON,PRIVATE COMMUNICATION(1973)                     9040 1451  167
 31M.R.BHAT,ENDF-268(TO BE PUBLISHED)                             9040 1451  168
 32R.E.CHRIEN AND H.LIOU(1978) TO BE PUBLISHED                    9040 1451  169
 33W.P.POENITZ,ANL/NDM-45(1978) TO BE PUBLISHED                   9040 1451  170
 34R.W.PEELE AND F.C.MAIENSCHEIN, NUCL.SCI.ENG. 40, 485 (1970)    9040 1451  171
 35R.J. HOWERTON, D.E. CULLEN, R.C. HAIGHT, M.H. MACGREGOR, S.T.  9040 1451  172
   PERKINS, AND E.F. PLECHARTY, "THE LLL EVALUATED NUCLEAR DATA   9040 1451  173
   LIBRARY (ENDL): EVALUATION TECHNIQUES, REACTION INDEX, AND     9040 1451  174
   DESCRIPTIONS OF INDIVIDUAL EVALUATIONS," UCRL-50400, VOL. 15,  9040 1451  175
   PART A, LAWERENCE LIVERMORE LABORATORY (1975).                 9040 1451  176
 36S.T.PERKINS,R.C.HAIGHT AND R.J.HOWERTON,NUCL.SCI.ENG.57,1(1975)9040 1451  177
 37D.K.OLSEN, ORNL/TM-8056(1982), ENDF-319.                       9040 1451  178
******************************************************************9040 1451  179
                                                                  9040 1451  180
                                                                  9040 1451  181
                                                                  9040 1451  182
                                                                  9040 1451  183
******************************************************************9040 1451  184
 ***************** Program LINEAR (VERSION 2002-1) ***************9040 1451  185
 For All Data Greater than 1.0000E-10 barns in Absolute Value     9040 1451  186
 Data Linearized to Within an Accuracy of .100000000 per-cent     9040 1451  187
 ***************** Program RECENT (VERSION 2002-1) ***************9040 1451  188
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9040 1451  189
 Data Linearized to within an Accuracy of .100000000 per-cent     9040 1451  190
 ***************** Program SIGMA1 (VERSION 2002-1) ***************9040 1451  191
 Data Doppler Broadened to 300.000000 Kelvin                      9040 1451  192
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9040 1451  193
 Data Linearized to Within an Accuracy pf .100000000 per-cent     9040 1451  194
 ***************** Program FIXUP (Version 2002-1) ****************9040 1451  195
 Corrected ZA/AWR in All Sections-----------------------------Yes 9040 1451  196
 Corrected Thresholds-----------------------------------------Yes 9040 1451  197
 Extended Cross Sections to 20 MeV----------------------------No  9040 1451  198
 Allow Cross Section Deletion---------------------------------No  9040 1451  199
 Allow Cross Section Reconstruction---------------------------No  9040 1451  200
 Make All Cross Sections Non-Negative-------------------------Yes 9040 1451  201
 Delete Energies Not in Ascending Order-----------------------Yes 9040 1451  202
 Deleted Duplicate Points-------------------------------------Yes 9040 1451  203
 Check for Ascending MAT/MF/MT Order--------------------------Yes 9040 1451  204
 Check for Legal MF/MT Numbers--------------------------------Yes 9040 1451  205
 Allow Creation of Missing Sections---------------------------No  9040 1451  206
 Allow Insertion of Energy Points-----------------------------No  9040 1451  207
 Create Uniform Energy Grid-----------------------------------No  9040 1451  208
 Delete Section if Cross Section =0 at All Energies-----------Yes 9040 1451  209
 ***************** Program GROUPIE (VERSION 2002-1) **************9040 1451  210
 Unshielded Group Averages Using  640 Groups                      9040 1451  211
 Weighting Spectrum: Flat (Constant) Spectrum                     9040 1451  212
                                1        451        218          19040 1451  213
                                2        151          4          09040 1451  214
                                3         18         72          09040 1451  215
                                3        102        217          09040 1451  216
                               33         18          9          09040 1451  217
                               33        102          7          09040 1451  218
                                                                  9040 1  099999
                                                                  9040 0  0    0
 9.02320E+4 2.30045E+2          0          0          1          09040 2151    1
 9.02320E+4 1.00000E+0          0          0          1          09040 2151    2
 5.00000E+0 4.00000E+3          0          0          0          09040 2151    3
 0.0        9.72000E-1          0          0          0          09040 2151    4
                                                                  9040 2  099999
                                                                  9040 0  0    0
 9.02320E+4 2.30044E+2          0          0          0          09040 3 18    1
 1.88470E+8 1.88470E+8          0          0          1        2069040 3 18    2
        206          1                                            9040 3 18    3
 500000.000 1.37500E-6 525000.000 4.12499E-6 550000.000 6.87498E-69040 3 18    4
 575000.000 9.62500E-6 600000.000 1.44501E-5 630000.000 2.13500E-59040 3 18    5
 660000.000 2.82500E-5 690000.000 4.12173E-5 720000.000 8.03773E-59040 3 18    6
 760000.000 .000130050 800000.000 .000154600 840000.000 .0002595459040 3 18    7
 880000.000 .000567766 920000.000 .001115025 960000.000 .0011350869040 3 18    8
 1000000.00 .001805998 1100000.00 .003257634 1200000.00 .0100931179040 3 18    9
 1300000.00 .038089744 1400000.00 .064670533 1500000.00 .0994199279040 3 18   10
 1600000.00 .097810452 1700000.00 .084170147 1800000.00 .0952105919040 3 18   11
 1900000.00 .116499192 2000000.00 .118500645 2100000.00 .1289995989040 3 18   12
 2200000.00 .130499193 2300000.00 .117750737 2400000.00 .1157501309040 3 18   13
 2500000.00 .118800036 2600000.00 .122399807 2700000.00 .1254663819040 3 18   14
 2800000.00 .125333781 2900000.00 .129000649 3000000.00 .1374367209040 3 18   15
 3100000.00 .138499460 3200000.00 .138262606 3300000.00 .1396000289040 3 18   16
 3400000.00 .141199830 3500000.00 .141599831 3600000.00 .1408000329040 3 18   17
 3700000.00 .140250187 3800000.00 .141200072 3900000.00 .1423999139040 3 18   18
 4000000.00 .142899857 4100000.00 .142699906 4200000.00 .1424999559040 3 18   19
 4300000.00 .142300003 4400000.00 .142100052 4500000.00 .1422143549040 3 18   20
 4600000.00 .142642911 4700000.00 .143071468 4800000.00 .1435000259040 3 18   21
 4900000.00 .143928582 5000000.00 .144517803 5100000.00 .1454997569040 3 18   22
 5200000.00 .145249710 5300000.00 .143749811 5400000.00 .1417500209040 3 18   23
 5500000.00 .139250337 5600000.00 .138500176 5700000.00 .1390002899040 3 18   24
 5800000.00 .141500578 5900000.00 .148001097 6000000.00 .1620014499040 3 18   25
 6100000.00 .182000830 6200000.00 .203750523 6300000.00 .2272505289040 3 18   26
 6400000.00 .252499823 6500000.00 .276599003 6600000.00 .2977987789040 3 18   27
 6700000.00 .318998553 6800000.00 .340198328 6900000.00 .3613981039040 3 18   28
 7000000.00 .376248272 7100000.00 .384748835 7200000.00 .3904989219040 3 18   29
 7300000.00 .393498528 7400000.00 .391373544 7500000.00 .3841239679040 3 18   30
 7600000.00 .376874391 7700000.00 .369631916 7800000.00 .3644204229040 3 18   31
 7900000.00 .360806729 8000000.00 .356899918 8100000.00 .3526999919040 3 18   32
 8200000.00 .348500063 8300000.00 .344300135 8400000.00 .3401002089040 3 18   33
 8500000.00 .336600256 8600000.00 .333800279 8700000.00 .3310003029040 3 18   34
 8800000.00 .328200325 8900000.00 .325400348 9000000.00 .3236003459040 3 18   35
 9100000.00 .322800318 9200000.00 .322000290 9300000.00 .3212002629040 3 18   36
 9400000.00 .320400235 9500000.00 .320200157 9600000.00 .3206000309040 3 18   37
 9700000.00 .320999903 9800000.00 .321399775 9900000.00 .3217996489040 3 18   38
 10000000.0 .321099623 10100000.0 .319299700 10200000.0 .3174997779040 3 18   39
 10300000.0 .315699855 10400000.0 .313899932 10500000.0 .3121000099040 3 18   40
 10600000.0 .310300086 10700000.0 .308500164 10800000.0 .3067002419040 3 18   41
 10900000.0 .304900318 11000000.0 .304000321 11100000.0 .3040002509040 3 18   42
 11200000.0 .304000179 11300000.0 .304000107 11400000.0 .3040000369040 3 18   43
 11500000.0 .304000033 11600000.0 .304000099 11700000.0 .3040001669040 3 18   44
 11800000.0 .304000232 11900000.0 .304000298 12000000.0 .3048003069040 3 18   45
 12100000.0 .306400257 12200000.0 .308000208 12300000.0 .3096001599040 3 18   46
 12400000.0 .311200110 12500000.0 .313025081 12600000.0 .3150750729040 3 18   47
 12700000.0 .317125064 12800000.0 .319175055 12900000.0 .3212250479040 3 18   48
 13000000.0 .323275038 13100000.0 .325325030 13200000.0 .3273750219040 3 18   49
 13300000.0 .329425013 13400000.0 .331475004 13500000.0 .3335501219040 3 18   50
 13600000.0 .335650362 13700000.0 .337750604 13800000.0 .3398508469040 3 18   51
 13900000.0 .341951087 14000000.0 .346751036 14100000.0 .3542506929040 3 18   52
 14200000.0 .361750348 14300000.0 .369250003 14400000.0 .3767496599040 3 18   53
 14500000.0 .384249315 14600000.0 .389874281 14700000.0 .3936245569040 3 18   54
 14800000.0 .397374831 14900000.0 .401125106 15000000.0 .4053668939040 3 18   55
 15100000.0 .410100194 15200000.0 .414833495 15300000.0 .4195667969040 3 18   56
 15400000.0 .424300097 15500000.0 .429033398 15600000.0 .4337666999040 3 18   57
 15700000.0 .438483313 15800000.0 .443099809 15900000.0 .4476996189040 3 18   58
 16000000.0 .451299505 16100000.0 .453899472 16200000.0 .4564994389040 3 18   59
 16300000.0 .459099404 16400000.0 .461699371 16500000.0 .4642993379040 3 18   60
 16600000.0 .466899304 16700000.0 .469499270 16800000.0 .4720992369040 3 18   61
 16900000.0 .474699203 17000000.0 .475649295 17100000.0 .4749495149040 3 18   62
 17200000.0 .474249732 17300000.0 .473549950 17400000.0 .4728501699040 3 18   63
 17500000.0 .472150387 17600000.0 .471450606 17700000.0 .4707508249040 3 18   64
 17800000.0 .470051042 17900000.0 .469351261 18000000.0 .4713512799040 3 18   65
 18100000.0 .476051098 18200000.0 .480750917 18300000.0 .4854507359040 3 18   66
 18400000.0 .490150554 18500000.0 .494850373 18600000.0 .4995501929040 3 18   67
 18700000.0 .504250010 18800000.0 .508949829 18900000.0 .5136496489040 3 18   68
 19000000.0 .517499576 19100000.0 .520499613 19200000.0 .5234996509040 3 18   69
 19300000.0 .526499687 19400000.0 .529499724 19500000.0 .5324997619040 3 18   70
 19600000.0 .535499798 19700000.0 .538499835 19800000.0 .5414998729040 3 18   71
 19900000.0 .544499909 20000000.0 0.0                             9040 3 18   72
                                                                  9040 3  099999
 9.02320E+4 2.30044E+2          0          0          0          09040 3102    1
 4.78640E+6 4.78640E+6          0          0          1        6419040 3102    2
        641          1                                            9040 3102    3
 .000100000 117.717596 .000105000 114.972465 .000110000 112.3645769040 3102    4
 .000115000 109.961479 .000120000 107.152220 .000127500 104.0353799040 3102    5
 .000135000 101.187548 .000142500 98.5704503 .000150000 95.73802059040 3102    6
 .000160000 92.7873368 .000170000 90.1026352 .000180000 87.63829839040 3102    7
 .000190000 85.3454282 .000200000 83.2519344 .000210000 81.28235679040 3102    8
 .000220000 79.4530263 .000230000 77.7534639 .000240000 75.75853689040 3102    9
 .000255000 73.5659823 .000270000 71.8742409 .000280000 69.99118079040 3102   10
 .000300000 67.6943744 .000320000 65.6147172 .000340000 63.71014439040 3102   11
 .000360000 61.9559112 .000380000 60.3543582 .000400000 58.68475839040 3102   12
 .000425000 56.9764152 .000450000 55.4155706 .000475000 53.98450369040 3102   13
 .000500000 52.6386001 .000525000 51.4083118 .000550000 50.24608029040 3102   14
 .000575000 49.1651529 .000600000 48.0573418 .000630000 46.91773229040 3102   15
 .000660000 45.8748715 .000690000 44.8744625 .000720000 43.81004259040 3102   16
 .000760000 42.6686716 .000800000 41.6088204 .000840000 40.63725899040 3102   17
 .000880000 39.7138277 .000920000 38.8674685 .000960000 38.05690769040 3102   18
 .001000000 37.2166694 .001050000 36.3394262 .001100000 35.51694219040 3102   19
 .001150000 34.7590912 .001200000 33.8650807 .001275000 32.88238449040 3102   20
 .001350000 31.9838228 .001425000 31.1452380 .001500000 30.25449569040 3102   21
 .001600000 29.3230418 .001700000 28.4726712 .001800000 27.68617629040 3102   22
 .001900000 26.9677133 .002000000 26.3015200 .002100000 25.67635889040 3102   23
 .002200000 25.1039807 .002300000 24.5566911 .002400000 23.93225549040 3102   24
 .002550000 23.2382004 .002700000 22.6952333 .002800000 22.10554159040 3102   25
 .003000000 21.3795011 .003200000 20.7185473 .003400000 20.11387849040 3102   26
 .003600000 19.5622492 .003800000 19.0528074 .004000000 18.52179629040 3102   27
 .004250000 17.9828720 .004500000 17.4910479 .004750000 17.03148329040 3102   28
 .005000000 16.6099462 .005250000 16.2191227 .005500000 15.84959409040 3102   29
 .005750000 15.5105884 .006000000 15.1545074 .006300000 14.79878309040 3102   30
 .006600000 14.4627117 .006900000 14.1518952 .007200000 13.81281779040 3102   31
 .007600000 13.4492601 .008000000 13.1166977 .008400000 12.80447929040 3102   32
 .008800000 12.5138121 .009200000 12.2436716 .009600000 11.98660089040 3102   33
 .010000000 11.7204259 .010500000 11.4390181 .011000000 11.18162339040 3102   34
 .011500000 10.9360800 .012000000 10.6546914 .012750000 10.34322669040 3102   35
 .013500000 10.0546958 .014250000 9.78988762 .015000000 9.507197929040 3102   36
 .016000001 9.21021411 .017000001 8.93772944 .017999999 8.688957049040 3102   37
 .018999999 8.46027176 .020000000 8.24568794 .021000000 8.049197419040 3102   38
 .022000000 7.86409138 .023000000 7.69167626 .024000000 7.489465889040 3102   39
 .025500000 7.27213432 .027000001 7.10017272 .028000001 6.913551159040 3102   40
 .029999999 6.68370492 .032000002 6.47421280 .034000002 6.282990349040 3102   41
 .035999998 6.10855617 .037999999 5.94753456 .039999999 5.779328459040 3102   42
 .042500000 5.60831761 .045000002 5.45204742 .047499999 5.306473969040 3102   43
 .050000001 5.17257368 .052499998 5.04852697 .055000000 4.930998419040 3102   44
 .057500001 4.82340078 .059999999 4.71022229 .063000001 4.596858059040 3102   45
 .066000000 4.48999040 .068999998 4.39041832 .071999997 4.282415399040 3102   46
 .075999998 4.16667382 .079999998 4.06076698 .083999999 3.961125819040 3102   47
 .088000000 3.86836194 .092000000 3.78228946 .096000001 3.699986769040 3102   48
 .100000001 3.61485380 .104999997 3.52466255 .109999999 3.442182359040 3102   49
 .115000002 3.36336348 .119999997 3.27302265 .127499998 3.173399779040 3102   50
 .135000005 3.08098779 .142499998 2.99586987 .150000006 2.904812439040 3102   51
 .159999996 2.80887282 .170000002 2.72093103 .180000007 2.640377819040 3102   52
 .189999998 2.56634734 .200000003 2.49683305 .209999993 2.433374679040 3102   53
 .219999999 2.37339008 .230000004 2.31735697 .239999995 2.252175989040 3102   54
 .254999995 2.17907301 .270000011 2.12333892 .280000001 2.061599899040 3102   55
 .300000012 1.98578742 .319999993 1.91625736 .340000004 1.852888159040 3102   56
 .360000014 1.79473111 .379999995 1.74025445 .400000006 1.684892419040 3102   57
 .425000012 1.62861092 .449999988 1.57516393 .474999994 1.526449959040 3102   58
 .500000000 1.48180440 .524999976 1.43952136 .550000012 1.400689819040 3102   59
 .574999988 1.36377395 .600000024 1.32608723 .629999995 1.288288039040 3102   60
 .660000026 1.25244201 .689999998 1.21802661 .720000029 1.181535689040 3102   61
 .759999990 1.14277962 .800000012 1.10644514 .839999974 1.073211149040 3102   62
 .879999995 1.04172353 .920000017 1.01264674 .959999979 .9851716089040 3102   63
 1.00000000 .956038107 1.04999995 .926183156 1.10000002 .8979742459040 3102   64
 1.14999998 .872395836 1.20000005 .842109589 1.27499998 .8086236599040 3102   65
 1.35000002 .778257586 1.42499995 .749757624 1.50000000 .7199226839040 3102   66
 1.60000002 .688643210 1.70000005 .660468927 1.79999995 .6345953909040 3102   67
 1.89999998 .611022622 2.00000000 .588899851 2.09999990 .5687421669040 3102   68
 2.20000005 .550394153 2.29999995 .532947154 2.40000010 .5131081369040 3102   69
 2.54999995 .491271807 2.70000005 .474584932 2.79999995 .4565969309040 3102   70
 3.00000000 .434425625 3.20000005 .415050727 3.40000010 .3974006379040 3102   71
 3.59999990 .381584534 3.79999995 .367323626 4.00000000 .3527724399040 3102   72
 4.25000000 .338295876 4.50000000 .325110757 4.75000000 .3133694609040 3102   73
 5.00000000 .303267228 5.25000000 .293953576 5.50000000 .2855665319040 3102   74
 5.75000000 .277770758 6.00000000 .270102388 6.30000019 .2625471839040 3102   75
 6.59999990 .255929492 6.90000010 .249813290 7.19999981 .2436649449040 3102   76
 7.59999990 .238586990 8.00000000 .503553581 8.39999962 .2863362769040 3102   77
 8.80000019 .223111173 9.19999981 .218540561 9.60000038 .2151443099040 3102   78
 10.0000000 .212235602 10.5000000 .209717999 11.0000000 .2080073389040 3102   79
 11.5000000 .207247833 12.0000000 .207791935 12.7500000 .2951547429040 3102   80
 13.5000000 .214394588 14.2500000 .221544185 15.0000000 .2361351519040 3102   81
 16.0000000 .264004204 17.0000000 .314148900 18.0000000 .4122856149040 3102   82
 19.0000000 .647190716 20.0000000 1.58908644 21.0000000 348.6497699040 3102   83
 22.0000000 13.7818597 23.0000000 580.272945 24.0000000 2.930193819040 3102   84
 25.5000000 .555913332 27.0000000 .309736817 28.0000000 .2130329379040 3102   85
 30.0000000 .157303513 32.0000000 .132189787 34.0000000 .1188181339040 3102   86
 36.0000000 .164088285 38.0000000 .135759158 40.0000000 .1265483069040 3102   87
 42.5000000 .102371570 45.0000000 .157196272 47.5000000 .1233692639040 3102   88
 50.0000000 .122941177 52.5000000 .179861901 55.0000000 .2502567379040 3102   89
 57.5000000 90.2939115 60.0000000 .912830407 63.0000000 .6321927599040 3102   90
 66.0000000 24.3366888 69.0000000 271.925256 72.0000000 .5815312739040 3102   91
 76.0000000 .210880950 80.0000000 .142075695 84.0000000 .1178710979040 3102   92
 88.0000000 .177175958 92.0000000 .103142449 96.0000000 .1451483209040 3102   93
 100.000000 .156948948 105.000000 .177049679 110.000000 61.35374129040 3102   94
 115.000000 .833155910 120.000000 52.4531072 127.500000 12.61246379040 3102   95
 135.000000 .096591513 142.500000 .464631869 150.000000 .6322294319040 3102   96
 160.000000 2.92064219 170.000000 40.5825351 180.000000 .1441355559040 3102   97
 190.000000 34.1464386 200.000000 .313053176 210.000000 .3491740809040 3102   98
 220.000000 25.1147614 230.000000 .154139326 240.000000 15.73711019040 3102   99
 255.000000 11.5444632 270.000000 .185698563 280.000000 9.542452139040 3102  100
 300.000000 8.64438446 320.000000 12.5427253 340.000000 8.447136309040 3102  101
 360.000000 14.2073100 380.000000 .242211404 400.000000 3.519085549040 3102  102
 425.000000 .087542524 450.000000 6.86556759 475.000000 5.928064139040 3102  103
 500.000000 1.28130689 525.000000 3.35649766 550.000000 4.146925839040 3102  104
 575.000000 2.75726884 600.000000 1.01066055 630.000000 3.533309959040 3102  105
 660.000000 10.4884715 690.000000 4.60324876 720.000000 3.198388619040 3102  106
 760.000000 1.35002046 800.000000 3.20385549 840.000000 3.029109269040 3102  107
 880.000000 2.14459626 920.000000 1.92581674 960.000000 4.248621159040 3102  108
 1000.00000 2.48660615 1050.00000 1.22423539 1100.00000 2.257732309040 3102  109
 1150.00000 1.35929281 1200.00000 2.92156323 1275.00000 1.828611139040 3102  110
 1350.00000 2.82915468 1425.00000 1.66774418 1500.00000 2.565043429040 3102  111
 1600.00000 2.50133524 1700.00000 1.68617223 1800.00000 2.282139959040 3102  112
 1900.00000 2.12353389 2000.00000 1.37174720 2100.00000 2.056500689040 3102  113
 2200.00000 1.83149119 2300.00000 1.65067293 2400.00000 1.467774939040 3102  114
 2550.00000 1.84524578 2700.00000 1.83833978 2800.00000 1.384372559040 3102  115
 3000.00000 1.53838922 3200.00000 1.35952475 3400.00000 .8649848279040 3102  116
 3600.00000 1.15591066 3800.00000 1.40748008 4000.00000 1.111035839040 3102  117
 4250.00000 1.07128158 4500.00000 1.03449171 4750.00000 1.000201769040 3102  118
 5000.00000 .973593704 5250.00000 .953520883 5500.00000 .9350279759040 3102  119
 5750.00000 .918114982 6000.00000 .900391280 6300.00000 .8819826279040 3102  120
 6600.00000 .865208821 6900.00000 .849255855 7200.00000 .8319234349040 3102  121
 7600.00000 .813541191 8000.00000 .796481488 8400.00000 .7805729709040 3102  122
 8800.00000 .765755262 9200.00000 .751972679 9600.00000 .7383556069040 3102  123
 10000.0000 .724537391 10500.0000 .710518034 11000.0000 .6972472909040 3102  124
 11500.0000 .684725159 12000.0000 .670198070 12750.0000 .6541666739040 3102  125
 13500.0000 .639803940 14250.0000 .626106419 15000.0000 .6108198579040 3102  126
 16000.0000 .594277804 17000.0000 .579237312 18000.0000 .5651981659040 3102  127
 19000.0000 .552160936 20000.0000 .540125394 21000.0000 .5281135479040 3102  128
 22000.0000 .517106375 23000.0000 .506579531 24000.0000 .4942983439040 3102  129
 25500.0000 .480763374 27000.0000 .469986373 28000.0000 .4597073769040 3102  130
 30000.0000 .448673655 32000.0000 .439883360 34000.0000 .4323360589040 3102  131
 36000.0000 .427078591 38000.0000 .422812572 40000.0000 .4208046729040 3102  132
 42500.0000 .418363187 45000.0000 .410433795 47500.0000 .3974149129040 3102  133
 50000.0000 .382527128 52500.0000 .367607866 55000.0000 .3526886039040 3102  134
 57500.0000 .337769341 60000.0000 .324008124 63000.0000 .3119999999040 3102  135
 66000.0000 .299999999 69000.0000 .288736879 72000.0000 .2780678019040 3102  136
 76000.0000 .266022623 80000.0000 .256066783 84000.0000 .2480740989040 3102  137
 88000.0000 .240299624 92000.0000 .234074339 96000.0000 .2281518469040 3102  138
 100000.000 .222706480 105000.000 .218100000 110000.000 .2135000009040 3102  139
 115000.000 .208900000 120000.000 .203365159 127500.000 .1984077539040 3102  140
 135000.000 .193825772 142500.000 .189258045 150000.000 .1852126519040 3102  141
 160000.000 .181541436 170000.000 .177744490 180000.000 .1728635829040 3102  142
 190000.000 .167733061 200000.000 .163506608 210000.000 .1605000009040 3102  143
 220000.000 .157500000 230000.000 .154500000 240000.000 .1510044389040 3102  144
 255000.000 .148884890 270000.000 .147521763 280000.000 .1460064759040 3102  145
 300000.000 .144700087 320000.000 .144100124 340000.000 .1435002079040 3102  146
 360000.000 .142900291 380000.000 .142300374 400000.000 .1430003639040 3102  147
 425000.000 .145000258 450000.000 .147000153 475000.000 .1490017709040 3102  148
 500000.000 .151942351 525000.000 .155672651 550000.000 .1594029529040 3102  149
 575000.000 .163122586 600000.000 .164940353 630000.000 .1650000009040 3102  150
 660000.000 .165000000 690000.000 .164661912 720000.000 .1629724359040 3102  151
 760000.000 .160945120 800000.000 .157571511 840000.000 .1527142539040 3102  152
 880000.000 .147855060 920000.000 .142800070 960000.000 .1376001919040 3102  153
 1000000.00 .130600244 1100000.00 .121800229 1200000.00 .1134002049040 3102  154
 1300000.00 .107400117 1400000.00 .101800020 1500000.00 .0959999459040 3102  155
 1600000.00 .089999894 1700000.00 .083749872 1800000.00 .0760000279040 3102  156
 1900000.00 .068000212 2000000.00 .061800293 2100000.00 .0574002709040 3102  157
 2200000.00 .053000247 2300000.00 .048600224 2400000.00 .0442002019040 3102  158
 2500000.00 .040800183 2600000.00 .038400170 2700000.00 .0360001579040 3102  159
 2800000.00 .033600144 2900000.00 .031200131 3000000.00 .0294001229040 3102  160
 3100000.00 .028200118 3200000.00 .027000114 3300000.00 .0258001109040 3102  161
 3400000.00 .024600106 3500000.00 .023400102 3600000.00 .0222000989040 3102  162
 3700000.00 .021000094 3800000.00 .019800090 3900000.00 .0186000869040 3102  163
 4000000.00 .017750083 4100000.00 .017250081 4200000.00 .0167500799040 3102  164
 4300000.00 .016250077 4400000.00 .015750075 4500000.00 .0152500729040 3102  165
 4600000.00 .014750070 4700000.00 .014250068 4800000.00 .0137500669040 3102  166
 4900000.00 .013250064 5000000.00 .012750062 5100000.00 .0122500609040 3102  167
 5200000.00 .011750058 5300000.00 .011250056 5400000.00 .0107500549040 3102  168
 5500000.00 .010250051 5600000.00 .009750049 5700000.00 .0092500479040 3102  169
 5800000.00 .008750045 5900000.00 .008250043 6000000.00 .0078950419040 3102  170
 6100000.00 .007685040 6200000.00 .007475039 6300000.00 .0072650389040 3102  171
 6400000.00 .007055037 6500000.00 .006845036 6600000.00 .0066350359040 3102  172
 6700000.00 .006425034 6800000.00 .006215033 6900000.00 .0060050329040 3102  173
 7000000.00 .005795030 7100000.00 .005585029 7200000.00 .0053750289040 3102  174
 7300000.00 .005165027 7400000.00 .004955026 7500000.00 .0047450259040 3102  175
 7600000.00 .004535024 7700000.00 .004325023 7800000.00 .0041150229040 3102  176
 7900000.00 .003905021 8000000.00 .003755020 8100000.00 .0036650209040 3102  177
 8200000.00 .003575019 8300000.00 .003485019 8400000.00 .0033950199040 3102  178
 8500000.00 .003305019 8600000.00 .003215018 8700000.00 .0031250189040 3102  179
 8800000.00 .003035018 8900000.00 .002945018 9000000.00 .0028550179040 3102  180
 9100000.00 .002765017 9200000.00 .002675017 9300000.00 .0025850179040 3102  181
 9400000.00 .002495016 9500000.00 .002405016 9600000.00 .0023150169040 3102  182
 9700000.00 .002225016 9800000.00 .002135015 9900000.00 .0020450159040 3102  183
 10000000.0 .001993765 10100000.0 .001981265 10200000.0 .0019687649040 3102  184
 10300000.0 .001956264 10400000.0 .001943764 10500000.0 .0019312639040 3102  185
 10600000.0 .001918763 10700000.0 .001906263 10800000.0 .0018937629040 3102  186
 10900000.0 .001881262 11000000.0 .001868762 11100000.0 .0018562619040 3102  187
 11200000.0 .001843761 11300000.0 .001831261 11400000.0 .0018187609040 3102  188
 11500000.0 .001806260 11600000.0 .001793760 11700000.0 .0017812599040 3102  189
 11800000.0 .001768759 11900000.0 .001756259 12000000.0 .0017437589040 3102  190
 12100000.0 .001731258 12200000.0 .001718758 12300000.0 .0017062579040 3102  191
 12400000.0 .001693757 12500000.0 .001681257 12600000.0 .0016687569040 3102  192
 12700000.0 .001656256 12800000.0 .001643756 12900000.0 .0016312559040 3102  193
 13000000.0 .001618755 13100000.0 .001606255 13200000.0 .0015937549040 3102  194
 13300000.0 .001581254 13400000.0 .001568754 13500000.0 .0015562539040 3102  195
 13600000.0 .001543753 13700000.0 .001531253 13800000.0 .0015187529040 3102  196
 13900000.0 .001506252 14000000.0 .001499169 14100000.0 .0014975029040 3102  197
 14200000.0 .001495835 14300000.0 .001494169 14400000.0 .0014925029040 3102  198
 14500000.0 .001490835 14600000.0 .001489169 14700000.0 .0014875029040 3102  199
 14800000.0 .001485835 14900000.0 .001484169 15000000.0 .0014825029040 3102  200
 15100000.0 .001480835 15200000.0 .001479169 15300000.0 .0014775029040 3102  201
 15400000.0 .001475835 15500000.0 .001474169 15600000.0 .0014725029040 3102  202
 15700000.0 .001470835 15800000.0 .001469169 15900000.0 .0014675029040 3102  203
 16000000.0 .001465835 16100000.0 .001464169 16200000.0 .0014625029040 3102  204
 16300000.0 .001460835 16400000.0 .001459169 16500000.0 .0014575029040 3102  205
 16600000.0 .001455835 16700000.0 .001454169 16800000.0 .0014525029040 3102  206
 16900000.0 .001450835 17000000.0 .001449169 17100000.0 .0014475029040 3102  207
 17200000.0 .001445835 17300000.0 .001444169 17400000.0 .0014425029040 3102  208
 17500000.0 .001440835 17600000.0 .001439169 17700000.0 .0014375029040 3102  209
 17800000.0 .001435835 17900000.0 .001434169 18000000.0 .0014325029040 3102  210
 18100000.0 .001430835 18200000.0 .001429169 18300000.0 .0014275029040 3102  211
 18400000.0 .001425835 18500000.0 .001424169 18600000.0 .0014225029040 3102  212
 18700000.0 .001420835 18800000.0 .001419169 18900000.0 .0014175029040 3102  213
 19000000.0 .001415835 19100000.0 .001414169 19200000.0 .0014125029040 3102  214
 19300000.0 .001410835 19400000.0 .001409169 19500000.0 .0014075029040 3102  215
 19600000.0 .001405835 19700000.0 .001404169 19800000.0 .0014025029040 3102  216
 19900000.0 .001400835 20000000.0 0.0                             9040 3102  217
                                                                  9040 3  099999
                                                                  9040 0  0    0
 9.02320E+4 2.30044E+2          0          0          0          1904033 18    1
 0.000000+0 0.000000+0          0         18          0          2904033 18    2
 0.000000+0 0.000000+0          0          1          6          3904033 18    3
 1.000000-5 0.000000+0 5.000000+5 1.600000-3 2.000000+7 0.000000+0904033 18    4
 0.000000+0 0.000000+0          0          1         24         12904033 18    5
 1.000000-5 0.000000+0 5.000000+5 1.024000-1 8.000000+5 1.440000-2904033 18    6
 9.000000+5 1.000000-2 1.000000+6 4.900000-3 1.200000+6 3.600000-3904033 18    7
 1.400000+6 1.600000-3 1.600000+6 3.600000-3 3.000000+6 1.600000-3904033 18    8
 4.000000+6 3.600000-3 6.000000+6 1.000000-2 2.000000+7 0.000000+0904033 18    9
                                                                  904033  099999
 9.02320E+4 2.30044E+2          0          0          0          1904033102    1
 0.000000+0 0.000000+0          0        102          0          2904033102    2
 0.000000+0 0.000000+0          0          1          6          3904033102    3
 1.000000-5 0.000000+0 1.500000+1 2.500000-3 2.000000+7 0.000000+0904033102    4
 0.000000+0 0.000000+0          0          1         10          5904033102    5
 1.000000-5 2.000000-4 3.000000-2 6.400000-3 1.500000+1 1.000000-2904033102    6
 1.000000+6 4.000000-2 2.000000+7 0.000000+0                      904033102    7
                                                                  904033  099999
                                                                  9040 0  0    0
                                                                     0 0  0    0
 9.22350E+4 2.33024E+2          0          1         34         109228 1451    1
 0.0        1.00000E+0          0          0          0          69228 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20029228 1451    3
 3.00000E+2 0.0                 1          0        414          49228 1451    4
 92-U -235 ORNL,LANL,+EVAL-NOV89 WESTON, YOUNG, POENITZ, LUBITZ   9228 1451    5
                      DIST-Feb2004                                9228 1451    6
----IRDF-2002         MATERIAL 9228                               9228 1451    7
-----INCIDENT NEUTRON DATA                                        9228 1451    8
------ENDF-6 FORMAT                                               9228 1451    9
 **************************************************************** 9228 1451   10
 92-U -235 ORNL,LANL,+EVAL-NOV89 WESTON, YOUNG, POENITZ, LUBITZ   9228 1451   11
                      DIST-NOV98 REV5-OCT97            19981109   9228 1451   12
----ENDF/B-VI         MATERIAL 9228         REVISION 5            9228 1451   13
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************9228 1451   14
DOSIMETRY                                                         9228 1451   15
******************************************************************9228 1451   16
                                                                  9228 1451   17
 ENDF/B-VI MOD 6 Revision, October 1997, L.C. Leal, H. Derrien,   9228 1451   18
                 N.M. Larson, and R.Q. Wright (ORNL)              9228 1451   19
                                                                  9228 1451   20
 1. New resonance parameter analysis; File 2, MT=151.             9228 1451   21
 2. Total and prompt-nubar revised below 2 eV; File 1, MT=451,    9228 1451   22
    452,456.                                                      9228 1451   23
                                                                  9228 1451   24
 ---------------------------------------------------------------- 9228 1451   25
 File 2                                                           9228 1451   26
   MT=151  Resonance parameters, from a new analysis by Leal      9228 1451   27
     et al. [LE97], using the multilevel R-matrix analysis code   9228 1451   28
     SAMMY [LA96].  Energy range for U235 is 0 to 2.25 keV.       9228 1451   29
     For the first time, integral data were fitted during the     9228 1451   30
       analysis process:  Thermal cross sections (fission,        9228 1451   31
       capture, and elastic), Westcott g-factors (fission and     9228 1451   32
       absorption) are from the ENDF/B-6 standards [CA93], and    9228 1451   33
       the K1 value is from Hardy [HA79].                         9228 1451   34
     Thermal parameters obtained in the present evaluation,       9228 1451   35
       first using the microscopic experimental data only, and    9228 1451   36
       second including the integral data as well, are compared   9228 1451   37
       to the SAMMY input in the following Table:                 9228 1451   38
                                                                  9228 1451   39
       Parameter        SAMMY input       Fit to    Fit to diff.  9228 1451   40
                          value          diff data    & integ.    9228 1451   41
                                          alone         data      9228 1451   42
       -----------    -----------------  --------   ------------  9228 1451   43
       Fission        584.25 +/- 1.11    582.28      584.88       9228 1451   44
       Capture         98.96 +/- 0.74     99.18       98.66       9228 1451   45
       Scattering      15.46 +/- 1.06     15.44       15.12       9228 1451   46
       Westcott gf    0.9771 +/- 0.0008    0.9743      0.9764     9228 1451   47
       Westcott ga    0.9790 +/- 0.0008    0.9774      0.9785     9228 1451   48
       Westcott gg                         0.9956      0.9910     9228 1451   49
       K1(barn)       722.70 +/- 3.90    717.48      722.43       9228 1451   50
                                                                  9228 1451   51
     The final adjustment of nu by SAMMY to the recommended K1    9228 1451   52
       value of 722.7 gave nu = 2.4367 +/- 0.0005, with fission   9228 1451   53
       and absorption cross sections calculated from the final    9228 1451   54
       resonance parameters.                                      9228 1451   55
     In the following Tables, the fission and capture cross       9228 1451   56
       sections calculated in this evaluation with the code       9228 1451   57
       SAMMY are compared with experimental data.                 9228 1451   58
                                                                  9228 1451   59
       Experimental and calculated total cross sections.          9228 1451   60
                                                                  9228 1451   61
       Energy Range    Calculated  Schrack   Weston   Weston      9228 1451   62
           (eV)          (b.eV)     (b.eV)   (b.eV)   (b.eV)      9228 1451   63
      ---------------  ----------  -------   ------   ------      9228 1451   64
         0.5 -   20.0    910.4      929.9                         9228 1451   65
        20.0 -   60.0   1867.8     1882.8    1869.9               9228 1451   66
        60.0 -  100.0    954.0      968.0     954.2               9228 1451   67
       100.0 -  200.0   2032.7     2092.7    2089.5   2073.9      9228 1451   68
       200.0 -  300.0   2062.2     2007.0    2060.0   2054.6      9228 1451   69
       300.0 -  400.0   1280.8     1321.6    1297.1   1292.9      9228 1451   70
       400.0 -  500.0   1333.2     1391.5    1351.8   1347.9      9228 1451   71
       500.0 -  600.0   1489.2     1467.9    1499.2   1494.3      9228 1451   72
       600.0 -  700.0   1126.6     1156.4    1134.1   1132.6      9228 1451   73
       700.0 -  800.0   1088.7     1085.8    1093.3   1075.7      9228 1451   74
       800.0 -  900.0    797.6      784.0     813.0    804.9      9228 1451   75
       900.0 - 1000.0    724.4      723.9     738.2    721.4      9228 1451   76
      1000.0 - 2000.0   7036.1                        7054.2      9228 1451   77
                                                                  9228 1451   78
       Experimental and calculated capture cross sections.        9228 1451   79
                                                                  9228 1451   80
       Energy Range     Calculated   De Saussure     Perez        9228 1451   81
           (eV)           (b.eV)       (b.eV)       (b.eV)        9228 1451   82
      ---------------   ----------   -----------    ------        9228 1451   83
        0.5  -   20.0      653.5         647                      9228 1451   84
       20.0  -   60.0     1066.1        1084         1057         9228 1451   85
       60.0  -  100.0      490.2         477          504         9228 1451   86
       100.0 -  200.0     1158.8        1148         1138         9228 1451   87
       200.0 -  300.0      907.8         904          940         9228 1451   88
       300.0 -  400.0      660.2         658          642         9228 1451   89
       400.0 -  500.0      495.9         506          478         9228 1451   90
       500.0 -  600.0      533.3         506          562         9228 1451   91
       600.0 -  700.0      494.8         481          449         9228 1451   92
       700.0 -  800.0      490.1         513          475         9228 1451   93
       800.0 -  900.0      439.8         444          397         9228 1451   94
       900.0 - 1000.0      504.2         542          482         9228 1451   95
      1000.0 - 1100.0      509.6         522          463         9228 1451   96
      1100.0 - 1200.0      413.7         395          332         9228 1451   97
      1200.0 - 1300.0      340.4         372          267         9228 1451   98
      1300.0 - 1400.0      304.1         304          225         9228 1451   99
      1400.0 - 1500.0      355.7         301          254         9228 1451  100
      ---------------   ----------   -----------    ------        9228 1451  101
        20.0 - 1500.0     9164.7        9046         8665         9228 1451  102
                                                                  9228 1451  103
    The fission and capture resonance integral calculated from    9228 1451  104
 the present evaluation are 276.04 b and 140.49 b, respectively,  9228 1451  105
 giving a capture-to-fission ratio (alpha value) of 0.509 in      9228 1451  106
 excellent agreement with the value obtained from integral        9228 1451  107
 measurements.                                                    9228 1451  108
    The following energy-differential data were included in the   9228 1451  109
 analysis:                                                        9228 1451  110
  (1) Transmission data of Harvey et al. [HA86] on the ORELA      9228 1451  111
      18-meter flight path, with sample thickness of 0.03269      9228 1451  112
      atoms/barn, cooled to 77 K (0.4 to 68 eV).                  9228 1451  113
  (2) Transmission data of Harvey et al. [HA86] on the ORELA      9228 1451  114
      80-meter flight path, with sample thickness of 0.00233      9228 1451  115
      atoms/barn, cooled to 77 K (4 to 2250 eV).                  9228 1451  116
  (3) Transmission data of Harvey et al. [HA86] on the ORELA      9228 1451  117
      80-meter flight path, with sample thickness of 0.03269      9228 1451  118
      atoms/barn, cooled to 77 K (4 to 2250 eV).                  9228 1451  119
  (4) Fission data of Schrack [SC88] on the RPI Linac at 8.4      9228 1451  120
      meter flight path (0.02 to 20 eV).                          9228 1451  121
 (5,6) Fission and capture data of de Saussure et al. [DE67]      9228 1451  122
      on the ORELA 25.2-meter flight path (0.01 to 2250 eV).      9228 1451  123
 (7,8) Fission and capture data of Perez et al. [PE73] on the     9228 1451  124
      ORELA 39-meter flight path (0.01 to 100 eV).                9228 1451  125
  (9) Fission data of Gwin et al. [GW84] on the ORELA 25.6-meter  9228 1451  126
      flight path (0.01 to 20 eV).                                9228 1451  127
 (10) Transmission data of Spencer et al. [SP84] on the ORELA     9228 1451  128
     ORELA 18-meter flight path, sample thickness of 0.001468     9228 1451  129
     atom/barn (0.01 to 1.0 eV).                                  9228 1451  130
 (11) Fission data of Wagemans et al. [WA88] on the Geel 18-      9228 1451  131
      meter flight path (0.001 to 1.0 eV)                         9228 1451  132
 (12,13) Absorption and fission data of Gwin [GW96] at ORELA      9228 1451  133
      (0.01 to 4.0 eV).                                           9228 1451  134
 (14) Fission data of Weston and Todd [WE84] on the ORELA         9228 1451  135
      18.9-meter flight path (14 to 2250 eV).                     9228 1451  136
 (15) Eta data of Wartena et al. [WA87] at 8 meters (0.0018 to    9228 1451  137
      1.0 eV).                                                    9228 1451  138
 (16) Eta (chopper) data of Weigmann et al [WE90] (0.0015 to      9228 1451  139
      0.15 eV).                                                   9228 1451  140
 (17) Fission data of Weston and Todd [WE92] on the ORELA         9228 1451  141
      86.5-meter flight path (100 to 2000 eV).                    9228 1451  142
 (18) Fission yield data of Moxon et al. [MO92] at ORELA          9228 1451  143
      (0.01 to 50.0 eV).                                          9228 1451  144
                                                                  9228 1451  145
 ---------------------------------------------------------------- 9228 1451  146
 REFERENCES FOR RESOLVED RESONANCE REGION                         9228 1451  147
                                                                  9228 1451  148
 [CA93] A. Carlson, W.P. Poenitz, G.M. Hale et al., "The ENDF/B-6 9228 1451  149
    Neutron Cross Section Measurements Standards," National       9228 1451  150
    Institute of Standards and Technology report NISTIR-5177      9228 1451  151
    (1993)                                                        9228 1451  152
 [DE67] G. de Saussure, R. Gwin, L.W. Weston, and R.W. Ingle,     9228 1451  153
    "Simultaneous Measurements of the Neutron Fission and Capture 9228 1451  154
    Cross Section for 235U for Incident Neutron Energy from       9228 1451  155
    0.04 eV to 3 keV," Oak Ridge National Laboratory report       9228 1451  156
    ORNL/TM-1804 (1967)                                           9228 1451  157
 [GW84] R. Gwin, R.R. Spencer, R.W. Ingle, J.H. Todd, and S.W.    9228 1451  158
    Scoles, Nuc.Sci.Eng. 88, 37 (1984)                            9228 1451  159
 [GW96] R. Gwin, To be published in Nuclear Science Engineering   9228 1451  160
 [HA79] J. Hardy, Brookhaven National Laboratory, report          9228 1451  161
    BNL-NCS-51123 [ENDF-300] (1979) Sec. B.1                      9228 1451  162
 [HA86] J.A. Harvey, N.W. Hill, F.G. Perey et al., Nuclear Data   9228 1451  163
    for Science and Technology, Proc. Int. Conf. May 30-June 3,   9228 1451  164
    1988, Mito, Japan. (Saikon Publishing, 1988) p. 115           9228 1451  165
 [LA96] N.M. Larson, "Updated Users' Guide to SAMMY" report       9228 1451  166
    ORNL/TM-9179/R3 (1996)                                        9228 1451  167
 [LE97] L.C. Leal, H. Derrien, N.M. Larson, R.Q. Wright,          9228 1451  168
    "R-Matrix Analysis of 235U Neutron Transmission and Cross     9228 1451  169
    Sections in the Energy Range 0 eV to 2.25 keV," Oak Ridge     9228 1451  170
    National Laboratory report ORNL/TM-13516 (1997).              9228 1451  171
 [MO92] M.C. Moxon, J.A. Harvey, and N.W. Hill, private           9228 1451  172
    communication, Oak Ridge National Laboratory (1992).          9228 1451  173
 [PE73] R.B. Perez, G. de Saussure, and E.G. Silver, Nucl.Sci.    9228 1451  174
    Eng. 52, 46 (1973)                                            9228 1451  175
 [SC88] R.A. Schrack, "Measurement of the 235U(n,f) Reaction from 9228 1451  176
    Thermal to 1 keV," Nuclear Data for Science and Technology,   9228 1451  177
    Proc. Int. Conf. May 30-June 3, Mito, Japan (Saikon           9228 1451  178
    Publishing, 1988) p. 101                                      9228 1451  179
 [SP84] R.R. Spencer, J.A. Harvey, N.W. Hill, and L. Weston,      9228 1451  180
    Nucl.Sci.Eng. 96, 318 (1987)                                  9228 1451  181
 [WA87] J.A. Wartena, H. Weigmann, and C. Burkholz, report  IAEA  9228 1451  182
    Tecdoc 491 (1987) p.123                                       9228 1451  183
 [WA88] C. Wagemans, P. Schillebeeckx, A.J. Deruyter, and R.      9228 1451  184
    Barthelemy, "Subthermal Fission Cross Section Measurements    9228 1451  185
    for 233U and 239Pu," Nuclear Data for Science and Technology, 9228 1451  186
    Proc. Int. Conf. May 30-June 3, Mito, Japan (Saikon           9228 1451  187
    Publishing, 1988) p. 91                                       9228 1451  188
 [WE84] L.W. Weston and J.H. Todd, Nucl.Sci.Eng. 88, 567 (1984)   9228 1451  189
 [WE90] H. Weigmann, P. Geltenbort, B. Keck, K. Shrenckenbach,    9228 1451  190
    and J.A. Wartena, The Physics of Reactors, Proc. Int.  Conf., 9228 1451  191
    Marseille, 1990, Vol.1 (1990) p. 133                          9228 1451  192
 [WE92] L.W. Weston and J.H. Todd, Nucl.Sci.Eng. 111, 415 (1992)  9228 1451  193
                                                                  9228 1451  194
 **************************************************************** 9228 1451  195
                                                                  9228 1451  196
 ENDF/B-VI MOD 5 Revision 4 (R.Q.Wright, ORNL, V. McLane, NNDC,   9228 1451  197
                 October, 1996)                                   9228 1451  198
                                                                  9228 1451  199
 File 1, MT=451: Update of comments.                              9228 1451  200
 File 1, MT=456: Update of prompt nubar.                          9228 1451  201
                                                                  9228 1451  202
 *****************************************************************9228 1451  203
                                                                  9228 1451  204
 ENDF/B-VI MOD 4 Revision, February 1995, C. Lubitz (KAPL)        9228 1451  205
                                                                  9228 1451  206
 The resonance parameters below 900 eV were adjusted as described 9228 1451  207
 in C.R. Lubitz, "A modification to ENDF6 U235 to increase        9228 1451  208
    epithermal alpha and K1", Proceedings of the Int. Conf. on    9228 1451  209
    Nuclear Data for Science and Technology, Gatlinburg, TN, May  9228 1451  210
    9-13, Vol. 2 (American Nuclear Soc., 1994) page 646.          9228 1451  211
                                                                  9228 1451  212
 *****************************************************************9228 1451  213
                                                                  9228 1451  214
 ENDF/B-VI MOD 3 Revision 2                                       9228 1451  215
                                                                  9228 1451  216
 Missing File 1 section 458 added.                                9228 1451  217
                                                                  9228 1451  218
 *****************************************************************9228 1451  219
                                                                  9228 1451  220
 ENDF/B-VI MOD 2 Revision, L. Weston (ORNL)                       9228 1451  221
                                                                  9228 1451  222
 FILE 1: The uncertainties on the fission cross section           9228 1451  223
 recommended by the Standards Committee of CSEWG are listed. The  9228 1451  224
 updated description of File 2, the resolved resonance parameters,9228 1451  225
 is given.                                                        9228 1451  226
                                                                  9228 1451  227
 FILE 2: The resolved resonance parameters have been changed      9228 1451  228
 extensively. The neutron energy region below 4 eV has been made  9228 1451  229
 a separate group. Eta decreases with decreasing neutron energy   9228 1451  230
 below 0.1 eV. At the higher neutron energies, the resonance      9228 1451  231
 parameters are more refined.                                     9228 1451  232
                                                                  9228 1451  233
 FILE 3: Smooth cross sections above 100 keV have minor           9228 1451  234
 corrections.                                                     9228 1451  235
                                                                  9228 1451  236
 FILE 31: Nubar covariance files were updated.                    9228 1451  237
                                                                  9228 1451  238
 FILE 33: All covariance files were removed as correct new files  9228 1451  239
 are not yet available.                                           9228 1451  240
 *****************************************************************9228 1451  241
                                                                  9228 1451  242
 ENDF/B-VI, MOD 1 Evaluation, April 1989                          9228 1451  243
                                                                  9228 1451  244
 Principal evaluators:                                            9228 1451  245
  Thermal parameters: Standards Committee of CSEWG.               9228 1451  246
  Resolved resonance region: (0-2250 eV) L.C. Leal (U.Tenn.),     9228 1451  247
    G. deSaussure (ORNL), R.B. Perez (U.Tenn.), N.M. Larson       9228 1451  248
    (ORNL), M.S.Moore (LANL), and R.Q. Wright (ORNL).             9228 1451  249
    Replaced by revision 6.                                       9228 1451  250
  Unresolved resonance region and File 3 below 100 keV and the    9228 1451  251
    capture cross section above 100 keV: W.P. Poenitz (ANL) and   9228 1451  252
    L.W. Weston (ORNL)                                            9228 1451  253
  Fission cross section above 100 keV: W.P. Poenitz (ANL) and the 9228 1451  254
    Standards Committee of CSEWG.                                 9228 1451  255
  Model calculations and fits above 100 keV: P.G. Young (LANL),   9228 1451  256
    R.E. MacFarlane (LANL), and E.D. Arthur (LANL).               9228 1451  257
  Covariance files: R.W. Peelle (ORNL).  All files reoved in      9228 1451  258
    revision 1, except MT=456.                                    9228 1451  259
                                                                  9228 1451  260
 File 1 Descriptive and Nubar Information ----------------------- 9228 1451  261
   MT=452 Total nubar.  Replaced in revision 6.                   9228 1451  262
   MT=455 Delayed neutron yields from England [EN89].             9228 1451  263
   MT=456 Prompt neutron yields. Replaced in revision 6.          9228 1451  264
                                                                  9228 1451  265
 FISSION CROSS SECTION UNCERTAINTIES:  The CSEWG Standards        9228 1451  266
 Committee supplied the following uncertainties with the these    9228 1451  267
 statements.  "These uncertainties are estimates such that if a   9228 1451  268
 modern day experiment were performed today on a given standard   9228 1451  269
 using the best techniques, those results should fall within these9228 1451  270
 expanded uncertainties (2/3 of the time).  They take into account9228 1451  271
 inconsistencies and concerns about R-matrix parameters.  Note    9228 1451  272
 that it is not assumed that the uncertainties are totally        9228 1451  273
 correlated within the energy ranges given."                      9228 1451  274
                                                                  9228 1451  275
          Energy (keV)          Estimated         Comb Result (%) 9228 1451  276
                             Uncertainty (%)                      9228 1451  277
           2.53E-05                0.2                (0.19)      9228 1451  278
           150-600                 1.5                            9228 1451  279
           600-1000                1.6                (0.60)      9228 1451  280
           1000-3000               1.8                            9228 1451  281
           3000-6000               2.3                (0.69)      9228 1451  282
           6000-10000              2.2                            9228 1451  283
           10000-12000             1.8                (1.14)      9228 1451  284
           12000-14000             1.2                            9228 1451  285
           14000-14500             0.8                (0.55)      9228 1451  286
           14500-15000             1.5                            9228 1451  287
           15000-16000             2.0                (0.97)      9228 1451  288
           16000-17000             2.5                            9228 1451  289
           17000-19000             3.0                (1.26)      9228 1451  290
           19000-20000             4.0                            9228 1451  291
                                                                  9228 1451  292
 File 2.  RESOLVED AND UNRESOLVED RESONANCE PARAMETERS ---------- 9228 1451  293
   MT=151                                                         9228 1451  294
     Resolved resonance region: replaced in revision 6.           9228 1451  295
     Unresolved resonance region:                                 9228 1451  296
        The unresolved resonance region was derived by a FITACS   9228 1451  297
     (Fritz Froehner code) fit by L.W. Weston to the Standards    9228 1451  298
     Committee recommendation for the fission cross section and   9228 1451  299
     new capture evaluation based on newer alpha measurements     9228 1451  300
     (see ANL-83-4 supplement).  These results were then fit      9228 1451  301
     with URES (Ed Pennington code) so ENDF would reproduce.      9228 1451  302
     unresolved resonance region extends from 2.25 to 25 keV      9228 1451  303
     and is used only for self shielding calculations.  Dilute    9228 1451  304
     cross sections are taken from File 3 which shows             9228 1451  305
     experimentally observed structure carried over from          9228 1451  306
     version 5 up to 100 keV.                                     9228 1451  307
                                                                  9228 1451  308
 File 3. SMOOTH CROSS SECTIONS ---------------------------------- 9228 1451  309
    Model calculations from LANL: P.G. Young, R.E.MacFarlane,     9228 1451  310
 E.D.Arthur.  The evaluation above 100 keV is based on a detailed 9228 1451  311
 theoretical analysis utilizing the available experimental data.  9228 1451  312
 Coupled channel optical model calculations with the ECIS code    9228 1451  313
 [Ra70] were used to provide the total, elastic, and inelastic    9228 1451  314
 cross sections to the first 3 members of the ground state        9228 1451  315
 rotational band, as well as neutron elastic and inelastic        9228 1451  316
 angular distributions to the rotational levels.  The ECIS code   9228 1451  317
 was also used to calculate neutron transmission coefficients.    9228 1451  318
 Hauser-Feshbach statistical theory calculations were carried out 9228 1451  319
 with the GNASH [Ar88,Yo77] and COMNUC [Du70] code systems,       9228 1451  320
 including preequilibrium and fission.  DWBA calculations were    9228 1451  321
 performed with the DWUCK code [Ku70] for several vibrational     9228 1451  322
 levels, using B(El) values inferred from (d,d') data on U234,    9228 1451  323
 U235, U238, as well as Coulomb excitation measurements.  A weak  9228 1451  324
 coupling model [Pe69] was used to apply the U234 and U238        9228 1451  325
 results to states in U235.                                       9228 1451  326
    A preliminary description of the analysis was given at the    9228 1451  327
 Mito conference [Yo88].                                          9228 1451  328
                                                                  9228 1451  329
 MT=1   SUM OF PARTIAL CROSS SECTIONS FROM 2.25 TO 100 KEV.       9228 1451  330
   0.10 to 20 Mev, obtained from a covariance analysis of         9228 1451  331
   available experimental data, using an initial or prior cross   9228 1451  332
   section from the coupled-channel optical model analysis.       9228 1451  333
   Experimental data used include [Fo71], [Ve80], [Bo72], [Po81], 9228 1451  334
   [Gr73], [Sc74], [Po83], [Pe60], [Wh65], [Ca73], and [Br58].    9228 1451  335
   The GLUCS code was used for analysis [He80].                   9228 1451  336
 MT=2   UNCHANGED FROM VERSION 5 FROM 2.25 TO 100 KEV.            9228 1451  337
   0.12 to 20 MeV, based on subtraction of (MT=4,16,17,18,37,102) 9228 1451  338
   from MT=1.                                                     9228 1451  339
 MT=18  2.2 to 120 keV: average values from simultaneous          9228 1451  340
   evaluation of W.P. Poenitz with structure carried over from    9228 1451  341
   version 5.  Renormalizaion was over 3 ranges per decade.       9228 1451  342
   0.10 to 20 MeV: standards evaluation by CSEWG Standards        9228 1451  343
   Committee.                                                     9228 1451  344
                                                                  9228 1451  345
 ---------------------------------------------------------------- 9228 1451  346
 REFERENCES                                                       9228 1451  347
                                                                  9228 1451  348
 [Ar88] E.D. Arthur, Los Alamos National Laboratory report        9228 1451  349
    LA-UR-88-382 (1988)                                           9228 1451  350
 [Bo72] K. Boeckhoff et al., J.Nuc.En. 26, 91 (1972)              9228 1451  351
 [Br58] A. Bratenahl et al., Phys.Rev. 110, 927 (1958)            9228 1451  352
 [Ca73] J. Cabe et al., report CEA-R-4524 (1973)                  9228 1451  353
 [Du70] C.L. Dunford, report AI-AEC-12931 (1970)                  9228 1451  354
 [En89] T.R. England et al, Los Alamos National Laboratory        9228 1451  355
    reports LA-11151-MS(88), LA-11534T(89); LAUR-88-4118 to be    9228 1451  356
    published in Nucl.Sci.Eng. (1989)                             9228 1451  357
 [Fo71] D. Foster and D. Glasgow, Phys.Rev. C 3, 576 (1971)       9228 1451  358
 [Fr86] J. Frehaut, report NEANDC(E) 238/L (1986)                 9228 1451  359
 [Gr73] L. Green et al., report USNDC-9 (1973) p.170              9228 1451  360
 [He80] D. Hetrick and C.Y. Fu, Oak Ridge National Laboratory     9228 1451  361
    report ORNL/TM-7341 (1980)                                    9228 1451  362
 [Ku70] P.D. Kunz, "DWUCK: A Distorted-Wave Born Approximation    9228 1451  363
    Program," unpublished report                                  9228 1451  364
 [Ma88] D.G.Madland, Nuclear Data for Science and Technology,     9228 1451  365
    Proc. Int. Conf., Mito, Japan, May 30-June 3, 1988, Mito,     9228 1451  366
    Japan. (Saikon Publishing, 1988) p.759                        9228 1451  367
 [Pe60] J. Peterson et al., Phys.Rev. 120, 521 (1960)             9228 1451  368
 [Pe69] R.J. Peterson, Ann.Phys. 53, 40 (1069)                    9228 1451  369
 [Po81] W. Poenitz et al., Nuc.Sci.Eng. 78, 333 (1981)            9228 1451  370
 [Po83] W. Poenitz et al., Argonne National Laboratory report     9228 1451  371
    ANL-NDM-80 (1983)                                             9228 1451  372
 [Ra70] J. Raynal, report IAEA SMR-9/8 (1972) p.281               9228 1451  373
 [Sc74] R. Schwartz et al., Nuc.Sci.Eng. 54, 322 (1974)           9228 1451  374
 [Ut66] C. Uttley et al., Paris Conf. (1966) v1, p165             9228 1451  375
 [Ve80] V. Vertebnyj et al., report YFI-16,8(1973)                9228 1451  376
 [Wh65] W. Whalen et al., Argonne National Laboratory report      9228 1451  377
    ANL-7110 (1965) p.15                                          9228 1451  378
 [Yo77] P.G. Young and E.D. Arthur, Los Alamos National           9228 1451  379
    Laboratory report LA-6947 (1977).                             9228 1451  380
 [Yo88] P.G. Young and E.D. Arthur, Nuclear Data for Science and  9228 1451  381
    Technology, Proc. Int. Conf., Mito, Japan, May 30-June 3,     9228 1451  382
    1988, Mito, Japan. (Saikon Publishing, 1988) p.603            9228 1451  383
                                                                  9228 1451  384
 *****************************************************************9228 1451  385
                                                                  9228 1451  386
                                                                  9228 1451  387
                                                                  9228 1451  388
                                                                  9228 1451  389
 ************************ C O N T E N T S *********************** 9228 1451  390
 ***************** Program LINEAR (VERSION 2002-1) ***************9228 1451  391
 For All Data Greater than 1.0000E-10 barns in Absolute Value     9228 1451  392
 Data Linearized to Within an Accuracy of .100000000 per-cent     9228 1451  393
 ***************** Program RECENT (VERSION 2002-1) ***************9228 1451  394
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9228 1451  395
 Data Linearized to within an Accuracy of .100000000 per-cent     9228 1451  396
 ***************** Program SIGMA1 (VERSION 2002-1) ***************9228 1451  397
 Data Doppler Broadened to 300.000000 Kelvin                      9228 1451  398
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9228 1451  399
 Data Linearized to Within an Accuracy pf .100000000 per-cent     9228 1451  400
 ***************** Program FIXUP (Version 2002-1) ****************9228 1451  401
 Corrected ZA/AWR in All Sections-----------------------------Yes 9228 1451  402
 Corrected Thresholds-----------------------------------------Yes 9228 1451  403
 Extended Cross Sections to 20 MeV----------------------------No  9228 1451  404
 Allow Cross Section Deletion---------------------------------No  9228 1451  405
 Allow Cross Section Reconstruction---------------------------No  9228 1451  406
 Make All Cross Sections Non-Negative-------------------------Yes 9228 1451  407
 Delete Energies Not in Ascending Order-----------------------Yes 9228 1451  408
 Deleted Duplicate Points-------------------------------------Yes 9228 1451  409
 Check for Ascending MAT/MF/MT Order--------------------------Yes 9228 1451  410
 Check for Legal MF/MT Numbers--------------------------------Yes 9228 1451  411
 Allow Creation of Missing Sections---------------------------No  9228 1451  412
 Allow Insertion of Energy Points-----------------------------No  9228 1451  413
 Create Uniform Energy Grid-----------------------------------No  9228 1451  414
 Delete Section if Cross Section =0 at All Energies-----------Yes 9228 1451  415
 ***************** Program GROUPIE (VERSION 2002-1) **************9228 1451  416
 Unshielded Group Averages Using  640 Groups                      9228 1451  417
 Weighting Spectrum: Flat (Constant) Spectrum                     9228 1451  418
                                1        451        422          69228 1451  419
                                2        151          4          69228 1451  420
                                3         18        217          29228 1451  421
                               33         18         53          19228 1451  422
                                                                  9228 1  099999
                                                                  9228 0  0    0
 9.22350E+4 2.33024E+2          0          0          1          09228 2151    1
 9.22350E+4 1.00000E+0          0          0          1          09228 2151    2
 1.00000E-5 2.25000E+3          0          0          0          09228 2151    3
 3.50000E+0 9.60200E-1          0          0          0          09228 2151    4
                                                                  9228 2  099999
                                                                  9228 0  0    0
 9.22350E+4 2.33024E+2          0          0          0          09228 3 18    1
 1.93720E+8 1.93720E+8          0          0          1        6419228 3 18    2
        641          1                                            9228 3 18    3
 .000100000 9805.44565 .000105000 9576.58959 .000110000 9359.172989228 3 18    4
 .000115000 9158.81971 .000120000 8924.60065 .000127500 8664.732699228 3 18    5
 .000135000 8427.28509 .000142500 8209.06581 .000150000 7972.884059228 3 18    6
 .000160000 7726.83530 .000170000 7502.95387 .000180000 7297.437119228 3 18    7
 .000190000 7106.20951 .000200000 6931.59545 .000210000 6767.315239228 3 18    8
 .000220000 6614.73347 .000230000 6472.96795 .000240000 6306.559359228 3 18    9
 .000255000 6123.66483 .000270000 5982.52302 .000280000 5825.396019228 3 18   10
 .000300000 5633.76253 .000320000 5460.23314 .000340000 5301.297839228 3 18   11
 .000360000 5154.89776 .000380000 5021.23541 .000400000 4881.864359228 3 18   12
 .000425000 4739.23564 .000450000 4608.94667 .000475000 4489.456319228 3 18   13
 .000500000 4377.06284 .000525000 4274.34196 .000550000 4177.297809228 3 18   14
 .000575000 4087.03116 .000600000 3994.50545 .000630000 3899.312979228 3 18   15
 .000660000 3812.19928 .000690000 3728.62825 .000720000 3639.695339228 3 18   16
 .000760000 3544.32250 .000800000 3455.75135 .000840000 3374.564279228 3 18   17
 .000880000 3297.39250 .000920000 3226.63610 .000960000 3158.862739228 3 18   18
 .001000000 3088.58871 .001050000 3015.21513 .001100000 2946.416769228 3 18   19
 .001150000 2883.00805 .001200000 2808.19450 .001275000 2725.942999228 3 18   20
 .001350000 2650.71743 .001425000 2580.49435 .001500000 2505.864519228 3 18   21
 .001600000 2427.81125 .001700000 2356.53647 .001800000 2290.600769228 3 18   22
 .001900000 2230.35443 .002000000 2174.48226 .002100000 2122.043409228 3 18   23
 .002200000 2074.01496 .002300000 2028.08069 .002400000 1975.639259228 3 18   24
 .002550000 1917.33528 .002700000 1871.70821 .002800000 1822.088059228 3 18   25
 .003000000 1760.97131 .003200000 1705.32414 .003400000 1654.419039228 3 18   26
 .003600000 1607.99265 .003800000 1565.14127 .004000000 1520.490199228 3 18   27
 .004250000 1475.15152 .004500000 1433.80806 .004750000 1395.182699228 3 18   28
 .005000000 1359.72924 .005250000 1326.84435 .005500000 1295.742349228 3 18   29
 .005750000 1267.21002 .006000000 1237.23029 .006300000 1207.238559228 3 18   30
 .006600000 1178.79652 .006900000 1152.32374 .007200000 1123.623289228 3 18   31
 .007600000 1093.00492 .008000000 1065.01491 .008400000 1038.751729228 3 18   32
 .008800000 1014.31842 .009200000 991.628105 .009600000 970.0474319228 3 18   33
 .010000000 947.719780 .010500000 924.123851 .011000000 902.5498069228 3 18   34
 .011500000 881.968820 .012000000 858.377920 .012750000 832.2540279228 3 18   35
 .013500000 808.046326 .014250000 785.825850 .015000000 762.1113209228 3 18   36
 .016000001 737.201126 .017000001 714.343317 .017999999 693.4602519228 3 18   37
 .018999999 674.247444 .020000000 656.207027 .021000000 639.6710829228 3 18   38
 .022000000 624.062750 .023000000 609.484077 .024000000 592.3042479228 3 18   39
 .025500000 573.671892 .027000001 558.869598 .028000001 542.7086499228 3 18   40
 .029999999 522.732344 .032000002 504.440711 .034000002 487.6563799228 3 18   41
 .035999998 472.255930 .037999999 457.986634 .039999999 443.0352159228 3 18   42
 .042500000 427.789733 .045000002 413.809066 .047499999 400.7416609228 3 18   43
 .050000001 388.666130 .052499998 377.437964 .055000000 366.7721629228 3 18   44
 .057500001 356.975025 .059999999 346.658820 .063000001 336.3192579228 3 18   45
 .066000000 326.567189 .068999998 317.474766 .071999997 307.6173299228 3 18   46
 .075999998 297.063784 .079999998 287.441943 .083999999 278.4211999228 3 18   47
 .088000000 270.063384 .092000000 262.378406 .096000001 255.0731149228 3 18   48
 .100000001 247.618727 .104999997 239.782344 .109999999 232.7116519228 3 18   49
 .115000002 226.023391 .119999997 218.531499 .127499998 210.3819449228 3 18   50
 .135000005 203.246366 .142499998 196.997225 .150000006 190.7646869228 3 18   51
 .159999996 184.898339 .170000002 180.357774 .180000007 177.1051079228 3 18   52
 .189999998 175.126287 .200000003 174.462125 .209999993 175.1938609228 3 18   53
 .219999999 177.178431 .230000004 180.252611 .239999995 185.0329859228 3 18   54
 .254999995 190.769754 .270000011 193.939661 .280000001 193.1709989228 3 18   55
 .300000012 184.231407 .319999993 168.852362 .340000004 151.7589049228 3 18   56
 .360000014 135.928082 .379999995 122.589373 .400000006 110.5176789228 3 18   57
 .425000012 99.9215048 .449999988 91.5947961 .474999994 84.94332229228 3 18   58
 .500000000 79.5238600 .524999976 75.0078680 .550000012 71.20982789228 3 18   59
 .574999988 67.9934101 .600000024 65.0089965 .629999995 62.28403759228 3 18   60
 .660000026 60.0415616 .689999998 58.2212189 .720000029 56.58891869228 3 18   61
 .759999990 55.3543587 .800000012 54.8208531 .839999974 55.12350979228 3 18   62
 .879999995 56.4393925 .920000017 59.2267685 .959999979 64.23533029228 3 18   63
 1.00000000 74.2339430 1.04999995 92.4090720 1.10000002 106.6311909228 3 18   64
 1.14999998 84.1961980 1.20000005 40.5506560 1.27499998 23.32765609228 3 18   65
 1.35000002 18.9406099 1.42499995 16.6043776 1.50000000 15.48397319228 3 18   66
 1.60000002 14.7261739 1.70000005 14.1849222 1.79999995 13.86143009228 3 18   67
 1.89999998 15.5494953 2.00000000 22.6032031 2.09999990 13.26896039228 3 18   68
 2.20000005 11.8173435 2.29999995 11.1169809 2.40000010 10.19335919228 3 18   69
 2.54999995 8.62381024 2.70000005 10.1648690 2.79999995 19.79615379228 3 18   70
 3.00000000 41.6625435 3.20000005 23.3431674 3.40000010 43.65022679228 3 18   71
 3.59999990 36.2943279 3.79999995 2.85022773 4.00000000 3.174980859228 3 18   72
 4.25000000 3.85193210 4.50000000 4.72371501 4.75000000 12.31006079228 3 18   73
 5.00000000 6.82445083 5.25000000 13.2267853 5.50000000 16.76028149228 3 18   74
 5.75000000 17.0446690 6.00000000 42.0229076 6.30000019 61.81895219228 3 18   75
 6.59999990 6.06136848 6.90000010 47.1281131 7.19999981 6.296274059228 3 18   76
 7.59999990 3.13158452 8.00000000 10.2897118 8.39999962 245.1606749228 3 18   77
 8.80000019 206.950433 9.19999981 68.4065317 9.60000038 25.68573689228 3 18   78
 10.0000000 23.9732579 10.5000000 13.3149403 11.0000000 13.29925449228 3 18   79
 11.5000000 33.1829564 12.0000000 113.363678 12.7500000 23.18694299228 3 18   80
 13.5000000 65.5441042 14.2500000 24.7410127 15.0000000 21.58862779228 3 18   81
 16.0000000 37.0450220 17.0000000 14.7065015 18.0000000 38.46404379228 3 18   82
 19.0000000 187.981636 20.0000000 30.3272760 21.0000000 43.55740589228 3 18   83
 22.0000000 19.9103987 23.0000000 67.9364956 24.0000000 47.81544969228 3 18   84
 25.5000000 44.6604029 27.0000000 37.5121468 28.0000000 11.47197099228 3 18   85
 30.0000000 21.2250310 32.0000000 48.1749933 34.0000000 153.0713249228 3 18   86
 36.0000000 11.8018034 38.0000000 49.6850700 40.0000000 32.98915849228 3 18   87
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 1.141800-5 5.553546-6 9.669227-6 3.160813-5 1.991877-5 1.359895-5922833 18   51
 6.513847-6 1.172085-5 5.091886-5 2.121602-5 9.574444-6 1.525340-5922833 18   52
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                                                                  922833  099999
                                                                  9228 0  0    0
                                                                     0 0  0    0
 9.22380E+4 2.36005E+2          0          1         34          49237 1451    1
 0.0        1.00000E+0          0          0          0          69237 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20029237 1451    3
 3.00000E+2 0.0                 1          0        423          69237 1451    4
 92-U -238 ORNL+,JAER EVAL-NOV89 L.W.WESTON ET AL.,Y.KANDA ET AL. 9237 1451    5
                      DIST-OCT98 REV3-FEB97            19981007   9237 1451    6
----IRDF-2002         MATERIAL 9237         REVISION 3            9237 1451    7
-----INCIDENT NEUTRON DATA                                        9237 1451    8
------ENDF-6 FORMAT                                               9237 1451    9
Relative covariances MF33 MT102 in the energy range up to 100 eV  9237 1451   10
were increased to account for the systematic difference between   9237 1451   11
the present ENDF/B-VI value of 2.718 barns and the newly          9237 1451   12
recommended value of 2.683 barns for the thermal capture cross    9237 1451   13
section. The correction amounts to ((2.718-2.683)/2.683)**2.      9237 1451   14
Ref.: A.Trkov et al: Re-visiting the U-238 Thermal Capture Cross  9237 1451   15
Section and Gamma-ray Emission Probabilities of Np-239 Decay,     9237 1451   16
to be published in Nuclear Science and Engineering, 2005.         9237 1451   17
******************************************************************9237 1451   18
 92-U -238 ORNL,LANL+ EVAL-NOV89 L.W.WESTON,P.G.YOUNG,W.POENITZ   9237 1451   19
                      DIST-OCT98 REV3-FEB97            19981007   9237 1451   20
----ENDF/B-VI         MATERIAL 9237         REVISION 3            9237 1451   21
*****************EXTRACT FOR SPECIAL PURPOSE FILE*****************9237 1451   22
DOSIMETRY                                                         9237 1451   23
******************************************************************9237 1451   24
 92-U -238 KYU,JAERI+ EVAL-MAR94 Y.KANDA ET AL.                   9237 1451   25
                      DIST-JUL98                                  9237 1451   26
----JENDL/D-99        MATERIAL 9237                               9237 1451   27
                                                                  9237 1451   28
 <DOSIMETRY CROSS SECTION>                                        9237 1451   29
      U -238 FISSION                                              9237 1451   30
 **************************************************************** 9237 1451   31
                                                                  9237 1451   32
 ENDF/B-VI MOD 4 Revision, February 1997, V.McLane (NNDC)         9237 1451   33
                                                                  9237 1451   34
 MT=1 changes                                                     9237 1451   35
    MF=451: Updated comments, references.                         9237 1451   36
    MF=455: Corrected TAB1 bookkeeping (minor revision).          9237 1451   37
 MT=2 changes                                                     9237 1451   38
    MF=151                                                        9237 1451   39
      Added l-dependent scattering radius equal to scattering     9237 1451   40
        radius for resolved region.                               9237 1451   41
      Corrected energy upper limit in unresolved region.          9237 1451   42
                                                                  9237 1451   43
 **************************************************************** 9237 1451   44
                                                                  9237 1451   45
 ENDF/B-VI MOD 3 Revision, January 1993, L. Weston (ORNL)         9237 1451   46
                                                                  9237 1451   47
 MF=2 changes                                                     9237 1451   48
    Resolved region (to 10 keV): Replaces the preliminary         9237 1451   49
      evaluation of Moxon and Sowerby with the final version      9237 1451   50
      [Mo??].                                                     9237 1451   51
    Unresolved region: Uses Froehner's evaluation.                9237 1451   52
                                                                  9237 1451   53
 **************************************************************** 9237 1451   54
                                                                  9237 1451   55
 ENDF/B-VI MOD 2 Revision 1, January 1991 (NNDC)                  9237 1451   56
                                                                  9237 1451   57
   Covariance files for total, elastic scattering, fission and    9237 1451   58
 capture cross sections removed, since the correct files were and 9237 1451   59
 still are not yet available.                                     9237 1451   60
                                                                  9237 1451   61
 **************************************************************** 9237 1451   62
                                                                  9237 1451   63
 ENDF/B-VI MOD 1 Evaluation, November 1989 (ORNL, LANL, ANL)      9237 1451   64
                                                                  9237 1451   65
 Principal evaluators                                             9237 1451   66
 --------------------                                             9237 1451   67
 RESOLVED RESONANCE REGION:    (10-5 to 10,000 eV)                9237 1451   68
    M.G.Sowerby and M. C. Moxon (Harwell)                         9237 1451   69
 UNRESOLVED RESONANCE REGION:  (10 TO 149 keV)                    9237 1451   70
    F.H.Froehner(KFK) and W.P.Poenitz(ANL)                        9237 1451   71
 REACTIONS ABOVE 149 keV:                                         9237 1451   72
    MODEL CODE CALCULATIONS: (LANL)-P.G.Young and R.E.MacFarlane  9237 1451   73
    FISSION: W.P.Poenitz(ANL)                                     9237 1451   74
 NU-BAR DELAYED AND DELAYED  NEUTRON SPECTRA:                     9237 1451   75
    KAISER AND CARPENTER (Ka78)                                   9237 1451   76
 GAMMA PRODUCTION FILES: R. HOWERTON (LLL)                        9237 1451   77
 UNCERTAINTY FILES: NOT YET AVAILABLE                             9237 1451   78
                                                                  9237 1451   79
 ---------------------------------------------------------------- 9237 1451   80
                                                                  9237 1451   81
 ENDF/B-VI EVALUATION ABOVE THE UNRESOLVED RESONANCE REGION       9237 1451   82
             P.G.Young and R.E.MacFarlane (LANL)                  9237 1451   83
              Updated by R.Q. Wright (ORNL)                       9237 1451   84
                                                                  9237 1451   85
   Above the unresolved resonance region, new evaluations were    9237 1451   86
 performed of the neutron total, (n,2n), (,n,3n), (n,4n), (n,f),  9237 1451   87
 (n,nf), (n,2nf), (n,3nf), and (n,gamma) cross sections as well as9237 1451   88
 prompt nubar.  The elastic and inelastic data from ENDF/B-V were 9237 1451   89
 carried over for Version VI.                                     9237 1451   90
   To provide the new data, coupled channel optical model calcu-  9237 1451   91
 lations were performed with the ECIS code (Ra70) for the lowest  9237 1451   92
 3 members of the U238 ground state rotational band. These calcu- 9237 1451   93
 lations were used to provide initial (prior) values for a covar- 9237 1451   94
 iance analysis of the total cross section and to provide neutron 9237 1451   95
 transmission coefficients for nuclear reaction theory            9237 1451   96
 calculations with the GNASH (Ar88,Yo77) and COMNUC (Du70) Hauser-9237 1451   97
 Feshbach statistical/fission/preequilibrium codes.  These theory 9237 1451   98
 calculations were used to provide the MF=6 neutron distributions 9237 1451   99
 from the (n,2n), (n,3n), and (n,4n) reactions as well as prior   9237 1451  100
 values for covariance analyses of the cross sections for those   9237 1451  101
 reactions.  Additionally, the above analyses plus DWBA calcu-    9237 1451  102
 lations were used to check the ENDF/B-V evaluation of elastic    9237 1451  103
 and inelastic scattering.  While some differences were found,    9237 1451  104
 the earlier work was generally found to be reliable, and we      9237 1451  105
 decided to carry over the ENDF/B-V data because of the effort    9237 1451  106
 taken to match experimental data, both at lower energies and at  9237 1451  107
 14 MeV.                                                          9237 1451  108
                                                                  9237 1451  109
 MF=1 DESCRIPTIVE INFORMATION                                     9237 1451  110
                                                                  9237 1451  111
 MF=2 RESONANCE PARAMETERS (Updated for MOD 3)                    9237 1451  112
    MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS           9237 1451  113
       RESOLVED RESONANCE PARAMETERS (1.0E-5 eV to 10.0 keV)      9237 1451  114
         Reich-Moore analysis from new evaluation by Moxon and    9237 1451  115
           Sowerby [1].  Present parameters are a preliminary set 9237 1451  116
           due to use of preliminary capture yield data of        9237 1451  117
           Macklin et al. [2].  Parameters above 4.0 kev corrected9237 1451  118
            for background and normalisation errors in [2].       9237 1451  119
         Parameters 0f the bound resonances evaluated so as to    9237 1451  120
           reproduce the following values at 2200m/s              9237 1451  121
                                                                  9237 1451  122
          Reaction    Cross section (barns)    Reference          9237 1451  123
           Elastic            9.38               [3]              9237 1451  124
           Fission           11.0E-6             [4]              9237 1451  125
           Capture            2.708              [5],[6]          9237 1451  126
       RESOLVED RESONANCE RANGE (10.0 to 149 keV)                 9237 1451  127
         Coherent calculation of point cross sections and of      9237 1451  128
          energy-dependent average resonance parameters from      9237 1451  129
          evaluated average resonance parameters for E = 0 with   9237 1451  130
          Hauser-Feshbach code FITACS [7]                         9237 1451  131
         In the unresolved region the point cross sections given  9237 1451  132
          in MF=3 are considered as correct.  The unresolved      9237 1451  133
          parameters in MF=2 are only to be used for self-        9237 1451  134
          shielding calculations.  The use of the parameters with 9237 1451  135
          ENDF processing codes does not lead to cross sections   9237 1451  136
          consistent with MF=3 as the codes use a more primative  9237 1451  137
          version of the formalism.                               9237 1451  138
         Cross-sections used to determine the parameters          9237 1451  139
           TOTAL: determined mainly by the following data.        9237 1451  140
             below 45 keV: Uttley et al. [19], Byoun et al. [20], 9237 1451  141
                  Kononov and Poletaev [9], Tsubone et al. [8],   9237 1451  142
             above 45 keV: Smith et al. [10]                      9237 1451  143
           ELASTIC SCATTERING:                                    9237 1451  144
             Calculated as (total)-(partial cross-sections)       9237 1451  145
           TOTAL INELASTIC AND INELASTIC LEVELS MT=51 AND 52      9237 1451  146
             Determined mainly by the following data:             9237 1451  147
             Winters et al. [11], Murzin et al. [12], Tsang and   9237 1451  148
             Brugger [13], Smith [14], with level scheme from     9237 1451  149
             Table of Isotopes [15]                               9237 1451  150
               Level No.  Energy(MeV)    Spin-parity              9237 1451  151
                  G.S.     0.0              0+                    9237 1451  152
                   1       0.0448           2+                    9237 1451  153
                   2       0.1484           4+                    9237 1451  154
                   3       0.3072           6+                    9237 1451  155
           FISSION                                                9237 1451  156
             Extrapolated downward from JEF-1.                    9237 1451  157
           CAPTURE CROSS-SECTION                                  9237 1451  158
             Determined mainly by the post-1966 data compiled by  9237 1451  159
             Poenitz [16], by the measurement of Kazakov [17] and 9237 1451  160
             by the mean parameters (radiation width, level       9237 1451  161
             density) extracted from resolved resonance           9237 1451  162
             parameters [7].                                      9237 1451  163
                                                                  9237 1451  164
   2200 M/S VALUES AND RESONANCE INTEGRALS GIVEN BY EVALUATION    9237 1451  165
                                                                  9237 1451  166
                   2200m/s values   Resonance Integral            9237 1451  167
                       (barns)         (barns)                    9237 1451  168
        Total          12.32            597.4                     9237 1451  169
        Elastic         9.60            319.4                     9237 1451  170
        Fission         6.46E-05          1.7E-03                 9237 1451  171
        Capture         2.72            278.0                     9237 1451  172
                                                                  9237 1451  173
 ---------------------------------------------------------------- 9237 1451  174
 REFERENCES FOR MF=2                                              9237 1451  175
                                                                  9237 1451  176
  1. M.C. Moxon and M.G. Sowerby, Pr0c 1988 Int.Reac.Phys.Conf.   9237 1451  177
     Jackson Hole (1988) Vol.1, p,281                             9237 1451  178
  2. R.L. Macklin et al, Conf. 1988 Mito, Japan, (1988) p.71      9237 1451  179
  3. S.F. Mughabghab, Neutron Cross Sections, Vol.1, Part B,      9237 1451  180
     Z=61-100 (Academic Press, 1984)                              9237 1451  181
  4. P. d'Hondt et al, Ann.Nucl.EN., 11, 485 (1984)               9237 1451  182
  5. W.P. Poenitz, report IAEA-TECDOC-335 (1985) p.426 and        9237 1451  183
     private communication (1987)                                 9237 1451  184
  6. A.D. Carlson et al, Proc.Conf. 1985 Santa Fe, Vol.2, p.1429  9237 1451  185
     (1985)                                                       9237 1451  186
  7. F.H. Froehner, PROC 1988 INT.REAC.PHYS. CONF., Jackson Hole  9237 1451  187
     (1988) Vol.III, p 171                                        9237 1451  188
  8. I. Tsubone et al, Nucl.Sci.Eng. 88, 579 (1984)               9237 1451  189
  9. V.N. Kononov and E.D. Poletaev, 1973  KIEV CONF 2, 199 (1984)9237 1451  190
 10. A.B. Smith et al, private communication (1988)               9237 1451  191
 11. R.R. Winters et al, Nucl.Sci.Eng. 78, 147 (1981)             9237 1451  192
 12. A.W. Murzin et al, Yad.Konst. 4, 30 (1986)                   9237 1451  193
 13. F.Y. Tsang and R.M. Brugger, Nucl.Sci.Eng. 65, 70 (1978)     9237 1451  194
 14. A.B. Smith, report INDC/P(84)-28, unpublished (1984)         9237 1451  195
 15. C.M. Lederer, Ed., Table of Isotopes, 7th edition, (1978)    9237 1451  196
 16. W.P. Poenitz et al, Argonne National Lab. report ANL-83-4    9237 1451  197
     suppl. (1983)                                                9237 1451  198
 17. L.E. Kazakov et al, Yad.Konst. 3, 37 (1986)                  9237 1451  199
 18. F.C. Difilippo et al, Phys.Rev.C 21, 1400 (1980)             9237 1451  200
 19. C.A. Uttley et al., Nucl.Data for Reactors, Proc.Int.Conf.   9237 1451  201
     Paris 1966 (IAEA, 1966) Vol.I, p.165                         9237 1451  202
 20. T.Y. Byoun et al., PROC.MEET. REACTOR PHYS. AND SHIELD CALC.,9237 1451  203
     Kiamesha Lake, NY, 1972 (U.S.Nucl.Reg.Comm., 1972) Vol.1,    9237 1451  204
     p.1115                                                       9237 1451  205
                                                                  9237 1451  206
 MF=3 SMOOTH CROSS SECTIONS                                       9237 1451  207
    MT=102 Radiative Capture Cross Section.  10 to 149 keV,       9237 1451  208
       evaluation by F.H. Froehner (KFK) which is based on FITACS 9237 1451  209
       fit to the experimental data.  0.15 to 20 MeV, taken       9237 1451  210
       directly from simultaneous standards analysis [Ca85],      9237 1451  211
       [Po89].                                                    9237 1451  212
                                                                  9237 1451  213
 ---------------------------------------------------------------- 9237 1451  214
 REFERENCES                                                       9237 1451  215
                                                                  9237 1451  216
 [Al61] K. Allen et al., J.Nuc.En. 14, 100 (1961)                 9237 1451  217
 [An58] G. Antropov et al., At.En. 5, 456 (1958)                  9237 1451  218
 [Ar88] E.D. Arthur, Los Alamos National Lab. report LA-UR-88-382 9237 1451  219
    (1988)                                                        9237 1451  220
 [Ba66] D. Barr, Los Aalamos National Lab., private communication 9237 1451  221
    to R.Howerton (1966)                                          9237 1451  222
 [Ba65] R. Batchelor et al., Nuc.Phys. 65, 236 (1965)             9237 1451  223
 [Br58] A. Bratenahl et al., Phys.Rev. 110, 927 (1958)            9237 1451  224
 [Ca73] J. Cabe et al., CEN Saclay report CEA-R-4524 (1973)       9237 1451  225
 [Ca85] A. Carlson et al., Nucl. Data for Basic & Applied Science,9237 1451  226
       Proc.Conf., Santa Fe, NM 1985 [] p.1429.                   9237 1451  227
 [Di80] F.C. Difillippo et al., Phys.Rev.C 21, 1400 (1980)        9237 1451  228
 [Du70] C.L. Dunford, Atomics Int. report AI-AEC-12931 (1970)     9237 1451  229
 [Fo71] D. Foster and D. Glasgow, Phys.Rev.C 3, 576 (1971)        9237 1451  230
 [Fr80a] J. Frehaut et al., Nucl.Sci.Eng. 74, 29 (1980)           9237 1451  231
 [Fr80b] J. Frehaut et al., Brookhaven National Lab. report       9237 1451  232
    BNL-NCS-512457 (1980) p.399                                   9237 1451  233
 [Fr86] J. Frehaut, NEANDC(E) 238/L (1986)                        9237 1451  234
 [Ha73] S. Hayes et al., Nuc.Sci.Eng. 50, 243 (1973)              9237 1451  235
 [He80] D. Hetrick and C.Y. Fu, Oak Ridge National Lab. report    9237 1451  236
    ORNL/TM-7341 (1980)                                           9237 1451  237
 [Ka78] R. Kaiser and S. Carpenter (ANL-West) private             9237 1451  238
    communication (1978).                                         9237 1451  239
 [Ko80] N. Kornilov et al., report ZFK-410 (1980) p.68            9237 1451  240
 [La73] J. Landrum et al., Phys.Rev.C 8, 1938 (1973)              9237 1451  241
 [Li79] P. Lisowski et al., (LANL WNR measurement) private        9237 1451  242
    communication (1979)                                          9237 1451  243
 [Ma69] D. Mather, report AWRE-O-47 (1969)                        9237 1451  244
 [Ma72] D. Mather et al., report AWRE-O-72 (1972).                9237 1451  245
 [Pe60] J. Peterson et al., Phys.Rev. 120, 521 (1960)             9237 1451  246
 [Pe61] J. Perkin, J.Nuc.En. 14, 69 (1961)                        9237 1451  247
 [Ph56] J. Phillips, report AERE-NP/R-2033 (1956)                 9237 1451  248
 [Po81] W. Poenitz et al., Nuc.Sci.Eng. 78, 333 (1981)            9237 1451  249
 [Po83] W.Poenitz et al., Argonne National Lab. report            9237 1451  250
    ANL-NDM-80 (1983)                                             9237 1451  251
 [Po89] W. Poenitz, ANL-West, private communication (1989)        9237 1451  252
 [Ra70] J. Raynal, report IAEA SMR-9/8 (1970)                     9237 1451  253
 [Ro57] L. Rosen et al., Los Alamos National Lab. report LA-2111  9237 1451  254
    (1958)                                                        9237 1451  255
 [Ry80] T. Ryves, J.Phys.G 6, 771 (1980)                          9237 1451  256
 [Sc74] R. Schwartz et al., Nuc.Sci.Eng. 54, 322 (1974)           9237 1451  257
 [Sh78] R. Shamu et al., private communication (1978)             9237 1451  258
 [Sl77] R. Slovacek et al., Nuc.Sci.Eng. 62, 455 (1977)           9237 1451  259
 [Sm82] A. Smith et al., Argonne National Lab. report ANL/NDM-74  9237 1451  260
    (1982)                                                        9237 1451  261
 [Ut66] C. Uttley et al., Paris Conf. (1966) vol.1, p.165         9237 1451  262
 [Ve78] L. Veeser and E. Arthur, Harwell Nuc.Data Conf. (1978)    9237 1451  263
    p 1054                                                        9237 1451  264
 [Wh62] P. White et al., J.Nuc.En.A/B 16, 261 (1962)              9237 1451  265
 [Wh71] J. Whalen et al., Argonne National Lab. report ANL-7710   9237 1451  266
    (1971) p.9                                                    9237 1451  267
 [Yo77] P.G. Young and E.D. Arthur, Los Alamos National Lab.      9237 1451  268
    report LA-6947 (1977)                                         9237 1451  269
 [Yo78] Chou You-Pu, report HSJ-77091 (1978)                      9237 1451  270
                                                                  9237 1451  271
 **************************************************************** 9237 1451  272
          Modifications applied by the IRDF evaluators            9237 1451  273
          H.Vonach and S.Tagesen, IRK Vienna                      9237 1451  274
             MT=102 Capture Cross Section                         9237 1451  275
          Uncertainties from simultaneous standards analysis      9237 1451  276
          used up to En=2.3+6 ev                                  9237 1451  277
          Uncertainties for En=2.3+6 to 2.0+7 ev estimated from   9237 1451  278
          existing experimental data (1)                          9237 1451  279
          REFERENCES:                                             9237 1451  280
          1.Neutron Cross Sections, vol2, V.McLane, C.L.Dunford,  9237 1451  281
          P.F.Rose, Academic Press(1988)                          9237 1451  282
                                                                  9237 1451  283
 **************************************************************** 9237 1451  284
                                                                  9237 1451  285
 ENDF/B-V MAT 1393 Evaluation, November 1981 (ANL, LLNL)          9237 1451  286
                                                                  9237 1451  287
 Description of data carried over from ENDF/B-V                   9237 1451  288
                                                                  9237 1451  289
 Principal Evaluators:                                            9237 1451  290
  E.M.Pennington (ANL), A.B.Smith (ANL), W.P.Poenitz (ANL)        9237 1451  291
  R.Howerton (LLL) - gamma production files                       9237 1451  292
 Contributing evaluators:                                         9237 1451  293
  R.Kaiser and S.Carpenter (ANL-west) - nu-bar delayed and        9237 1451  294
   delayed neutron spectra                                        9237 1451  295
                                                                  9237 1451  296
MF = 3 smooth cross sections                                      9237 1451  297
   Cross sections above 45 kev were evaluated by A.Smith.         9237 1451  298
   more details are provided under each reaction type below. Most 9237 1451  299
   of the evaluation above 45 kev is described in ANL/NDM-32.     9237 1451  300
 ---------------------------------------------------------------- 9237 1451  301
 REFERENCES                                                       9237 1451  302
  1. R.E. Kaiser and S.G. Carpenter (ANL-west) private comm.      9237 1451  303
     (March 1978)                                                 9237 1451  304
  2. S.A. Cox, Argonne National Lab. report ANL/NDM-5 (1974)      9237 1451  305
  3. C. Besant et al, Sem. Fast Pulsed Reactors CONF-760111 (1976)9237 1451  306
  4. F. Manero and V. Konshin, At.En.Review 10, #4 (1972)         9237 1451  307
  5. M. Soleilhac, revised data received from NNCSC               9237 1451  308
  6. B. Nurpeisov et al., Sov.At.En. translation 807 (Mar 1976)   9237 1451  309
  7. G. deSaussure et al., Prog.Nucl.En. 3, 87 (1979)             9237 1451  310
  8. D. Olsen et al., Nuc.Sci.Eng. 62, 479 (1977)                 9237 1451  311
  9. P. Guenther, D. Havel, A. Smith Argonne National Lab. report 9237 1451  312
     ANL-NDM-22 (1976)                                            9237 1451  313
 10. E. Pennington, W. Poenitz, A. Smith, Trans.Am.Nucl.Soc. 26,  9237 1451  314
     591 (1977)                                                   9237 1451  315
 11. W.P. Poenitz Argonne National Lab. report ANL/NDM-45 (1979)  9237 1451  316
 12. W.P. Poenitz and A.B. Smith, ed. Argonne National Lab. report9237 1451  317
     ANL-76-90 (1976)                                             9237 1451  318
 13. R. Slovacek et al., Nucl.Sci.Eng. 62, 455 (1977)             9237 1451  319
 14. M. Caner, M. Segev, W. Yiftah, Nucl.Sci.Eng. 59, 395 (1976)  9237 1451  320
 15. E. Kujawski and L. Stewart, Trans.Am.Nucl.Soc. 24, 453 (1976)9237 1451  321
 16. L.W. Weston private comm. to B.A. Magurno Nov.12, 1982       9237 1451  322
 17. R. Sher and ?. Beck report EPRI NP-1771/81 and rev. 1/83,    9237 1451  323
     and private communication to Magurno, February 1983          9237 1451  324
                                                                  9237 1451  325
 **************************************************************** 9237 1451  326
 92-U -238 KYU,JAERI+ EVAL-MAR94 Y.KANDA ET AL.                   9237 1451  327
                      DIST-JUL98                                  9237 1451  328
----JENDL/D-99        MATERIAL 9237                               9237 1451  329
-----INCIDENT NEUTRON DATA                                        9237 1451  330
------ENDF-6 FORMAT                                               9237 1451  331
HISTORY                                                           9237 1451  332
87-01 SIMULTANEOUS EVALUATION FOR FISSION AND CAPTURE CROSS       9237 1451  333
      SECTIONS WAS COMPLETED IN THE ENERGY RANGE ABOVE 50 KEV.    9237 1451  334
93-03 FISSION SPECTRA CALCULATED BY T.OHSAWA(KINKI UNIV.)         9237 1451  335
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          9237 1451  336
98-04 COMPILED TO JENDL DOSIMETRY FILE 99.                        9237 1451  337
                                                                  9237 1451  338
            ===== POINT-WISE DATA FILE =====                      9237 1451  339
                                                                  9237 1451  340
 <DOSIMETRY CROSS SECTION>                                        9237 1451  341
      U -238 FISSION                                              9237 1451  342
                                                                  9237 1451  343
MF=1  GENERAL INFORMATION                                         9237 1451  344
  MT=451  DESCRIPTIVE DATA AND DIRECTORY RECORDS                  9237 1451  345
                                                                  9237 1451  346
                                                                  9237 1451  347
   2200-M/S CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS.    9237 1451  348
                       2200 M/S(B)     RES. INTEG.(B)             9237 1451  349
           FISSION      11.8E-6           1.72                    9237 1451  350
                                                                  9237 1451  351
 ***************** PROGRAM LINEAR (VERSION 87-1) *****************9237 1451  352
 DATA LINEARIZED TO WITHIN AN ACCURACY OF     0.800 PER-CENT      9237 1451  353
 ***************** PROGRAM RECENT (VERSION 89-1) *****************9237 1451  354
 RESONANCE CONTRIBUTION RECONSTRUCTED TO WITHIN    1.000 PER-CENT 9237 1451  355
 COMBINED DATA NOT THINNED (ALL RESONANCE + BACKGROUND DATA KEPT) 9237 1451  356
 ***************** PROGRAM LINEAR (VERSION 87-1) *****************9237 1451  357
 DATA LINEARIZED TO WITHIN AN ACCURACY OF     0.800 PER-CENT      9237 1451  358
                                                                  9237 1451  359
MF=3  NEUTRON CROSS SECTIONS                                      9237 1451  360
     BELOW 10 KEV, NO BACKGROUND CROSS SECTIONS WERE GIVEN.       9237 1451  361
     ABOVE 10 KEV, CROSS SECTIONS WERE EVALUATED AS FOLLOWS, AND  9237 1451  362
     THEY WERE REPRESENTED WITH THE UNRESOLVED RESONANCE          9237 1451  363
     PARAMETERS EXCEPT THE FISSION CROSS SECTION.                 9237 1451  364
                                                                  9237 1451  365
  MT=18  FISSION                                                  9237 1451  366
     BELOW 100 KEV : TAKEN FROM EXPERIMENTAL DATA /12/.           9237 1451  367
     100 - 600 KEV : EVALUATED ON THE BASIS OF THE DATA OF        9237 1451  368
          DIFFILIPPO ET AL. /13/, BEHRENS AND CARLSON /14/,       9237 1451  369
          NORDBORG ET AL. /15/ AND MEADOWS /16,17/.               9237 1451  370
     ABOVE 600 KEV : RESULTS OF SIMULTANEOUS EVALUATION /18/ MADE 9237 1451  371
          BY CONSIDERING THE EXPERIMENTAL DATA OF REFS./14,15,    9237 1451  372
          16,17,19,20,21,22,23,24,25,26,27,28/.                   9237 1451  373
                                                                  9237 1451  374
MF=33                                                             9237 1451  375
 MT=18   Taken from JENDL/D-99                                    9237 1451  376
                                                                  9237 1451  377
                                                                  9237 1451  378
REFERENCES                                                        9237 1451  379
12) DIFILLIPO F.C. ET AL.: NUCL. SCI. ENG., 63, 153 (1977).       9237 1451  380
13) DIFILLIPO F.C. ET AL.: NUCL. SCI. ENG., 68, 43 (1978).        9237 1451  381
14) BEHRENS J.W. AND CARLSON G.W.: NUCL. SCI. ENG., 63, 250       9237 1451  382
    (1977).                                                       9237 1451  383
15) NORDBORG C. ET AL: ANL-76-90, 128 (1976).                     9237 1451  384
16) MEADOWS J.W.: NUCL. SCI. ENG., 58, 255 (1975).                9237 1451  385
17) MEADOWS J.W.: NUCL. SCI. ENG., 49, 310 (1972).                9237 1451  386
18) KANDA Y. ET AL.: 1985 SANTA FE, 2, 1567 (1986).               9237 1451  387
19) CANCE M. AND GRENIER G.:NUCL. SCI. ENG., 68, 197 (1978).      9237 1451  388
20) BILAUD P. ET AL.:1958 GENEVA,16, 106, 5809 (1958).            9237 1451  389
21) ADAMOV V.M. ET AL.: 1977 NBS, 313 (1977).                     9237 1451  390
22) ARLT R. ET AL.: KE, 24, 48, 8102 (1981).                      9237 1451  391
23) CIERJACKS S. ET AL.:1976 ANL, 94 (1976).                      9237 1451  392
24) GOVERDOVSKII A.A. ET AL.: 1983 KIEV, 2, 159  (1983).          9237 1451  393
25) ANDROSENKO S.D. ET AL.: 1983 KIEV, 2, 153  (1983).            9237 1451  394
26) FURSOV B.I. ET AL.: SOV. ATOM. ENERG., 43, 808  (1978).       9237 1451  395
27) POENITZ W.P. AND ARMANI R.J.: J. NUCL. ENEG., 26, 483 (1972). 9237 1451  396
28) POENITZ W.P.: NUCL. SCI. ENG., 57, 300 (1975).                9237 1451  397
                                                                  9237 1451  398
 ************************ C O N T E N T S *********************** 9237 1451  399
 ***************** Program LINEAR (VERSION 2002-1) ***************9237 1451  400
 For All Data Greater than 1.0000E-10 barns in Absolute Value     9237 1451  401
 Data Linearized to Within an Accuracy of .100000000 per-cent     9237 1451  402
 ***************** Program RECENT (VERSION 2002-1) ***************9237 1451  403
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9237 1451  404
 Data Linearized to within an Accuracy of .100000000 per-cent     9237 1451  405
 ***************** Program SIGMA1 (VERSION 2002-1) ***************9237 1451  406
 Data Doppler Broadened to 300.000000 Kelvin                      9237 1451  407
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9237 1451  408
 Data Linearized to Within an Accuracy pf .100000000 per-cent     9237 1451  409
 ***************** Program FIXUP (Version 2002-1) ****************9237 1451  410
 Corrected ZA/AWR in All Sections-----------------------------Yes 9237 1451  411
 Corrected Thresholds-----------------------------------------Yes 9237 1451  412
 Extended Cross Sections to 20 MeV----------------------------No  9237 1451  413
 Allow Cross Section Deletion---------------------------------No  9237 1451  414
 Allow Cross Section Reconstruction---------------------------No  9237 1451  415
 Make All Cross Sections Non-Negative-------------------------Yes 9237 1451  416
 Delete Energies Not in Ascending Order-----------------------Yes 9237 1451  417
 Deleted Duplicate Points-------------------------------------Yes 9237 1451  418
 Check for Ascending MAT/MF/MT Order--------------------------Yes 9237 1451  419
 Check for Legal MF/MT Numbers--------------------------------Yes 9237 1451  420
 Allow Creation of Missing Sections---------------------------No  9237 1451  421
 Allow Insertion of Energy Points-----------------------------No  9237 1451  422
 Create Uniform Energy Grid-----------------------------------No  9237 1451  423
 Delete Section if Cross Section =0 at All Energies-----------Yes 9237 1451  424
 ***************** Program GROUPIE (VERSION 2002-1) **************9237 1451  425
 Unshielded Group Averages Using  640 Groups                      9237 1451  426
 Weighting Spectrum: Flat (Constant) Spectrum                     9237 1451  427
                                1        451        433          49237 1451  428
                                2        151          4          49237 1451  429
                                3         18        217          19237 1451  430
                                3        102        217          39237 1451  431
                               33         18         11          09237 1451  432
                               33        102        335          09237 1451  433
                                                                  9237 1  099999
                                                                  9237 0  0    0
 9.22380E+4 2.36005E+2          0          0          1          09237 2151    1
 9.22380E+4 1.00000E+0          0          0          1          09237 2151    2
 1.00000E-5 1.00000E+4          0          0          0          09237 2151    3
 0.0        9.42848E-1          0          0          0          09237 2151    4
                                                                  9237 2  099999
                                                                  9237 0  0    0
 9.22380E+4 2.36005E+2          0          0          0          09237 3 18    1
 1.89629E+8 1.89629E+8          0          0          1        6419237 3 18    2
        641          1                                            9237 3 18    3
 .000100000 .000184668 .000105000 .000180362 .000110000 .0001762729237 3 18    4
 .000115000 .000172502 .000120000 .000168096 .000127500 .0001632069237 3 18    5
 .000135000 .000158740 .000142500 .000154635 .000150000 .0001501939237 3 18    6
 .000160000 .000145564 .000170000 .000141353 .000180000 .0001374889237 3 18    7
 .000190000 .000133892 .000200000 .000130609 .000210000 .0001275209237 3 18    8
 .000220000 .000124650 .000230000 .000121984 .000240000 .0001188559237 3 18    9
 .000255000 .000115416 .000270000 .000112762 .000280000 .0001098089237 3 18   10
 .000300000 .000106207 .000320000 .000102945 .000340000 9.99571E-59237 3 18   11
 .000360000 9.72059E-5 .000380000 9.46943E-5 .000400000 9.20757E-59237 3 18   12
 .000425000 8.93960E-5 .000450000 8.69475E-5 .000475000 8.47028E-59237 3 18   13
 .000500000 8.25920E-5 .000525000 8.06627E-5 .000550000 7.88401E-59237 3 18   14
 .000575000 7.71450E-5 .000600000 7.54077E-5 .000630000 7.36205E-59237 3 18   15
 .000660000 7.19851E-5 .000690000 7.04164E-5 .000720000 6.87471E-59237 3 18   16
 .000760000 6.69572E-5 .000800000 6.52954E-5 .000840000 6.37724E-59237 3 18   17
 .000880000 6.23249E-5 .000920000 6.09980E-5 .000960000 5.97271E-59237 3 18   18
 .001000000 5.84097E-5 .001050000 5.70345E-5 .001100000 5.57454E-59237 3 18   19
 .001150000 5.45576E-5 .001200000 5.31564E-5 .001275000 5.16164E-59237 3 18   20
 .001350000 5.02084E-5 .001425000 4.88945E-5 .001500000 4.74987E-59237 3 18   21
 .001600000 4.60394E-5 .001700000 4.47074E-5 .001800000 4.34754E-59237 3 18   22
 .001900000 4.23502E-5 .002000000 4.13069E-5 .002100000 4.03278E-59237 3 18   23
 .002200000 3.94312E-5 .002300000 3.85737E-5 .002400000 3.75953E-59237 3 18   24
 .002550000 3.65078E-5 .002700000 3.56570E-5 .002800000 3.47323E-59237 3 18   25
 .003000000 3.35937E-5 .003200000 3.25576E-5 .003400000 3.16104E-59237 3 18   26
 .003600000 3.07471E-5 .003800000 2.99506E-5 .004000000 2.91208E-59237 3 18   27
 .004250000 2.82791E-5 .004500000 2.75109E-5 .004750000 2.67928E-59237 3 18   28
 .005000000 2.61334E-5 .005250000 2.55216E-5 .005500000 2.49428E-59237 3 18   29
 .005750000 2.44116E-5 .006000000 2.38534E-5 .006300000 2.32950E-59237 3 18   30
 .006600000 2.27684E-5 .006900000 2.22829E-5 .007200000 2.17535E-59237 3 18   31
 .007600000 2.11862E-5 .008000000 2.06673E-5 .008400000 2.01803E-59237 3 18   32
 .008800000 1.97270E-5 .009200000 1.93056E-5 .009600000 1.89046E-59237 3 18   33
 .010000000 1.84894E-5 .010500000 1.80505E-5 .011000000 1.76491E-59237 3 18   34
 .011500000 1.72663E-5 .012000000 1.68277E-5 .012750000 1.63424E-59237 3 18   35
 .013500000 1.58931E-5 .014250000 1.54812E-5 .015000000 1.50421E-59237 3 18   36
 .016000001 1.45812E-5 .017000001 1.41583E-5 .017999999 1.37719E-59237 3 18   37
 .018999999 1.34166E-5 .020000000 1.30832E-5 .021000000 1.27781E-59237 3 18   38
 .022000000 1.24907E-5 .023000000 1.22230E-5 .024000000 1.19084E-59237 3 18   39
 .025500000 1.15692E-5 .027000001 1.13006E-5 .028000001 1.10089E-59237 3 18   40
 .029999999 1.06500E-5 .032000002 1.03234E-5 .034000002 1.00257E-59237 3 18   41
 .035999998 9.75425E-6 .037999999 9.50355E-6 .039999999 9.24161E-69237 3 18   42
 .042500000 8.97539E-6 .045000002 8.73211E-6 .047499999 8.50551E-69237 3 18   43
 .050000001 8.29718E-6 .052499998 8.10449E-6 .055000000 7.92212E-69237 3 18   44
 .057500001 7.75531E-6 .059999999 7.58005E-6 .063000001 7.40522E-69237 3 18   45
 .066000000 7.24071E-6 .068999998 7.08773E-6 .071999997 6.92131E-69237 3 18   46
 .075999998 6.74264E-6 .079999998 6.57928E-6 .083999999 6.42576E-69237 3 18   47
 .088000000 6.28307E-6 .092000000 6.15099E-6 .096000001 6.02488E-69237 3 18   48
 .100000001 5.89475E-6 .104999997 5.75707E-6 .109999999 5.63137E-69237 3 18   49
 .115000002 5.51135E-6 .119999997 5.37402E-6 .127499998 5.22263E-69237 3 18   50
 .135000005 5.08266E-6 .142499998 4.95465E-6 .150000006 4.81743E-69237 3 18   51
 .159999996 4.67296E-6 .170000002 4.54092E-6 .180000007 4.42044E-69237 3 18   52
 .189999998 4.30995E-6 .200000003 4.20631E-6 .209999993 4.11165E-69237 3 18   53
 .219999999 4.02241E-6 .230000004 3.93941E-6 .239999995 3.84384E-69237 3 18   54
 .254999995 3.73714E-6 .270000011 3.65553E-6 .280000001 3.56497E-69237 3 18   55
 .300000012 3.45451E-6 .319999993 3.35535E-6 .340000004 3.26599E-69237 3 18   56
 .360000014 3.18067E-6 .379999995 3.10393E-6 .400000006 3.02593E-69237 3 18   57
 .425000012 2.94428E-6 .449999988 2.87043E-6 .474999994 2.80166E-69237 3 18   58
 .500000000 2.73988E-6 .524999976 2.68321E-6 .550000012 2.62772E-69237 3 18   59
 .574999988 2.57815E-6 .600000024 2.52624E-6 .629999995 2.47453E-69237 3 18   60
 .660000026 2.42564E-6 .689999998 2.38131E-6 .720000029 2.33401E-69237 3 18   61
 .759999990 2.28178E-6 .800000012 2.23587E-6 .839999974 2.19123E-69237 3 18   62
 .879999995 2.15172E-6 .920000017 2.11434E-6 .959999979 2.08108E-69237 3 18   63
 1.00000000 2.04424E-6 1.04999995 2.00718E-6 1.10000002 1.97269E-69237 3 18   64
 1.14999998 1.94246E-6 1.20000005 1.90602E-6 1.27499998 1.86651E-69237 3 18   65
 1.35000002 1.83288E-6 1.42499995 1.80086E-6 1.50000000 1.76880E-69237 3 18   66
 1.60000002 1.73647E-6 1.70000005 1.70830E-6 1.79999995 1.68472E-69237 3 18   67
 1.89999998 1.66301E-6 2.00000000 1.64531E-6 2.09999990 1.63059E-69237 3 18   68
 2.20000005 1.61794E-6 2.29999995 1.60871E-6 2.40000010 1.59963E-69237 3 18   69
 2.54999995 1.59324E-6 2.70000005 1.59020E-6 2.79999995 1.59329E-69237 3 18   70
 3.00000000 1.60347E-6 3.20000005 1.62120E-6 3.40000010 1.64925E-69237 3 18   71
 3.59999990 1.68712E-6 3.79999995 1.73754E-6 4.00000000 1.81176E-69237 3 18   72
 4.25000000 1.92264E-6 4.50000000 2.07439E-6 4.75000000 2.28731E-69237 3 18   73
 5.00000000 2.59737E-6 5.25000000 3.07418E-6 5.50000000 3.87484E-69237 3 18   74
 5.75000000 5.42717E-6 6.00000000 1.02457E-5 6.30000019 .0001078319237 3 18   75
 6.59999990 .001115810 6.90000010 8.67297E-6 7.19999981 1.30114E-69237 3 18   76
 7.59999990 3.80596E-7 8.00000000 2.50553E-7 8.39999962 2.58209E-79237 3 18   77
 8.80000019 2.97648E-7 9.19999981 3.43688E-7 9.60000038 3.90050E-79237 3 18   78
 10.0000000 4.40501E-7 10.5000000 4.95398E-7 11.0000000 5.49559E-79237 3 18   79
 11.5000000 6.04128E-7 12.0000000 6.76534E-7 12.7500000 7.73992E-79237 3 18   80
 13.5000000 8.90463E-7 14.2500000 1.03734E-6 15.0000000 1.27641E-69237 3 18   81
 16.0000000 1.70901E-6 17.0000000 2.53130E-6 18.0000000 4.53423E-69237 3 18   82
 19.0000000 1.29072E-5 20.0000000 .003044283 21.0000000 .0002335999237 3 18   83
 22.0000000 6.21566E-6 23.0000000 2.11257E-6 24.0000000 1.00282E-69237 3 18   84
 25.5000000 6.22895E-7 27.0000000 5.34668E-7 28.0000000 5.45691E-79237 3 18   85
 30.0000000 6.90426E-7 32.0000000 1.16027E-6 34.0000000 4.80306E-69237 3 18   86
 36.0000000 .000321611 38.0000000 6.81239E-7 40.0000000 8.15589E-89237 3 18   87
 42.5000000 7.06497E-8 45.0000000 1.10208E-7 47.5000000 1.58009E-79237 3 18   88
 50.0000000 2.13391E-7 52.5000000 2.84426E-7 55.0000000 3.90089E-79237 3 18   89
 57.5000000 5.84208E-7 60.0000000 1.21992E-6 63.0000000 .0002314589237 3 18   90
 66.0000000 .000328269 69.0000000 4.80554E-7 72.0000000 2.11524E-79237 3 18   91
 76.0000000 5.97862E-7 80.0000000 5.74436E-5 84.0000000 5.16331E-89237 3 18   92
 88.0000000 1.16773E-7 92.0000000 2.17638E-7 96.0000000 5.95206E-79237 3 18   93
 100.000000 7.71072E-5 105.000000 2.38574E-7 110.000000 8.34158E-89237 3 18   94
 115.000000 8.57761E-8 120.000000 1.03492E-7 127.500000 1.24924E-79237 3 18   95
 135.000000 1.47168E-7 142.500000 1.71946E-7 150.000000 2.09340E-79237 3 18   96
 160.000000 2.77760E-7 170.000000 4.55506E-7 180.000000 5.95252E-59237 3 18   97
 190.000000 9.40205E-6 200.000000 .000111774 210.000000 4.93613E-79237 3 18   98
 220.000000 6.74250E-8 230.000000 3.22793E-5 240.000000 6.33722E-89237 3 18   99
 255.000000 8.06979E-8 270.000000 1.08109E-7 280.000000 1.43942E-79237 3 18  100
 300.000000 2.15402E-7 320.000000 5.05216E-7 340.000000 .0001076249237 3 18  101
 360.000000 3.66765E-6 380.000000 8.82725E-8 400.000000 1.65882E-79237 3 18  102
 425.000000 2.95672E-7 450.000000 9.49531E-5 475.000000 1.21865E-59237 3 18  103
 500.000000 5.03088E-5 525.000000 7.41218E-5 550.000000 3.70682E-79237 3 18  104
 575.000000 .000220720 600.000000 1.84857E-5 630.000000 3.58844E-79237 3 18  105
 660.000000 1.60780E-6 690.000000 .003119950 720.000000 .0156989949237 3 18  106
 760.000000 1.40855E-7 800.000000 2.24445E-5 840.000000 .0003646309237 3 18  107
 880.000000 1.61614E-7 920.000000 1.63494E-8 960.000000 4.28418E-99237 3 18  108
 1000.00000 4.45165E-8 1050.00000 2.45123E-7 1100.00000 .0001542799237 3 18  109
 1150.00000 .000867571 1200.00000 .004540664 1275.00000 3.63512E-79237 3 18  110
 1350.00000 1.33179E-7 1425.00000 6.97851E-8 1500.00000 3.92568E-89237 3 18  111
 1600.00000 2.28333E-8 1700.00000 1.42444E-8 1800.00000 9.50553E-99237 3 18  112
 1900.00000 6.34242E-9 2000.00000 4.49933E-9 2100.00000 3.19030E-99237 3 18  113
 2200.00000 2.34720E-9 2300.00000 1.78264E-9 2400.00000 1.31466E-99237 3 18  114
 2550.00000 1.00839E-9 2700.00000 9.1651E-10 2800.00000 9.0786E-109237 3 18  115
 3000.00000 1.03038E-9 3200.00000 1.26485E-9 3400.00000 1.57850E-99237 3 18  116
 3600.00000 1.99590E-9 3800.00000 2.50887E-9 4000.00000 3.24264E-99237 3 18  117
 4250.00000 4.25527E-9 4500.00000 5.60104E-9 4750.00000 7.59153E-99237 3 18  118
 5000.00000 1.09465E-8 5250.00000 1.87454E-8 5500.00000 9.98495E-59237 3 18  119
 5750.00000 2.07209E-8 6000.00000 1.34150E-8 6300.00000 3.06706E-89237 3 18  120
 6600.00000 7.54352E-8 6900.00000 .000249709 7200.00000 .0004390949237 3 18  121
 7600.00000 .000403901 8000.00000 1.69908E-7 8400.00000 3.85076E-89237 3 18  122
 8800.00000 9.14997E-9 9200.00000 .000117323 9600.00000 2.39228E-89237 3 18  123
 10000.0000 6.11736E-5 10500.0000 6.87096E-5 11000.0000 7.63109E-59237 3 18  124
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 13500.0000 .000115961 14250.0000 .000127320 15000.0000 .0001306509237 3 18  126
 16000.0000 .000125950 17000.0000 .000121250 18000.0000 .0001165509237 3 18  127
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 22000.0000 9.77501E-5 23000.0000 9.30500E-5 24000.0000 8.70085E-59237 3 18  129
 25500.0000 7.76953E-5 27000.0000 6.94596E-5 28000.0000 5.95473E-59237 3 18  130
 30000.0000 4.60400E-5 32000.0000 3.27058E-5 34000.0000 2.31997E-59237 3 18  131
 36000.0000 3.32135E-5 38000.0000 4.69502E-5 40000.0000 5.40000E-59237 3 18  132
 42500.0000 5.47205E-5 45000.0000 8.93750E-5 47500.0000 9.21250E-59237 3 18  133
 50000.0000 9.48750E-5 52500.0000 9.76250E-5 55000.0000 9.66750E-59237 3 18  134
 57500.0000 9.20250E-5 60000.0000 8.69100E-5 63000.0000 8.09608E-59237 3 18  135
 66000.0000 7.05029E-5 69000.0000 5.84263E-5 72000.0000 4.51266E-59237 3 18  136
 76000.0000 4.13000E-5 80000.0000 3.02947E-5 84000.0000 1.87843E-59237 3 18  137
 88000.0000 2.01489E-5 92000.0000 3.55173E-5 96000.0000 4.21000E-59237 3 18  138
 100000.000 4.21000E-5 105000.000 4.21000E-5 110000.000 4.21000E-59237 3 18  139
 115000.000 4.21000E-5 120000.000 4.21000E-5 127500.000 4.21258E-59237 3 18  140
 135000.000 4.22353E-5 142500.000 4.68456E-5 150000.000 9.89993E-59237 3 18  141
 160000.000 9.89995E-5 170000.000 9.89996E-5 180000.000 9.89997E-59237 3 18  142
 190000.000 9.89998E-5 200000.000 9.89999E-5 210000.000 9.89998E-59237 3 18  143
 220000.000 9.84576E-5 230000.000 9.46678E-5 240000.000 8.95601E-59237 3 18  144
 255000.000 8.80000E-5 270000.000 8.80002E-5 280000.000 8.80309E-59237 3 18  145
 300000.000 9.67757E-5 320000.000 .000144495 340000.000 .0001926849237 3 18  146
 360000.000 .000212267 380000.000 .000230749 400000.000 .0002191809237 3 18  147
 425000.000 .000258449 450000.000 .000347497 475000.000 .0004024919237 3 18  148
 500000.000 .000432432 525000.000 .000526455 550000.000 .0006464019237 3 18  149
 575000.000 .000739215 600000.000 .000898255 630000.000 .0011510129237 3 18  150
 660000.000 .001448599 690000.000 .001795637 720000.000 .0023494379237 3 18  151
 760000.000 .003689601 800000.000 .005415006 840000.000 .0083797649237 3 18  152
 880000.000 .014041883 920000.000 .016609551 960000.000 .0154054559237 3 18  153
 1000000.00 .021098718 1100000.00 .035642428 1200000.00 .0492712289237 3 18  154
 1300000.00 .124624261 1400000.00 .286684114 1500000.00 .3835787879237 3 18  155
 1600000.00 .427749836 1700000.00 .469499913 1800000.00 .5102486849237 3 18  156
 1900000.00 .534698786 2000000.00 .544320453 2100000.00 .5491868679237 3 18  157
 2200000.00 .551238061 2300000.00 .550750544 2400000.00 .5489966269237 3 18  158
 2500000.00 .545950571 2600000.00 .541983212 2700000.00 .5373099049237 3 18  159
 2800000.00 .532896485 2900000.00 .530015352 3000000.00 .5286027539237 3 18  160
 3100000.00 .528407760 3200000.00 .529577983 3300000.00 .5321134219237 3 18  161
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 3700000.00 .553908158 3800000.00 .559422185 3900000.00 .5638070749237 3 18  163
 4000000.00 .566154510 4100000.00 .566464493 4200000.00 .5645515329237 3 18  164
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 4600000.00 .547448043 4700000.00 .543104014 4800000.00 .5392686529237 3 18  166
 4900000.00 .536084795 5000000.00 .533526575 5100000.00 .5309683569237 3 18  167
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 8200000.00 .996085035 8300000.00 .996678962 8400000.00 .9972728909237 3 18  178
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 8800000.00 .996680669 8900000.00 .996426616 9000000.00 .9950136459237 3 18  180
 9100000.00 .992441756 9200000.00 .989869868 9300000.00 .9872979799237 3 18  181
 9400000.00 .984726090 9500000.00 .982556185 9600000.00 .9807882649237 3 18  182
 9700000.00 .979020343 9800000.00 .977252421 9900000.00 .9754845009237 3 18  183
 10000000.0 .975160487 10100000.0 .976280382 10200000.0 .9774002779237 3 18  184
 10300000.0 .978520172 10400000.0 .979640067 10500000.0 .9807599629237 3 18  185
 10600000.0 .981879857 10700000.0 .982999752 10800000.0 .9841196479237 3 18  186
 10900000.0 .985239542 11000000.0 .985014540 11100000.0 .9834446429237 3 18  187
 11200000.0 .981874744 11300000.0 .980304846 11400000.0 .9787349489237 3 18  188
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 2.878892-7 4.897605-7 9.923790-7 2.086909-6 3.239421-6 3.618747-6923733102  169
 3.381891-6 3.364527-6 2.725278-6 2.682695-6 1.989228-7 2.118542-7923733102  170
 2.835050-7 4.540196-7 8.350671-7 1.712897-6 2.648913-6 2.833098-6923733102  171
 2.754924-6 3.387071-6 1.965278-6 2.171306-6 1.943143-7 2.058122-7923733102  172
 2.688171-7 4.151860-7 7.381307-7 1.536702-6 2.492000-6 2.881013-6923733102  173
 2.836635-6 3.093766-6 1.840185-6 2.017366-6                      923733102  174
 3.000000+0 0.000000+0       7925        102          0          1923733102  175
 0.000000+0 0.000000+0          0          6        226         15923733102  176
 1.000000-5 3.000000-1 1.000000+2 1.000000+3 1.000000+4 3.750000+4923733102  177
 9.000000+4 1.350000+5 2.050000+5 2.750000+5 4.125000+5 6.250000+5923733102  178
 9.500000+5 1.500000+6 2.300000+6 1.000000-5 3.000000-1 2.000000+3923733102  179
 1.000000+4 3.750000+4 9.000000+4 1.350000+5 2.050000+5 2.750000+5923733102  180
 4.125000+5 6.250000+5 9.500000+5 1.325000+6 1.900000+6 2.900000+6923733102  181
 1.904603-7 1.904603-7-7.019740-7-7.569720-7-6.784168-7-6.410915-7923733102  182
-6.332510-7-5.931338-7-5.921360-7-5.500066-7-4.869104-7-5.189673-7923733102  183
-5.275000-7-4.925769-7 1.904603-7 1.904603-7-7.019740-7-7.569720-7923733102  184
-6.784168-7-6.410915-7-6.332510-7-5.931338-7-5.921360-7-5.500066-7923733102  185
-4.869104-7-5.189673-7-5.275000-7-4.925769-7-2.077068-7-2.077068-7923733102  186
 4.898264-6 4.995980-6 3.949305-6 2.354107-6 1.762626-6 1.855394-6923733102  187
 1.830603-6 1.369138-6 8.822445-7 8.886017-7 2.400386-7 1.128638-7923733102  188
-2.367599-7-2.367599-7 5.955326-6 5.859049-6 4.636561-6 2.947353-6923733102  189
 2.165060-6 2.150697-6 2.164094-6 1.631786-6 1.099795-6 1.103367-6923733102  190
 3.425039-7 1.877006-7-3.172946-7-3.172946-7 6.018329-6 8.861832-6923733102  191
 5.582043-6 4.444510-6 3.255190-6 3.044139-6 2.876880-6 2.238705-6923733102  192
 1.742325-6 1.704786-6 6.865661-7 4.543919-7-3.247937-7-3.247937-7923733102  193
 6.197744-6 6.269205-6 1.150200-5 6.764391-6 4.995449-6 4.034151-6923733102  194
 3.644963-6 2.798364-6 2.241931-6 1.934477-6 9.565376-7 6.829714-7923733102  195
-3.401727-7-3.401727-7 3.647359-6 4.859471-6 7.050691-6 1.251732-5923733102  196
 6.939321-6 4.473837-6 3.908653-6 3.334621-6 2.457505-6 1.961523-6923733102  197
 8.233363-7 6.148151-7-3.575621-7-3.575621-7 2.026198-6 2.809060-6923733102  198
 4.106891-6 6.019233-6 1.183465-5 5.403999-6 3.036257-6 2.991122-6923733102  199
 1.460160-6 1.022404-6-1.422252-8 1.417935-7-3.467652-7-3.467652-7923733102  200
 2.781274-6 3.243317-6 3.904329-6 4.583747-6 6.771917-6 1.078073-5923733102  201
 5.703652-6 4.674022-6 2.675783-6 2.137674-6 1.130911-6 1.050914-6923733102  202
-3.535544-7-3.535544-7 3.000571-6 3.333089-6 3.750328-6 4.014345-6923733102  203
 4.021693-6 6.120898-6 1.515973-5 6.394111-6 4.551817-6 4.043548-6923733102  204
 3.426664-6 2.936175-6-3.765661-7-3.765661-7 1.896861-6 2.159099-6923733102  205
 2.516510-6 3.289814-6 3.677357-6 4.407419-6 5.856354-6 1.414620-5923733102  206
 5.430003-6 3.898874-6 3.341352-6 2.645717-6-4.109963-7-4.109963-7923733102  207
 1.427190-6 1.888070-6 2.404225-6 3.213500-6 3.543918-6 3.905430-6923733102  208
 4.530942-6 5.004335-6 1.389684-5 6.309738-6 5.002581-6 3.299843-6923733102  209
-4.017482-7-4.017482-7 4.377614-7 8.747613-7 1.138413-6 1.309742-6923733102  210
 1.212702-6 1.674478-6 3.613283-6 3.741159-6 5.714753-6 2.302298-5923733102  211
 1.683904-5 8.479661-6-4.033112-7-4.033112-7-1.996981-7 3.327431-7923733102  212
 4.018752-7 3.129066-7 1.148386-7 4.586439-7 2.429662-6 2.325577-6923733102  213
 4.206472-6 7.926156-6 3.961073-5 3.207020-5                      923733102  214
 3.000000+0 0.000000+0       9228         18          0          1923733102  215
 0.000000+0 0.000000+0          0          6        361         15923733102  216
 1.000000-5 3.000000-1 1.000000+2 1.000000+3 1.000000+4 3.750000+4923733102  217
 9.000000+4 1.350000+5 2.050000+5 2.750000+5 4.125000+5 6.250000+5923733102  218
 9.500000+5 1.500000+6 2.300000+6 1.000000-5 3.000000-1 7.800000+0923733102  219
 1.100000+1 1.000000+2 1.000000+3 1.000000+4 3.750000+4 9.000000+4923733102  220
 1.350000+5 2.050000+5 2.750000+5 4.125000+5 6.250000+5 9.500000+5923733102  221
 1.325000+6 1.900000+6 2.900000+6 4.600000+6 6.750000+6 9.500000+6923733102  222
 1.350000+7 1.550000+7 2.000000+7 4.120031-9 4.120031-9-7.918788-9923733102  223
-7.918788-9-2.171802-8-1.746444-8 1.229234-8-1.135734-8-1.790750-8923733102  224
 2.336772-8-1.41480-10-1.017960-8 5.044801-8 1.674350-8 1.247294-8923733102  225
 1.329616-8 1.931502-8 1.966685-8 1.908975-8 1.283924-8 9.396333-9923733102  226
 3.450409-9 8.112564-9 4.120031-9 4.120031-9-7.918788-9-7.918788-9923733102  227
-2.171802-8-1.746444-8 1.229234-8-1.135734-8-1.790750-8 2.336772-8923733102  228
-1.41480-10-1.017960-8 5.044801-8 1.674350-8 1.247294-8 1.329616-8923733102  229
 1.931502-8 1.966685-8 1.908975-8 1.283924-8 9.396333-9 3.450409-9923733102  230
 8.112564-9 3.906122-7 3.906122-7 1.311645-6 1.311645-6 2.413183-6923733102  231
 2.460964-6 2.983461-6 2.527120-6 2.714317-6 2.678308-6 2.660081-6923733102  232
 2.675881-6 2.151841-6 1.976851-6 1.818055-6 1.777526-6 1.655458-6923733102  233
 1.544691-6 1.487994-6 1.275018-6 1.067313-6 5.311681-7 9.632330-7923733102  234
 4.184709-7 4.184709-7 1.447843-6 1.447843-6 2.694459-6 2.892719-6923733102  235
 3.638571-6 3.135139-6 3.366454-6 3.245738-6 3.114898-6 3.130073-6923733102  236
 2.531963-6 2.346474-6 2.151492-6 2.097494-6 1.949340-6 1.812555-6923733102  237
 1.745052-6 1.498504-6 1.254898-6 6.248403-7 1.132928-6 4.626174-7923733102  238
 4.626174-7 1.622848-6 1.622848-6 2.966232-6 3.432597-6 5.688083-6923733102  239
 4.582886-6 4.979980-6 4.583791-6 4.133409-6 4.046871-6 3.336078-6923733102  240
 3.184438-6 2.909915-6 2.819586-6 2.613597-6 2.422280-6 2.330329-6923733102  241
 2.006674-6 1.680714-6 8.371374-7 1.517885-6 3.932794-7 3.932794-7923733102  242
 1.447838-6 1.447838-6 2.703966-6 3.436486-6 5.122691-6 7.174253-6923733102  243
 7.805172-6 6.856467-6 5.367642-6 5.021746-6 4.167291-6 4.055483-6923733102  244
 3.677896-6 3.512186-6 3.229974-6 2.963649-6 2.846886-6 2.472893-6923733102  245
 2.071395-6 1.033842-6 1.872878-6 3.474893-7 3.474893-7 1.359861-6923733102  246
 1.359861-6 2.624447-6 3.461609-6 5.090528-6 7.493914-6 1.303279-5923733102  247
 9.074728-6 6.403962-6 5.835266-6 4.948797-6 4.855329-6 4.434647-6923733102  248
 4.239867-6 3.869714-6 3.523156-6 3.383203-6 2.954499-6 2.475535-6923733102  249
 1.238298-6 2.240272-6 3.961709-7 3.961709-7 1.433665-6 1.433665-6923733102  250
 2.696034-6 3.187881-6 4.215297-6 6.164439-6 8.092111-6 1.595267-5923733102  251
 7.928151-6 6.248201-6 5.376552-6 5.152228-6 4.748594-6 4.567367-6923733102  252
 4.148828-6 3.750376-6 3.598700-6 3.180284-6 2.654147-6 1.330140-6923733102  253
 2.401390-6 4.044586-7 4.044586-7 1.438398-6 1.438398-6 2.637152-6923733102  254
 2.986730-6 3.951442-6 5.080911-6 6.277739-6 8.271959-6 1.115239-5923733102  255
 6.831780-6 5.665925-6 5.170668-6 4.727049-6 4.588867-6 4.184250-6923733102  256
 3.792206-6 3.631848-6 3.199669-6 2.663915-6 1.332716-6 2.410612-6923733102  257
 3.224936-7 3.224936-7 1.303452-6 1.303452-6 2.510809-6 3.013809-6923733102  258
 3.729339-6 4.588372-6 5.496114-6 6.247491-6 6.780534-6 1.172814-5923733102  259
 6.754721-6 5.548898-6 5.143174-6 4.988147-6 4.475989-6 3.949614-6923733102  260
 3.759107-6 3.293664-6 2.787971-6 1.399763-6 2.531463-6 3.234167-7923733102  261
 3.234167-7 1.226796-6 1.226796-6 2.304837-6 2.690726-6 3.269777-6923733102  262
 4.184483-6 4.900121-6 5.925724-6 5.771941-6 6.867382-6 1.171719-5923733102  263
 6.496188-6 5.483618-6 5.208147-6 4.680770-6 4.045318-6 3.850792-6923733102  264
 3.412132-6 2.893050-6 1.458853-6 2.631127-6 2.501066-7 2.501066-7923733102  265
 1.000070-6 1.000070-6 1.905809-6 2.305040-6 2.833609-6 4.010246-6923733102  266
 4.773239-6 5.619265-6 5.534104-6 5.597130-6 5.939952-6 1.146934-5923733102  267
 7.166277-6 6.145922-6 5.447677-6 4.727558-6 4.508064-6 4.065641-6923733102  268
 3.446592-6 1.727079-6 3.135060-6 1.051057-7 1.051057-7 5.873906-7923733102  269
 5.873906-7 1.177779-6 1.468241-6 1.856267-6 2.638892-6 2.864619-6923733102  270
 3.679720-6 3.697025-6 4.211474-6 4.426577-6 6.835702-6 1.262842-5923733102  271
 8.885556-6 6.385032-6 5.671047-6 5.461539-6 5.000133-6 4.284651-6923733102  272
 2.129101-6 3.932657-6 9.722399-8 9.722399-8 5.084818-7 5.084818-7923733102  273
 1.012793-6 1.258993-6 1.601016-6 2.265194-6 2.355179-6 3.161445-6923733102  274
 3.147990-6 3.677312-6 3.676768-6 5.524721-6 6.855775-6 1.243189-5923733102  275
 9.611692-6 6.597824-6 6.445379-6 5.871086-6 5.042240-6 2.532897-6923733102  276
 4.637333-6                                                       923733102  277
 3.000000+0 0.000000+0       9437         18          0          1923733102  278
 0.000000+0 0.000000+0          0          6        331         15923733102  279
 1.000000-5 3.000000-1 1.000000+2 1.000000+3 1.000000+4 3.750000+4923733102  280
 9.000000+4 1.350000+5 2.050000+5 2.750000+5 4.125000+5 6.250000+5923733102  281
 9.500000+5 1.500000+6 2.300000+6 1.000000-5 3.000000-1 1.000000+2923733102  282
 1.000000+3 1.000000+4 3.750000+4 9.000000+4 1.350000+5 2.050000+5923733102  283
 2.750000+5 4.125000+5 6.250000+5 9.500000+5 1.325000+6 1.900000+6923733102  284
 2.900000+6 4.600000+6 6.750000+6 9.500000+6 1.350000+7 1.550000+7923733102  285
 2.000000+7 1.756601-8 1.756601-8 2.307246-8 3.049692-8 6.589630-8923733102  286
 4.306795-8 3.891639-8 9.316174-8 6.233225-8 5.014352-8 1.132461-7923733102  287
 7.828227-8 7.217931-8 7.466687-8 8.420934-8 8.280880-8 7.986202-8923733102  288
 7.099759-8 6.653936-8 3.729051-8 6.229219-8 1.756601-8 1.756601-8923733102  289
 2.307246-8 3.049692-8 6.589630-8 4.306795-8 3.891639-8 9.316174-8923733102  290
 6.233225-8 5.014352-8 1.132461-7 7.828227-8 7.217931-8 7.466687-8923733102  291
 8.420934-8 8.280880-8 7.986202-8 7.099759-8 6.653936-8 3.729051-8923733102  292
 6.229219-8 4.462786-7 4.462786-7 2.837186-6 2.806743-6 3.223859-6923733102  293
 2.752009-6 3.010122-6 2.961952-6 2.971455-6 3.034000-6 2.467666-6923733102  294
 2.328588-6 2.168345-6 2.148547-6 2.101845-6 1.956477-6 1.868093-6923733102  295
 1.606852-6 1.416914-6 7.693215-7 1.329355-6 4.845855-7 4.845855-7923733102  296
 3.132689-6 3.256939-6 3.913624-6 3.392811-6 3.695923-6 3.566611-6923733102  297
 3.470179-6 3.539297-6 2.892230-6 2.746992-6 2.550140-6 2.519340-6923733102  298
 2.457250-6 2.281159-6 2.177644-6 1.876005-6 1.653521-6 8.985493-7923733102  299
 1.551922-6 5.522040-7 5.522040-7 3.438471-6 3.867718-6 6.089964-6923733102  300
 4.935918-6 5.382186-6 4.995669-6 4.606240-6 4.582258-6 3.812452-6923733102  301
 3.710496-6 3.431793-6 3.369575-6 3.273834-6 3.032319-6 2.894236-6923733102  302
 2.499881-6 2.202559-6 1.199479-6 2.068463-6 5.048252-7 5.048252-7923733102  303
 3.168782-6 3.887495-6 5.527578-6 7.574905-6 8.200554-6 7.254595-6923733102  304
 5.857552-6 5.588665-6 4.658222-6 4.595782-6 4.214876-6 4.082617-6923733102  305
 3.923727-6 3.600930-6 3.433465-6 2.983538-6 2.618851-6 1.420304-6923733102  306
 2.460591-6 4.740287-7 4.740287-7 3.176372-6 3.970602-6 5.519170-6923733102  307
 7.847616-6 1.357481-5 9.459232-6 6.909114-6 6.411306-6 5.445994-6923733102  308
 5.421315-6 4.991993-6 4.829055-6 4.591193-6 4.185679-6 3.990721-6923733102  309
 3.479556-6 3.045590-6 1.645466-6 2.863388-6 4.904450-7 4.904450-7923733102  310
 3.224962-6 3.648894-6 4.494154-6 6.372683-6 8.250372-6 1.645021-5923733102  311
 8.292258-6 6.662842-6 5.744732-6 5.594043-6 5.180347-6 5.028297-6923733102  312
 4.732302-6 4.281294-6 4.081069-6 3.583898-6 3.108881-6 1.671810-6923733102  313
 2.921791-6 5.179343-7 5.179343-7 3.228833-6 3.502100-6 4.376715-6923733102  314
 5.429168-6 6.657624-6 8.720918-6 1.189946-5 7.362235-6 6.140660-6923733102  315
 5.733672-6 5.281981-6 5.181792-6 4.906823-6 4.452004-6 4.239362-6923733102  316
 3.730595-6 3.251817-6 1.751799-6 3.052687-6 4.618064-7 4.618064-7923733102  317
 3.101498-6 3.554217-6 4.180992-6 4.990470-6 5.929547-6 6.708322-6923733102  318
 7.279768-6 1.250699-5 7.214284-6 6.057901-6 5.665926-6 5.554190-6923733102  319
 5.173895-6 4.593276-6 4.355488-6 3.817554-6 3.360511-6 1.809253-6923733102  320
 3.170271-6 4.124357-7 4.124357-7 2.762236-6 3.088725-6 3.571202-6923733102  321
 4.445007-6 5.195247-6 6.309300-6 6.113009-6 7.239937-6 1.216836-5923733102  322
 6.836683-6 5.833379-6 5.606253-6 5.194231-6 4.520603-6 4.285438-6923733102  323
 3.770336-6 3.302310-6 1.771589-6 3.122687-6 2.810233-7 2.810233-7923733102  324
 2.155689-6 2.505228-6 2.936489-6 4.045053-6 4.836048-6 5.855992-6923733102  325
 5.702776-6 5.664378-6 6.012916-6 1.167280-5 7.220186-6 6.264512-6923733102  326
 5.695446-6 4.919647-6 4.676586-6 4.184389-6 3.636112-6 1.925731-6923733102  327
 3.444378-6 1.203301-7 1.203301-7 1.262618-6 1.521675-6 1.824114-6923733102  328
 2.555311-6 2.803257-6 3.856687-6 3.718516-6 4.195658-6 4.391636-6923733102  329
 6.740464-6 1.247719-5 8.932404-6 6.456683-6 5.685773-6 5.465747-6923733102  330
 4.982233-6 4.350095-6 2.231388-6 4.170753-6 6.444943-8 6.444943-8923733102  331
 9.519869-7 1.166006-6 1.423474-6 2.034209-6 2.151504-6 3.242044-6923733102  332
 3.021133-6 3.535045-6 3.502486-6 5.328298-6 6.687729-6 1.212462-5923733102  333
 9.427675-6 6.431210-6 6.282109-6 5.700808-6 4.973386-6 2.534591-6923733102  334
 4.757867-6                                                       923733102  335
                                                                  923733  099999
                                                                  9237 0  0    0
                                                                     0 0  0    0
 9.32370E+4 2.35011E+2          0          1         34         109346 1451    1
 0.0        1.00000E+0          0          0          0          69346 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20029346 1451    3
 3.00000E+2 0.0                 1          0        345          49346 1451    4
 93-Np-237 FEI/LANL   EVAL-May96 K.Zolotarev et al.,P.Young et al.9346 1451    5
                      DIST-Feb2004                                9346 1451    6
----IRDF-2002         MATERIAL 9346                               9346 1451    7
-----INCIDENT NEUTRON DATA                                        9346 1451    8
------ENDF-6 FORMAT                                               9346 1451    9
***************************************************************** 9346 1451   10
 93-Np-237 FEI        EVAL-May96  K.Zolotarev et al.              9346 1451   11
                      DIST-Sep03                                  9346 1451   12
----BROND-3           MATERIAL 9346         Revision 2, Oct. 2003 9346 1451   13
***************************************************************** 9346 1451   14
------Russian Reactor Dosimetry File RRDF-2002                    9346 1451   15
***************************************************************** 9346 1451   16
Authors of evaluation: K.I.Zolotarev, S.A.Badikov, A.I.Blokhin,   9346 1451   17
                       A.V.Ignatyuk                               9346 1451   18
***************************************************************** 9346 1451   19
                                                                  9346 1451   20
                    ----- MF=2 MT=151 -----                       9346 1451   21
                                                                  9346 1451   22
RESONANCE PARAMETERS                                              9346 1451   23
--------------------                                              9346 1451   24
Resolved Resonance Region : 1.0E-5 - 600 eV                       9346 1451   25
    Resolved MLBW resonance parameters up to 600 eV were based on 9346 1451   26
on data from ref. [1].                                            9346 1451   27
    A statistical method  of  the resonance analysis showed  that 9346 1451   28
the missing of the resonances becomes essential above  the energy 9346 1451   29
of 150 eV. However only weak resonances are missed with the neut- 9346 1451   30
ron widths less than the average width by the factor 5-10.        9346 1451   31
    The resonances with widths close to average or above it  were 9346 1451   32
identified without  the noticeable  missing up  to the  energy of 9346 1451   33
600 eV.  So as these resonances  give dominant contribution  into 9346 1451   34
the neutron cross sections the resolved resonances region was ex- 9346 1451   35
panded up to 600 eV  and  average contribution of the missed weak 9346 1451   36
resonances was taken into account by addition  of  relevant cross 9346 1451   37
section background in the file MF=3.  (For fission cross sections 9346 1451   38
this background is equal to zero).                                9346 1451   39
                                                                  9346 1451   40
Unresolved Resonance Region : 600 eV - 6 keV                      9346 1451   41
    For the optical-statistical calculation of the cross sections 9346 1451   42
in the unresolved resonance region were used the following para-  9346 1451   43
meters:                                                           9346 1451   44
       Average resonance spacing - D0 = 0.57+-0.03 eV             9346 1451   45
       Neutron strengh function  - S0 = (0.97+-0.07)*104          9346 1451   46
       Average radiation width   - Gg = 40.0+-1.2 meV             9346 1451   47
This values were obtained  as  a result of  the analysis resolwed 9346 1451   48
MLBW resonance parameters taking into account the missed resonan- 9346 1451   49
ces correction.                                                   9346 1451   50
    Considerable attention was paid to  the  analysis of fission  9346 1451   51
widths and  elimination  of contradictions  in the description of 9346 1451   52
intermediate structure of averaged fission cross sections for the 9346 1451   53
neutron energies above 100 eV. The new experimental data [2-4] on 9346 1451   54
fission cross sections were included in the analysis.  They  were 9346 1451   55
obtained by LANL and JAERI physicists on their neutron spectrome- 9346 1451   56
ter [2,3]  and by Dubna-Obninsk collaboration on the pulsed reac- 9346 1451   57
tor of JINR [4].                                                  9346 1451   58
    The resulting set of resonance parameters reproduces well the 9346 1451   59
observed intermediate structure of fission cross sections (100 eV-9346 1451   60
6 keV).  Corresponding group  fission cross sections are 30-50 %  9346 1451   61
lower than  JENDL-3.2  evaluation [5]  and  approximately  twice  9346 1451   62
higher than ENDF/B-VI ones [6].  Corrected fission widths of  the 9346 1451   63
neutron resonances below 100 eV also result in fission cross sec- 9346 1451   64
tions which are lower than JENDL-3.2 values [5].                  9346 1451   65
    Calculated  from  the adopted resonance parameters  2200 M/S  9346 1451   66
cross sections and resonance integrals are agree rather well with 9346 1451   67
the recommended evaluated experimental data [1] :                 9346 1451   68
                                                                  9346 1451   69
  Value             This evaluation    Experimental data [1]      9346 1451   70
  Total               190.23 barn                                 9346 1451   71
  Elastic             14.17  barn                                 9346 1451   72
  Fission             0.0215 barn      0.0215+-0.0024 barn        9346 1451   73
  Capture             176.04 barn       175.9+-2.9    barn        9346 1451   74
  Fission res. int.   6.930  barn         6.9+-1.0    barn        9346 1451   75
  Capture res. int.   642.30 barn         640+-50     barn        9346 1451   76
                                                                  9346 1451   77
                    ----- MF=3 MT= 18 -----                       9346 1451   78
                                                                  9346 1451   79
FISSION CROSS SECTIONS                                            9346 1451   80
----------------------                                            9346 1451   81
    Np-237 fission cross sections from 1.0E-5 eV to 6 keV are re- 9346 1451   82
constructed from evaluated MLBW resolved and unresolved resonance 9346 1451   83
parameters.                                                       9346 1451   84
    For the evaluation of the  Np-237(n,f)  cross sections in the 9346 1451   85
neutron energy region of  6 keV - 20 MeV  available  experimental 9346 1451   86
data [7- 46] were analyzed.  During this  procedure  experimental 9346 1451   87
data  if it  was possible  were  corrected to the new recommended 9346 1451   88
cross section data for monitor reactions used in the measurements 9346 1451   89
and to the new recommended decay data.                            9346 1451   90
    The top priority was given to absolute measurements  where no 9346 1451   91
reference cross sections were used to determine the neutron  flux 9346 1451   92
and to time-of-flight experiments  with simultaneous registration 9346 1451   93
of the fission and monitoring reaction events.                    9346 1451   94
    In ten experiments the Np-237(n,f) cross sections were measu- 9346 1451   95
red relatively to the fission of U-235.  The use  as the standard 9346 1451   96
of the U-235 fission cross section from  ENDF/B-VI  [47]  instead 9346 1451   97
of the old one (ENDF/B-V) results in decrease of the  Np-237(n,f) 9346 1451   98
cross sections in average  by 2 %  in 0.1 - 2.0 MeV  range and by 9346 1451   99
1.5 % in 2.0 - 3.0 MeV range.                                     9346 1451  100
    In the work of Kupriyanov et al. [20] the  Np-237(n,f)  cross 9346 1451  101
sections  were  measured against  the fission  cross sections  of 9346 1451  102
Pu-239. At the present time there are no recommended Pu-239 cross 9346 1451  103
sections as a standard data.  The data  from  two libraries were  9346 1451  104
used to get  absolute values: JENDL-3.2 [48] and ENDF/B-VI [49].  9346 1451  105
Below 1.6 MeV the results of Ref. [20] disagree with the integral 9346 1451  106
experiments no matter which data are used for  Pu-239(n,f) .  The 9346 1451  107
analysis of Ref. [20] data demonstrated that  the  good agreement 9346 1451  108
with  the rest of  data may be obtained for the energy  region of 9346 1451  109
1.6-7.0 MeV if  Pu-239(n,f) reaction cross section data are taken 9346 1451  110
from JENDL-3.2 library.                                           9346 1451  111
    The ratio of Np-237 to U-235  fission cross sections measured 9346 1451  112
by Behrens et al. [23] in 0.11 - 18.89 MeV energy range was multi-9346 1451  113
plied by factor of 1.051. This normalization factor was  obtained 9346 1451  114
from the values of the functional <sNp237(n,f)> / <sU235(n,f)> in 9346 1451  115
the 1 - 5 MeV  energy range evaluated before.  There is a  lot of 9346 1451  116
experimental data which are in  good agreement in  this interval. 9346 1451  117
The ratio of the Np-237(n,f) evaluated averaged cross section for 9346 1451  118
the neutron spectrum of  Cf-252 spontaneous  fission, known  from 9346 1451  119
many works, to the averaged data  of Behrens et al. [23] is equal 9346 1451  120
to 1.055 that confirms our renormalization of these data.         9346 1451  121
    The analysis of experimental data on the ratio of Np-237  and 9346 1451  122
U-235 fission cross sections  indicates that the relative  energy 9346 1451  123
trends of <sNp237(n,f)> / <sU235(n,f)> measured by Terayama et al.9346 1451  124
[36] in the energy range of 4.19 - 6.99 MeV  and  by Goverdovskiy 9346 1451  125
et al. [32]  in the 5.66 - 10.06 MeV energy range coincides  with 9346 1451  126
the  results  of other  authors.  To make them agree  in absolute 9346 1451  127
values Terayama et al. and Goverdovskiy et al. results were multi-9346 1451  128
plied by 0.96 and 1.079, respectively.  The data  on  the  Np-237 9346 1451  129
fission cross sections obtained by Terayama et al. on T(p,n)He-3  9346 1451  130
neutron source for the  0.70 - 2.99 MeV  energy range are in good 9346 1451  131
agreement with the results of Refs. [38-40]. So they were correc- 9346 1451  132
ted only according to  the new data  on the  monitoring  reaction 9346 1451  133
U-235(n,f)  [46].                                                 9346 1451  134
    Experimental data of Meadows et al. [26] as well as  that  of 9346 1451  135
Kupriyanov et al. [20] are  systematically  too low  below  1 MeV 9346 1451  136
that   contradicts   to  the   evaluated   integral   experiments 9346 1451  137
available.  Above 1 MeV  Meadows et al. [26] data well agree with 9346 1451  138
the results of other authors  so they were included in the final  9346 1451  139
evaluation only above this energy. Data of Kupriyanov et al. [20] 9346 1451  140
were taken into account in the evaluation above 1.6 MeV.          9346 1451  141
    Statistical analysis  of the input experimental cross section 9346 1451  142
data for  Np-237(n,f) reaction in 0.1-20 MeV neutron energy range 9346 1451  143
was carried out  by means of PADE-2 code [50].  Rational function 9346 1451  144
was used as the model function [51].                              9346 1451  145
    Averaged cross sections for  U-235  thermal fission [52]  and 9346 1451  146
Cf-252 spontaneous fission neutron spectra [53] calculated  from  9346 1451  147
the evaluated Np-237(n,f) excitation function are the following:  9346 1451  148
                                                                  9346 1451  149
  9346 1451  150
    TYPE OF SPECTRUM    <CS>,mb (calc.)    <CS>, mb (measured)  9346 1451  151
  9346 1451  152
 U-235 neutron fission     1356.2        1353.0 +- 24.0   [54]  9346 1451  153
                                         1350.0 +- 24.0   [55]  9346 1451  154
  9346 1451  155
 CF-252 spont. fission     1359.9        1361.0 +- 21.6   [55]  9346 1451  156
  9346 1451  157
                                                                  9346 1451  158
    Evaluated Np-237 fission cross section is in a good agreement 9346 1451  159
with the integral experiment data both  for U-235 thermal fission 9346 1451  160
neutron spectrum and for Cf-252 spontaneous fission neutron spec- 9346 1451  161
trum.                                                             9346 1451  162
    The evaluated Np-237(n,f) cross section agrees within the ac- 9346 1451  163
curacy with integral experimental data for SIGNA-SIGMA field.     9346 1451  164
    The Np-237 fission cross sections measured in  CFRMF facility 9346 1451  165
are lower than calculated ones for any fission cross section eva- 9346 1451  166
luation. This apparently indicates the necessity of more detailed 9346 1451  167
and careful analysis of the CFRMF experimental  data  accuracy.   9346 1451  168
                                                                  9346 1451  169
                    ----- MF=33 MT= 18-----                       9346 1451  170
    Uncertainties in  the evaluated excitation function  for the  9346 1451  171
Np-237(n,f) reaction are given in the two independent matrixes.   9346 1451  172
    In the  energy range 1.000E-05 eV - 0.1 MeV uncertainties are 9346 1451  173
given in the form of diagonal matrix  of uncertainties  for  6-th 9346 1451  174
neutron energy intervals (LB=1)                                   9346 1451  175
    In the energy range 0.1 - 20 MeV  uncertainties are presented 9346 1451  176
in  the form  of relative covariance matrix  for the  48 -neutron 9346 1451  177
energy groups (LB=5).  Eigenvalues  of this  6-th digits relative 9346 1451  178
covariance matrix are the following:                              9346 1451  179
                                                                  9346 1451  180
    1.49939E-07    1.52531E-07    1.53109E-07    1.53318E-07      9346 1451  181
    1.54049E-07    1.55336E-07    1.56641E-07    1.58051E-07      9346 1451  182
    1.58347E-07    1.60763E-07    1.63743E-07    1.64776E-07      9346 1451  183
    1.67513E-07    1.69820E-07    1.73330E-07    1.75751E-07      9346 1451  184
    1.77557E-07    2.05370E-07    2.66364E-07    2.70615E-07      9346 1451  185
    2.75409E-07    2.80956E-07    2.93138E-07    3.15582E-07      9346 1451  186
    3.35128E-07    4.86134E-07    7.89097E-07    3.07453E-06      9346 1451  187
    1.65989E-05    9.67332E-05    1.24983E-04    1.51845E-04      9346 1451  188
    4.05040E-04    4.14092E-04    5.11273E-04    5.63190E-04      9346 1451  189
    7.24776E-04    8.29295E-04    9.68770E-04    9.77438E-04      9346 1451  190
    1.07709E-03    1.13969E-03    1.57856E-03    1.84372E-03      9346 1451  191
    2.04068E-03    2.65362E-03    3.89983E-03    1.60049E-02      9346 1451  192
                                                                  9346 1451  193
References:                                                       9346 1451  194
 1. S.F.Mughabghab  Neutron Cross Sections. N.Y.-London, Academic 9346 1451  195
    Press, 1984, v.1, part B.                                     9346 1451  196
 2. J.Kimura  Nucl. Sci. Techn., v. 30, p.863, 1993               9346 1451  197
 3. A.D.Carlson et al. Proc. of an Int. Conf. on Nuclear Data for 9346 1451  198
    Science and Technology, Gatlinburg, Tennessee, USA, 9-13 May  9346 1451  199
    1994, Ed. J.Dickens, ANS, Oak Ridge, 1994, v.1, p.40          9346 1451  200
 4. A.A.Goverdovskiy et al.  Jadernaja Fizika (Rus.), v.58, p.27, 9346 1451  201
    January 1995                                                  9346 1451  202
 5. Y.Kikuchi  Proc. of an Int. Conf. on Nuclear Data for Science 9346 1451  203
    and Technology, Gatlinburg, Tennessee, USA, 9-13 May 1994,    9346 1451  204
    Ed. J.Dickens, ANS, Oak Ridge, 1994, v.2, p.692               9346 1451  205
 6. P.Young, E.Arthur, F.Mann  ENDF/B-VI library, MAT 9346, 1990  9346 1451  206
 7. E.D.Klema  Phys. Rev., v.72, p.88, July 1947                  9346 1451  207
 8. R.L.Henkel  Report LA-2114, 1957                              9346 1451  208
    R.L.Henkel  Report LA-2122, June 1957                         9346 1451  209
 9. A.N.Protopopov et al. Atomnaja Energija (Sov.),v.4,p.190,1958 9346 1451  210
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10. R.B.Murrey, H.W.Schmitt  Phys. Rev., v.115, p.1707, 1959      9346 1451  212
11. B.M.Gokhberg et al.  Doklady Akademii Nauk SSSR, v.128,(6),   9346 1451  213
    p.1157, 1959                                                  9346 1451  214
12. V.M.Pankratov et al. Atomnaya Energiya, v.9, p.399, 1960 ???  9346 1451  215
13. V.M.Pankratov  Atomnaja Energiya (Sov.), v.14, p.177, 1963    9346 1451  216
14. J.A.Grundl  Nucl. Sci. Eng., v.30, p.39, October 1967         9346 1451  217
15. P.H.White, G.P.Warner  J. of Nucl. Energy, v.21, p.671, 1967  9346 1451  218
16. W.E.Stein, R.K.Smith, H.L.Smith   Proceedings Conf. Neutron   9346 1451  219
    Cross Sections and Technology, Washington, D.C., March 4-7,   9346 1451  220
    1968, NBS Special Publication 299 , p.627 ,  U.S. National    9346 1451  221
    Bureau of Standards, 1968                                     9346 1451  222
17. R.H.Iyer, R.Sampathkumar Proc. of 12th Symp. on Nuclear Phys. 9346 1451  223
    and Solid State Phys., Roorkee, India, 28-31 December 1969,   9346 1451  224
    v.2, p.289 ;                                                  9346 1451  225
    R.H.Iyer, R.Sampathkumar  Prog. Report BARC/I-79, p.55, 1970  9346 1451  226
18. W.K.Brown et al. Nucl. Phys., vA156, p.609, November 1970     9346 1451  227
19. R.J.Jiacoletti, W.K.Brown, H.G.Olson.  Nucl. Sci. Eng., v.48, 9346 1451  228
    p.412, August 1972                                            9346 1451  229
20. V.M.Kupriyanov et al.  Atomnaya Energiya, v.45, p.440, 1978   9346 1451  230
21. D.J.Grady et al.  Proc. of an Int. Conf. on Nuclear Cross     9346 1451  231
    Sections for Technology, Knoxville, Tennessee, 22-26 October  9346 1451  232
    1979, NBS Special Publ.594, p.976, September 1980             9346 1451  233
22. R.Arlt et al.   Report ZFK-410, p.122, January 1980 ;         9346 1451  234
    R.Arlt et al.   Kernenergie, v.24, p.48, February 1981        9346 1451  235
23. J.W.Behrens, J.C.Browne, J.C.Malden   Nucl. Sci. Eng., v.80,  9346 1451  236
    p.393, 1982                                                   9346 1451  237
24. M.Cance, G.Grenier   Proc of an Int. Conf. on Nuclear Data    9346 1451  238
    for Science and Technology, Antwerp, 6-10 September 1982,     9346 1451  239
    Dr. Reidel Publishing Company, 1983, p.51                     9346 1451  240
25. M.Varnagy, S.Juhasz, J.Csikai  Nucl. Instr. Meth., v.196,     9346 1451  241
    p.465, May 1982                                               9346 1451  242
26. J.W.Meadows  Nucl. Sci. Eng., v.85, p.271, November 1983      9346 1451  243
27. I.D.Alkhazov, E.A.Ganza, L.V.Drapchinskij et al. Proceedings  9346 1451  244
    of the 3-d All-union Conference  on the  Neutron Radiation    9346 1451  245
    Metrology at Reactors and Accelerators, v.2, p.201, Moscow,   9346 1451  246
    CNIIATOMINFORM, 1983                                          9346 1451  247
28. K.R.Zasadny et al.  J. Trans. Amer. Nucl. Soc., v.47, p.425,  9346 1451  248
    November 1984                                                 9346 1451  249
29. Wu Jingxia et al. Chinese J. of Nuclear Physics, v.6, p.369,  9346 1451  250
    November 1984                                                 9346 1451  251
30. I.Garlea et al. Revue Roumaine de Physique, v.29, p.421, 1984 9346 1451  252
31. A.A.Goverdovski et al.  Preprint FEI-1552, Obninsk, 1984      9346 1451  253
32. A.A.Goverdovskij et al. VANT, Serija: Yadernye Konstanty,     9346 1451  254
    issue 3(57), p.13, September 1984                             9346 1451  255
33. K.Kanda et al.  Report JAERI-M-85-035, p.220, 1985            9346 1451  256
34. R.Arlt et al.  Isotopenpraxis, v.21, p.344, 1985              9346 1451  257
35. A.A.Goverdovskij et al.  Atomnaja Energija (Sov.), v.58, no.2,9346 1451  258
    p.137, February 1985                                          9346 1451  259
36. H.Terayama et al.   Progress Report NETU-47, 1986 ;           9346 1451  260
    H.Terayama et al.   Progress Report NEANDC(J)-122, Sep. 1986  9346 1451  261
37. I.D.Alkhazov et al.   VANT, Serija: Yadernye Konstanty, v.4,  9346 1451  262
    p.19, December 1986                                           9346 1451  263
38. V.A.Kalinin et al.  VANT, Serija: Yadernye Konstanty, v.4,    9346 1451  264
    p.3, December 1987                                            9346 1451  265
39. P.W.Lisowski et al.   Proc. of an Int. Conf. on Nuclear Data  9346 1451  266
    for Science and Technology, Mito, Japan, 30 May-3 June 1988,  9346 1451  267
    pp. 97-99                                                     9346 1451  268
40. J.W.Meadows  Annals of Nucl. Energy, v.15, p.421, August 1988 9346 1451  269
41. J.W.Meadows, D.L.Smith, L.P.Geraldo   Annals of Nucl. Energy, 9346 1451  270
    v.16, p.471, September 1989                                   9346 1451  271
36. L.Desdin, S.Szegedi, J.Csikai  Acta Physica Hungaria, v.65,   9346 1451  272
    p.271, 1989                                                   9346 1451  273
43. P.W.Lisowski et al.  Proc. of the Conference on Fifty Years   9346 1451  274
    with Nuclear Fission, NIST, Gaithersburg, MD, 1989, p.443     9346 1451  275
44. K.Merla et al.   Proc. of an Int. Conf. on Nuclear Data for   9346 1451  276
    Science and Technology, Julich, FRG, 13-17 May 1991. Springer 9346 1451  277
    Verlag, Berlin - Heidelberg, 1992, p.510-513                  9346 1451  278
45. A.D.Carlson et al. Proc. of an Int. Conf. on Nuclear Data for 9346 1451  279
    Science and Technology, Gatlinburg, Tennessee, USA, May 9-13, 9346 1451  280
    1994, Vol.1, pp. 40-42                                        9346 1451  281
46. T.Iwasaki et al. Nucl. Sci. Technology, v.36, p.127, 1999     9346 1451  282
47. L.Weston et al. ORNL,LANL eval. April 1989, ENDF/B-VI Library 9346 1451  283
    MAT=9228;                                                     9346 1451  284
    H.Conde ed. Nuclear Data Standards for Nuclear Measurements,  9346 1451  285
    Report NEANDC-311 U, p.51-58, OECD, Paris, 1992.              9346 1451  286
48. M.Kawai et al. eval. NAIG, JENDL-3.2 library, MAT=9437,       9346 1451  287
    Rev. 2, February 1993                                         9346 1451  288
49. P.Young et al. eval. ORNL, LANL , ENDF/B-VI library, MAT=9437,9346 1451  289
    Rev.1, January 1993                                           9346 1451  290
50. S.A.Badikov et al.  Preprint FEI-1686, Obninsk, 1985          9346 1451  291
51. S.Badikov, N.Rabotnov, K.Zolotarev  Proc. of NEANSC Speciali- 9346 1451  292
    st's Meeting on Evaluation and Processing of Covariance Data, 9346 1451  293
    Oak Ridge, USA, 1992, OECD, Paris, 1993, p.105                9346 1451  294
52. L.W.Weston et al.  Evaluated Neutron Data  for  Uranium-235,  9346 1451  295
    ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989    9346 1451  296
53. W.Mannhart  IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987        9346 1451  297
54. W.Mannhart  Prog. Report INDC(Ger)-045, pp.40-43, June 1999   9346 1451  298
55. W.Mannhart  Validation of Differential Cross Sections with    9346 1451  299
    Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 9346 1451  300
    September 2002                                                9346 1451  301
******************************************************************9346 1451  302
                    ----- MF=3 MT= 1 -----                        9346 1451  303
                    ----- MF=3 MT= 2 -----                        9346 1451  304
 93-NP-237 LANL       EVAL-APR90 P.YOUNG, E.ARTHUR, F.MANN        9346 1451  305
                      DIST-SEP91 REV1-JUL91            19910806   9346 1451  306
----ENDF/B-VI         MATERIAL 9346         REVISION 1            9346 1451  307
 MT=1   Neutron Total Cross Section.  Derrien evaluation (De80,   9346 1451  308
          De89) used from 1.0E-5 eV to 0.008 MeV. Above 0.008 MeV,9346 1451  309
          coupled channel optical model calculations (ECIS code)  9346 1451  310
          with modified Lagrange (Ha80) potential used as prior   9346 1451  311
          in a covariance analysis of measurement by Lisowski et  9346 1451  312
          al. from 3 to 20 MeV (Li90).                            9346 1451  313
 MT=2   All Energies, based on subtraction of MT=4,16,17,18,37,   9346 1451  314
          and 102 from MT=1.                                      9346 1451  315
******************************************************************9346 1451  316
 The cross sections for total and elastic were modified between   9346 1451  317
 6 and 10 Kev for continuity with the data of Zolatarev file 18.  9346 1451  318
 The number of interpolation schemes is set to 1.                 9346 1451  319
                                                                  9346 1451  320
******************************************************************9346 1451  321
 ***************** Program LINEAR (VERSION 2002-1) ***************9346 1451  322
 For All Data Greater than 1.0000E-10 barns in Absolute Value     9346 1451  323
 Data Linearized to Within an Accuracy of .100000000 per-cent     9346 1451  324
 ***************** Program RECENT (VERSION 2002-1) ***************9346 1451  325
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9346 1451  326
 Data Linearized to within an Accuracy of .100000000 per-cent     9346 1451  327
 ***************** Program SIGMA1 (VERSION 2002-1) ***************9346 1451  328
 Data Doppler Broadened to 300.000000 Kelvin                      9346 1451  329
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9346 1451  330
 Data Linearized to Within an Accuracy pf .100000000 per-cent     9346 1451  331
 ***************** Program FIXUP (Version 2002-1) ****************9346 1451  332
 Corrected ZA/AWR in All Sections-----------------------------Yes 9346 1451  333
 Corrected Thresholds-----------------------------------------Yes 9346 1451  334
 Extended Cross Sections to 20 MeV----------------------------No  9346 1451  335
 Allow Cross Section Deletion---------------------------------No  9346 1451  336
 Allow Cross Section Reconstruction---------------------------No  9346 1451  337
 Make All Cross Sections Non-Negative-------------------------Yes 9346 1451  338
 Delete Energies Not in Ascending Order-----------------------Yes 9346 1451  339
 Deleted Duplicate Points-------------------------------------Yes 9346 1451  340
 Check for Ascending MAT/MF/MT Order--------------------------Yes 9346 1451  341
 Check for Legal MF/MT Numbers--------------------------------Yes 9346 1451  342
 Allow Creation of Missing Sections---------------------------No  9346 1451  343
 Allow Insertion of Energy Points-----------------------------No  9346 1451  344
 Create Uniform Energy Grid-----------------------------------No  9346 1451  345
 Delete Section if Cross Section =0 at All Energies-----------Yes 9346 1451  346
 ***************** Program GROUPIE (VERSION 2002-1) **************9346 1451  347
 Unshielded Group Averages Using  640 Groups                      9346 1451  348
 Weighting Spectrum: Flat (Constant) Spectrum                     9346 1451  349
                                1        451        353          19346 1451  350
                                2        151          4          19346 1451  351
                                3         18        217          19346 1451  352
                               33         18        220          19346 1451  353
                                                                  9346 1  099999
                                                                  9346 0  0    0
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 9.32370E+4 1.00000E+0          0          0          1          09346 2151    2
 1.00000E-5 6.00000E+2          0          0          0          09346 2151    3
 2.50000E+0 9.54000E-1          0          0          0          09346 2151    4
                                                                  9346 2  099999
                                                                  9346 0  0    0
 9.32370E+4 2.35011E+2          0          0          0          09346 3 18    1
 1.96370E+8 1.96370E+8          0          0          1        6419346 3 18    2
        641          1                                            9346 3 18    3
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                                                                  9346 3  099999
                                                                  9346 0  0    0
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 1.00000+ 5 0.00000+ 0                                            934633 18    6
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 1.06327- 4 2.00867- 4 2.82548- 4 3.39481- 4 3.72530- 4 3.87081- 4934633 18  199
 3.88907- 4 3.77309- 4 3.51727- 4 9.64193- 4 9.01880- 4 6.57344- 4934633 18  200
 3.41072- 4 1.07066- 4 3.11372- 5 8.47740- 5 1.96925- 4 3.10075- 4934633 18  201
 3.95536- 4 4.45941- 4 4.64516- 4 4.58009- 4 4.14746- 4 3.25813- 4934633 18  202
 9.79517- 4 8.48395- 4 5.60783- 4 2.68204- 4 9.54045- 5 6.53598- 5934633 18  203
 1.30517- 4 2.32221- 4 3.30598- 4 4.06862- 4 4.56004- 4 4.79820- 4934633 18  204
 4.75834- 4 4.25947- 4 8.85772- 4 7.28861- 4 4.60726- 4 2.13428- 4934633 18  205
 6.81451- 5 3.16448- 5 7.13005- 5 1.50030- 4 2.40988- 4 3.28775- 4934633 18  206
 4.06173- 4 4.96655- 4 5.78294- 4 7.35670- 4 5.68859- 4 3.21582- 4934633 18  207
 1.03067- 4-2.84224- 5-6.78220- 5-3.62829- 5 4.05124- 5 1.41735- 4934633 18  208
 2.53158- 4 4.20532- 4 6.26698- 4 5.22812- 4 3.55656- 4 1.57839- 4934633 18  209
 2.11845- 6-8.22425- 5-9.78357- 5-6.04168- 5 1.27671- 5 1.07588- 4934633 18  210
 2.69172- 4 4.90480- 4 3.05310- 4 2.08198- 4 1.10496- 4 3.95566- 5934633 18  211
 3.42473- 6-1.04504- 6 1.90253- 5 5.63655- 5 1.32607- 4 2.49668- 4934633 18  212
 2.37424- 4 2.42348- 4 2.29411- 4 2.06211- 4 1.78849- 4 1.51149- 4934633 18  213
 1.25140- 4 9.14376- 5 5.55298- 5 3.49455- 4 4.09754- 4 4.23490- 4934633 18  214
 4.00001- 4 3.50544- 4 2.84715- 4 1.70068- 4 9.99255- 6 5.36145- 4934633 18  215
 5.97068- 4 6.00550- 4 5.60150- 4 4.89289- 4 3.47930- 4 1.33595- 4934633 18  216
 7.05793- 4 7.51272- 4 7.45658- 4 7.02138- 4 5.88980- 4 3.96187- 4934633 18  217
 8.46993- 4 8.93652- 4 9.01817- 4 8.60734- 4 7.52757- 4 1.00335- 3934633 18  218
 1.07891- 3 1.14035- 3 1.16290- 3 1.23137- 3 1.41398- 3 1.59674- 3934633 18  219
 1.79587- 3 2.24847- 3 3.07560- 3                                 934633 18  220
                                                                  934633  099999
                                                                  9346 0  0    0
                                                                     0 0  0    0
 9.42390E+4 2.36999E+2          0          1         34         109437 1451    1
 0.0        1.00000E+0          0          0          0          69437 1451    2
 1.00000E+0 2.00000E+7          0          0         10       20029437 1451    3
 3.00000E+2 0.0                 1          0        564          49437 1451    4
 94-Pu-239 NAIG       EVAL-MAR87 M.KAWAI, T.YOSHIDA, K.HIDA       9437 1451    5
                      DIST-Feb2004                                9437 1451    6
----IRDF-2002         MATERIAL 9437                               9437 1451    7
-----INCIDENT NEUTRON DATA                                        9437 1451    8
------ENDF-6 FORMAT                                               9437 1451    9
================================================================= 9437 1451   10
 94-PU-239 NAIG       EVAL-MAR87 M.KAWAI, T.YOSHIDA, K.HIDA       9437 1451   11
                      DIST-SEP89 REV2-FEB93                       9437 1451   12
----JENDL-3.2         MATERIAL 9437                               9437 1451   13
================================================================= 9437 1451   14
HISTORY                                                           9437 1451   15
87-03 EVALUATION WAS MADE BY                                      9437 1451   16
        M.KAWAI AND K.HIDA(NAIG) :  CROSS SECTIONS ABOVE          9437 1451   17
                      RESONANCE REGION AND OTHER QUANTITIES,      9437 1451   18
        T.YOSHIDA(NAIG) : RESONANCE PARAMETERS AND BACKGROUND     9437 1451   19
                      CROSS SECTIONS,                             9437 1451   20
      DATA WERE COMPILED BY T.NAKAGAWA (JAERI).                   9437 1451   21
88-08 PARTLY MODIFIED.                                            9437 1451   22
       NU-BAR, RESOLVED RESONS., (N,2N).                          9437 1451   23
89-02 FP YIELDS WERE TAKEN FROM JNDC FP DECAY DATA FILE VERSION-2.9437 1451   24
89-03 UNRESOLVED RESONANCE PARAMETERS WERE SLIGHTLY MODIFIED.     9437 1451   25
93-02 JENDL-3.2.                                                  9437 1451   26
      RESONANCE PARAMETERS EVALUATED BY H.DERRIEN (JAERI)/1/.     9437 1451   27
      FISSION SPECTRA CALCULATED BY T.OHSAWA (KINKI UNIV.)        9437 1451   28
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          9437 1451   29
                                                                  9437 1451   30
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  9437 1451   31
      (2,151)       RESOLVED RESONANCE PARAMETERS UP TO 2.5 KEV   9437 1451   32
     ***********************************************************  9437 1451   33
                                                                  9437 1451   34
                                                                  9437 1451   35
MF=1  GENERAL INFORMATION                                         9437 1451   36
  MT=451  DESCRIPTIVE DATA AND DICTIONARY                         9437 1451   37
                                                                  9437 1451   38
MF=2  RESONANCE PARAMETERS                                        9437 1451   39
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             9437 1451   40
   RESOLVED RES. PARAMETERS FOR REICH-MOORE FORMULA: UP TO 2.5 KEV9437 1451   41
      PARAMETERS WERE TAKEN FROM REF./1/ DETAILS OF EVALUATION    9437 1451   42
      ARE GIVEN IN APPENDIX.                                      9437 1451   43
   UNRESOLVED RESONANCES : FROM 2.5 TO 30 KEV.                    9437 1451   44
      THE ENERGY DEPENDENT S0, S1 AND FISSION WIDTH WERE DETER-   9437 1451   45
      MINED SO AS TO REPRODUCE THE EVALUATED TOTAL, CAPTURE AND   9437 1451   46
      FISSION CROSS SECTIONS.                                     9437 1451   47
                                                                  9437 1451   48
   2200-M/SEC CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS.  9437 1451   49
                       2200 M/S          RES. INTEG.              9437 1451   50
         TOTAL       1025.7   B             -                     9437 1451   51
         ELASTIC        7.970 B             -                     9437 1451   52
         FISSION      747.4   B            302.6 B                9437 1451   53
         CAPTURE      270.3   B            181.6 B                9437 1451   54
                                                                  9437 1451   55
MF=3  NEUTRON CROSS SECTIONS                                      9437 1451   56
     BELOW 2.5 KEV, CROSS SECTIONS WERE REPRESENTED WITH THE      9437 1451   57
     RESOLVED RESONANCE PARAMETERS.  BETWEEN 2.5 AND 30 KEV, CROSS9437 1451   58
     SECTIONS WERE REPLACED WITH UNRESOLVED RESONANCE PARAMETERS. 9437 1451   59
                                                                  9437 1451   60
  MT=1  TOTAL                                                     9437 1451   61
     BELOW 7 MEV, JENDL-2 EVALUATION WHICH WERE BASED ON THE      9437 1451   62
     EXPERIMENTS OF REFS./10,11,12,13,14/ WAS ADOPTED.  ABOVE     9437 1451   63
     7 MEV, EXPERIMENTAL DATA BY POENITZ /15/ WERE ADOPTED.       9437 1451   64
                                                                  9437 1451   65
  MT=2  ELASTIC SCATTERING                                        9437 1451   66
     CALCULATED AS (TOTAL) - (PARTIAL CROSS SECTIONS).            9437 1451   67
                                                                  9437 1451   68
  MT=18   FISSION                                                 9437 1451   69
     BELOW  50 KEV                                                9437 1451   70
        BASED ON MEASUREMENTS OF REF./31/ AND REF./32/.           9437 1451   71
     ABOVE  50 KEV                                                9437 1451   72
        SIMULTANEOUS EVALUATION WAS PERFORMED BY KANDA ET AL./33/ 9437 1451   73
                                                                  9437 1451   74
MF=33  COVARIANCES                                                9437 1451   75
  MT=18                                                           9437 1451   76
     TAKEN FROM JENDL/D-99.                                       9437 1451   77
                                                                  9437 1451   78
REFERENCES                                                        9437 1451   79
 1) DERRIEN H.: J. NUCL. SCI. TECHNOL., 30, 845 (1993).           9437 1451   80
10) UTTELY C.A.: EANDC(UK)-40 (1964).                             9437 1451   81
11) SCHWARTZ R.B. ET AL.: NUCL. SCI. ENG., 54, 322 (1974).        9437 1451   82
12) FOSTER D.G.JR. AND GLAGOW D.W.: PHYS. REV., C3, 576 (1971).   9437 1451   83
13) SMITH A.B. ET AL.: J. NUCL. ENERGY, 27, 317 (1973).           9437 1451   84
14) NADOLNY ET AL.: C00-3058-39, 33 (1973).                       9437 1451   85
15) POENITZ W.P. ET AL.: NUCL. SCI. ENG., 78, 333 (1981).         9437 1451   86
31) GAYTHER D.B.: 1975 WASHINGTON, 2, 560 (1975).                 9437 1451   87
32) WAGEMANS C. ET AL.: ANN. NUCL. ENERGY, 7, 495 (1980).         9437 1451   88
                                                                  9437 1451   89
                                                                  9437 1451   90
================================================================= 9437 1451   91
APPENDIX          RESONANCE DATA                                  9437 1451   92
================================================================= 9437 1451   93
                                                                  9437 1451   94
     THE PRESENT FILE CONTAINS THE RESONANCE PARAMETERS OBTAINED  9437 1451   95
FROM A SAMMY FIT ANALYSIS OF HIGH RESOLUTION EXPERIMENTAL DATA,   9437 1451   96
PERFORMED AT ORNL(OAK RIDGE NATIONNAL LABORATORY,USA) BY H.DERRIEN9437 1451   97
AND G.DE SAUSSURE AND AT JAERI(TOKAI-MURA RESEARCH ESTABLISHMENT, 9437 1451   98
JAPAN) BY H.DERRIEN.                                              9437 1451   99
   THE FILE CONTAINS THREE INDEPENDANT SECTIONS:                  9437 1451  100
   1/ THE FIRST CORRESPONDS TO THE ENERGY RANGE 0 KEV TO 1 KEV.   9437 1451  101
THE CORRESPONDING SET OF RESONANCE PARAMETRES CONTAINS 398 RESO-  9437 1451  102
NANCES IN THE ENERGY RANGE 0 KEV TO 1 KEV, 4 FICTICIOUS NEGATIVE  9437 1451  103
ENERGY RESONANCES AND 3 FICTICIOUS RESONANCES ABOVE 1 KEV;        9437 1451  104
   2/ THE SECOND CORRESPONDS TO THE ENERGY RANGE 1 KEV TO 2 KEV.  9437 1451  105
THE CORRESPONDING SET OF RESONANCE PARAMETERS CONTAINS 435 RESON- 9437 1451  106
ANCES IN THE ENERGY RANGE 0.980 KEV TO 2.02 KEV, 3 FICTICIOUS     9437 1451  107
RESONANCES BELOW 0.9 KEV AND 3 FICTICIOUS RESONANCES ABOVE 2.02   9437 1451  108
KEV;                                                              9437 1451  109
   3/ THE THIRD CORRESPONDS TO THE ENERGY RANGE 2 KEV TO 2.5 KEV. 9437 1451  110
THE CORRESPONDING SET OF RESONANCE PARAMETERS CONTAINS 218 RESO-  9437 1451  111
NANCES IN THE ENERGY RANGE 1.98 KEV TO 2.53 KEV, 3 FICTICIOUS     9437 1451  112
RESONANCES BELOW 1.98 KEV AND 3 FICTICIOUS RESONANCES ABOVE 2.53  9437 1451  113
KEV.                                                              9437 1451  114
   IN ALL SECTIONS THE FICTICIOUS RESONANCE PARAMETERS TAKE INTO  9437 1451  115
ACCOUNT THE CONTRIBUTION OF ALL THE EXTERNAL TRUNCATED RESONANCES 9437 1451  116
IN SUCH A WAY THAT NO TOTAL, SCATTERING, FISSION AND CAPTURE      9437 1451  117
SMOOTH FILES ARE NEEDED IN THE CORRESPONDING ENERGY RANGES FOR THE9437 1451  118
REPRODUCTION OF THE CROSS SECTIONS WITHIN THE EXPERIMENTAL ERRORS.9437 1451  119
   THE FOLLOWING EXPERIMENTAL DATA BASE HAS BEEN USED IN THE SAMMY9437 1451  120
FITS:                                                             9437 1451  121
  -ABSORPTION AND FISSION FROM R.GWIN ET AL./1,2/;                9437 1451  122
  -FISSION FROM R.GWIN ET AL./3,4/, J.BLONS/5/, L.W.WESTON ET     9437 1451  123
   AL./6,7/;                                                      9437 1451  124
  -TRANSMISSION FROM R.R.SPENCER ET AL./8/, J.A.HARVEY ET AL./9/  9437 1451  125
PRIOR TO THE FITS THE EXPERIMENTAL FISSION AND ABSORPTION CROSS   9437 1451  126
SECTIONS WERE NORMALISED, DIRECTLY OR INDIRECTLY TO THE 0.0253 EV 9437 1451  127
VALUES OBTAINED BY THE ENDF/B-VI STANDARD EVALUATION GROUP/10/.   9437 1451  128
THE TRANSMISSION DATA WERE CONSIDERED AS ACCURATE ABSOLUTE MEASU- 9437 1451  129
REMENTS(R.R.SPENCER TOTAL CROSS SECTION AT 0.0253 EV IS 1025.0 B  9437 1451  130
IN EXCELLENT AGREEMENT WITH THE 1027.3 B STANDARD VALUE).         9437 1451  131
   DETAILS ON THE ANALYSIS ARE FOUND IN REFERENCES/11,12,13/      9437 1451  132
                                                                  9437 1451  133
***************************************************************** 9437 1451  134
         COMMENTS ON THE THERMAL AND LOW ENERGY RANGES            9437 1451  135
***************************************************************** 9437 1451  136
                                                                  9437 1451  137
     THE THERMAL CROSS SECTION VALUES CALCULATED AT 293 K BY THE  9437 1451  138
RESONANCE PARAMETERS OF THE FIRST SECTION ARE GIVEN IN THE FOLLO- 9437 1451  139
WING TABLE:                                                       9437 1451  140
                                                                  9437 1451  141
                                                                  9437 1451  142
              SAMMY      RESENDD              PROPOSED            9437 1451  143
                  293 K (BARN)        STANDARD VALUES(BARN)/10/   9437 1451  144
****************************************************************  9437 1451  145
FISSION       747.64     747.90           747.99+-1.87            9437 1451  146
CAPTURE       271.10     270.73           271.43+-2.14            9437 1451  147
SCATTERING      7.97       7.99             7.88+-0.97            9437 1451  148
TOTAL        1026.71    1026.62          1027.30+-5.00            9437 1451  149
****************************************************************  9437 1451  150
                                                                  9437 1451  151
     ONE SHOULD NOTE THAT THE 293 K CROSS SECTIONS CALCULATED AT  9437 1451  152
0.0253 EV DEPEND ON THE WAY THE DOPPLER BROADENING CALCULATION IS 9437 1451  153
PERFORMED. FOR INSTANCE USING A GAUSSIAN BROADENING FUNCTION WILL 9437 1451  154
GIVE A FISSION CROSS SECTION ABOUT 2.5 BARNS LARGER THAN THE ONE  9437 1451  155
OBTAINED FROM THE ACCURATE CALCULATION WHICH CONSERVES THE 1/V    9437 1451  156
SHAPE OF THE THERMAL CROSS SECTION. THE VALUES GIVEN IN THE TABLE 9437 1451  157
ABOVE WERE OBTAINED FROM SAMMY (LEAL-HWANG METHOD)/14,15/ AND FROM9437 1451  158
RESENDD WITH 0.1% FOR THE INTERPOLATION ACCURACY/16/.             9437 1451  159
    THE FOLLOWING TABLE SHOWS EXPERIMENTAL CROSS SECTIONS AVE-    9437 1451  160
RAGED OVER THE ENERGY RANGES 0.02 EV TO 0.06 EV AND 0.02 EV TO    9437 1451  161
0.65 EV, COMPARED TO THE CALCULATED VALUES:                       9437 1451  162
                                                                  9437 1451  163
                                                                  9437 1451  164
                  AVERAGE CROSS-SECTIONS(BARN)                    9437 1451  165
****************************************************************  9437 1451  166
 REFERENCES(1-10)   0.02 TO 0.06 EV        0.02 TO 0.65 EV        9437 1451  167
****************************************************************  9437 1451  168
                   EXP     CALC (293K)     EXP    CALC (293K)     9437 1451  169
GWIN71 FISS       631.41                  843.71                  9437 1451  170
GWIN76 FISS       631.41                  838.39                  9437 1451  171
GWIN84 FISS(*)    631.41  631.75(+0.05%)  837.18  838.69(+0.18%)  9437 1451  172
DERUYTER70 FISS   631.41                  859.43                  9437 1451  173
WAGEMANS80 FISS   631.41                  862.56                  9437 1451  174
WAGEMANS88 FISS   631.41                  841.80                  9437 1451  175
GWIN71 CAPTURE    243.84  243.22(-0.25%)  524.75  518.13(-1.26%)  9437 1451  176
GWIN76 ABSORPT(*) 875.90  874.29(-0.18%) 1359.96 1357.14(-0.21%)  9437 1451  177
SPENCER84 TOT(*)  883.20  882.86(-0.04%) 1361.69 1367.6 (+0.43%)  9437 1451  178
****************************************************************  9437 1451  179
(*)THESE DATA HAD THE LARGIEST WEIGHT IN THE THERMAL FIT. THE VA- 9437 1451  180
LUES BETWEEN THE PARENTHESES GIVE THE PERCENTAGE DEVIATION BETWEEN9437 1451  181
THE CALCULATED DATA AND THE EXPERIMENTAL DATA.                    9437 1451  182
***************************************************************** 9437 1451  183
                                                                  9437 1451  184
     THE VALUE OF 631.4 BARNS FOR ALL THE AVERAGED EXPERIMENTAL   9437 1451  185
FISSION CROSS SECTIONS IN THE ENERGY RANGE 0.02 EV TO 0.06 EV     9437 1451  186
CORRESPONDS TO THE RENORMALISATION OF THE FISSION EXPERIMENTS TO  9437 1451  187
748.0+-1. BARNS AT 0.0253 EV. ORNL DATA ARE CONSISTENT WITHIN 0.8%9437 1451  188
OVER THE ENERGY RANGE 0.02 EV TO 0.65 EV (I.E. OVER THE 0.3 EV    9437 1451  189
RESONANCE). DERUYTER 1970 AND WAGEMANS 1980 DATA ARE ABOUT 2.5%   9437 1451  190
LARGER AND WERE NOT INCLUDED IN THE SAMMY FIT. WHEN NORMALIZED ON 9437 1451  191
THE STANDARD VALUE AT 0.0253 EV, GWIN 76 ABSORPTION AGREES WITH   9437 1451  192
THE ABSORPTION OBTAINED FROM SPENCER TOTAL CROSS SECTION WITHIN   9437 1451  193
0.7% OVER THE 0.3 EV RESONANCE. THE PRESENT EVALUATION IS         9437 1451  194
ESSENTIALLY THE RESULT OF A CONSISTENT SAMMY ANALYSIS OF ALL THE  9437 1451  195
AVAILABLE ORNL DATA WITH A LARGER WEIGHT ON GWIN 1984 FISSION,    9437 1451  196
GWIN 1976 ABSORPTION AND SPENCER TRANSMISSION DATA.               9437 1451  197
     AFTER RENORMALIZATION OF THE CALCULATED FISSION CROSS SECTION9437 1451  198
ON THE PRELIMINARY 1991 WESTON AND TODD FISSION DATA(SEE NEXT     9437 1451  199
SECTION) A SLIGHT ADJUSTMENT OF THE NEGATIVE RESONANCE PARAMETERS 9437 1451  200
WAS PERFORMED TO KEEP THE VALUES CALCULATED AT 0.0253 EV IN CLOSE 9437 1451  201
AGREEMENT WITH THE STANDARD VALUES. THE 1988 DATA OF WAGEMANS ET  9437 1451  202
AL./17/ AGREE WITHIN 0.4% WITH THE CALCULATED VALUES OVER THE     9437 1451  203
ENERGY RANGE FROM 0.02 EV TO 0.65 EV AFTER ADJUSTMENT OF THE      9437 1451  204
ENERGY SCALE TO THE ORNL SCALE (THE DIFFERENCE WAS 0.27 EV AT 20  9437 1451  205
EV BETWEEN 1988 WAGEMANS AND ORNL SAMMY FIT ENERGY SCALES).       9437 1451  206
                                                                  9437 1451  207
***************************************************************** 9437 1451  208
         COMMENTS ON THE 0 KEV TO 1 KEV ENERGY RANGE.             9437 1451  209
***************************************************************** 9437 1451  210
                                                                  9437 1451  211
   AT THE END OF 1987, AN ANALYSIS WAS COMPLETED UP TO 1 KEV. IN A9437 1451  212
PRELIMINARY STEP, A CORRELATED FIT OF HARVEY TRANSMISSION DATA,   9437 1451  213
WESTON 84 FISSION DATA AND BLONS FISSION DATA WAS PERFORMED, WITH 9437 1451  214
POSSIBLE ADJUSTMENT OF THE NORMALIZATION COEFFICIENTS AND OF THE  9437 1451  215
BACKGROUND CORRECTIONS. THIS PRELIMINARY STEP HAS SHOWN THAT THIS 9437 1451  216
ADJUSTMENT WAS NOT NECESSARY TO HAVE CONSISTENCY BETWEEN HARVEY   9437 1451  217
DATA AND WESTON DATA. BLONS DATA NEEDED A LARGE READJUSTMENT OF   9437 1451  218
THE BACKGROUND AND OF THE NORMALIZATION. THEREFORE, THE FINAL FIT 9437 1451  219
WAS PERFORMED ONLY ON HARVEY TRANSMISSION DATA, GWIN 84 FISSION   9437 1451  220
DATA (BELOW 30 EV) AND WESTON 84 FISSION DATA, WITH NO BACKGROUND 9437 1451  221
AND NORMALISATION ADJUSTMENT. BLONS DATA, WHICH HAVE BETTER       9437 1451  222
RESOLUTION THAN WESTON 84 DATA, WERE USED ONLY TO OBTAIN MORE     9437 1451  223
ACCURATE FISSION WIDTHS OF SOME NARROW RESONANCES IN THE HIGH     9437 1451  224
ENERGY RANGE.                                                     9437 1451  225
   IN 1989, PRELIMINARY RESULTS OF THE 1988 WESTON FISSION        9437 1451  226
MEASUREMENT/7/ WERE INCLUDED IN THE SAMMY EXPERIMENTAL DATA       9437 1451  227
BASE.  ONE EXPECTED FROM THIS MEASUREMENT, WHICH WAS PERFORMED BY 9437 1451  228
USING A 86 M FLIGHT PATH WITH A RESOLUTION COMPARABLE TO THE      9437 1451  229
RESOLUTION OF HARVEY TRANSMISSION, A CONFIRMATION OF THE EXCELLENT9437 1451  230
QUALITY OF THE 1984 MEASUREMENT. A CONSISTENT SAMMY FIT OF HARVEY 9437 1451  231
TRANSMISSION, WESTON 84 FISSION AND PRELIMINARY WESTON 88 FISSION 9437 1451  232
WAS RESTARTED FROM THE PARAMETER AND COVARIANCE FILES OBTAINED IN 9437 1451  233
1987.  IT APPEARED THAT LARGE BACKGROUND AND NORMALISATION        9437 1451  234
CORRECTIONS WERE NEEDED ON THE NEW WESTON FISSION TO OBTAIN       9437 1451  235
CONSISTENCY WITH HARVEY TRANSMISSION DATA. THESE CORRECTIONS WERE 9437 1451  236
COMPARABLE TO THOSE FOUND ON BLONS DATA AND WERE NOT UNDERSTOOD BY9437 1451  237
THE AUTHORS OF THE EXPERIMENT. THE LAST SAMMY RUNS WERE PERFORMED 9437 1451  238
BY NOT ALLOWING BACKGROUND AND NORMALIZATION VARIATIONS ON HARVEY 9437 1451  239
TRANSMISSION AND WESTON 84 FISSION(VERY SMALL ERROR BARS WERE     9437 1451  240
ASSIGNED TO THE CORRESPONDING PARAMETERS IN THE COVARIANCE MATRIX)9437 1451  241
AND BY ALLOWING THESE VARIATIONS ON WESTON 88 DATA. A NEW SET OF  9437 1451  242
RESONANCE PARAMETERS WAS OBTAINED,WHICH WAS IMPROVED COMPARED TO  9437 1451  243
THE PREVIOUS SET DUE TO THE VERY HIGH RESOLUTION OF THE NEW WESTON9437 1451  244
FISSION MEASUREMENT.                                              9437 1451  245
   THE CALCULATED AVERAGE FISSION CROSS SECTION IN THE ENERGY     9437 1451  246
RANGE FROM 0.1 KEV TO 1.0 KEV WAS 3.7% SMALLER THAN THE VALUES    9437 1451  247
OBTAINED BY THE ENDF/B-VI STANDARD EVALUATION GROUP, DUE TO THE   9437 1451  248
FACT THAT WESTON 84 DATA WERE 3.1% LOWER THAN THE AVERAGE STANDARD9437 1451  249
VALUE. A NEW MEASUREMENT WAS PERFORMED BY WESTON AND TODD IN 1991 9437 1451  250
/18/ IN ORDER TO CHECK THEIR 1984 DATA. A CAREFUL NORMALIZATION   9437 1451  251
OF THE DATA IN THE THERMAL ENERGY RANGE SHOWED THAT THE 1984 DATA 9437 1451  252
SHOULD BE RENORMALIZED BY ABOUT +3%. TO TAKE INTO ACCOUNT THIS    9437 1451  253
RENORMALIZATION, THE 1989 RESONANCE PARAMETERS WERE MODIFIED AT   9437 1451  254
JAERI/13/ IN THE FOLLOWING WAY:                                   9437 1451  255
   1/ INCREASE OF THE FISSION WIDTH BY 3% AND DECREASE OF THE     9437 1451  256
CAPTURE WIDTH BY A QUANTITY EQUAL TO THE VARIATION OF THE FISSION 9437 1451  257
WIDTH, IN THE NARROW RESONANCES(MAINLY 1+ RESONANCES); THAT DOES  9437 1451  258
NOT MODIFY THE TOTAL CROSS SECTION IN THE CORRESPONDING           9437 1451  259
RESONANCES;                                                       9437 1451  260
   2/ ADJUSTMENT OF THE NEUTRON WIDTH OF THE 0+ RESONANCES BY A   9437 1451  261
REFIT OF THE TRANSMISSION DATA AND OF THE RENORMALIZED WESTON AND 9437 1451  262
TODD 1984 DATA IN ENERGY RANGES WHERE THE CONTRIBUTION OF THE 0+  9437 1451  263
RESONANCES IS DOMINANT, AND INCREASE OF THE OTHER(SMALL) 0+       9437 1451  264
NEUTRON WIDTHS BY 3%. NO SEVERE INCONSISTENCY WAS OBSERVED BETWEEN9437 1451  265
THE TRANSMISSION DATA AND THE NEW FISSION DATA OVER THE DOMINANT  9437 1451  266
0+ RESONANCES;THE DIFFERENCES BETWEEN THE 1989 FITS OF THE TRANS- 9437 1451  267
MISSION AND THE NEW FITS WERE CONSISTENT WITHIN THE EXPERIMENTAL  9437 1451  268
ERROR BARS.                                                       9437 1451  269
   THE FOLLOWING TABLE SHOWS THE FISSION CROSS SECTIONS CALCULA-  9437 1451  270
TED FROM THE RESONANCE PARAMETERS, THE EXPERIMENTAL VALUES AND THE9437 1451  271
RESULTS OF THE ENDF/B-VI STANDARD EVALUATION GROUP AVERAGED IN THE9437 1451  272
SAME ENERGY INTERVALS. WESTON 1991 DATA ARE PRELIMINARY. WESTON   9437 1451  273
1984 DATA ARE NORMALIZED ON PRELIMINARY WESTON 1991:              9437 1451  274
                                                                  9437 1451  275
                           CROSS-SECTIONS(BARN)                   9437 1451  276
         *************************************************        9437 1451  277
            ENERGY    CALCUL   WESTON   WESTON   STANDARD         9437 1451  278
             (EV)               1991     1984                     9437 1451  279
         *************************************************        9437 1451  280
          0.010-10.    80.12    79.98                             9437 1451  281
              9-20     94.74    94.91                             9437 1451  282
             20-40     17.52    17.76    17.97                    9437 1451  283
             40-60     50.64    50.90    50.87                    9437 1451  284
             60-100    54.42    54.38    54.33                    9437 1451  285
            100-200    18.63    18.59    18.56    18.66           9437 1451  286
            200-300    17.85             17.89    17.88           9437 1451  287
            300-400     8.31              8.34     8.43           9437 1451  288
            400-500     9.59              9.58     9.57           9437 1451  289
         -------------------------------------------------        9437 1451  290
            200-500    11.92    11.93    11.93    11.96           9437 1451  291
         -------------------------------------------------        9437 1451  292
            500-600    15.39             15.57    15.86           9437 1451  293
            600-700     4.37              4.30     4.46           9437 1451  294
            700-800     5.51              5.53     5.63           9437 1451  295
            800-900     4.84              4.89     4.98           9437 1451  296
            900-1000    8.33              8.38     8.30           9437 1451  297
         -------------------------------------------------        9437 1451  298
            500-1000    7.69     7.73     7.73     7.79           9437 1451  299
         -------------------------------------------------        9437 1451  300
             20-1000   13.09    13.11    13.11                    9437 1451  301
         **************************************************       9437 1451  302
                                                                  9437 1451  303
                                                                  9437 1451  304
   GWIN 1971 AND 1976 ABSORPTION DATA WERE NOT INCLUDED IN THE    9437 1451  305
SAMMY FIT IN THE ENERGY RANGE ABOVE 1 EV. ACCURATE ABSORPTION     9437 1451  306
CROSS SECTIONS SHOULD BE CALCULATED FROM THE PARAMETERS OBTAINED  9437 1451  307
FROM THE ANALYSIS OF THE TRANSMISSION AND FISSION DATA. THE FOLLO-9437 1451  308
WING TABLE SHOWS THE CALCULATED AVERAGE VALUES OF THE CAPTURE, AB-9437 1451  309
SORPTION AND ALPHA COMPARED TO GWIN 1971 AND GWIN 1976 DATA. THE  9437 1451  310
CALCULATIONS WERE PERFORMED WITH RESENDD, 1.0 % ACCURACY:         9437 1451  311
                                                                  9437 1451  312
                     CROSS-SECTIONS(BARN)                         9437 1451  313
    *******************************************************       9437 1451  314
      ENERGY(EV)   CALC. VALUES (293K)     GWIN DATA              9437 1451  315
    *******************************************************       9437 1451  316
                  CAPT   ABSORP ALPHA     ABSORP ALPHA            9437 1451  317
       7.3- 16.0  76.61  196.04  0.64     208.00  0.74(*)         9437 1451  318
      16.0- 37.5  20.51   44.55  0.85      46.50  0.89(*)         9437 1451  319
      37.5- 50.0  48.72   70.00  2.29      83.15  2.96(*)         9437 1451  320
      50.0-100.0  33.60   92.13  0.57      92.84  0.63            9437 1451  321
     100.0-200.0  15.58   34.29  0.83      33.66  0.87            9437 1451  322
     200.0-300.0  15.85   33.68  0.89      34.69  0.94            9437 1451  323
     300.0-400.0   9.69   18.01  1.16      18.31  1.16            9437 1451  324
     400.0-500.0   3.96   13.56  0.41      13.56  0.44            9437 1451  325
     500.0-600.0  10.87   26.30  0.70      26.54  0.72            9437 1451  326
     600.0-700.0   6.53   10.90  1.49      11.57  1.54            9437 1451  327
     700.0-800.0   4.95   10.47  0.90      10.52  0.97            9437 1451  328
     800.0-900.0   3.65    8.50  0.75       9.30  0.82            9437 1451  329
     900.0-999.9   5.06   13.51  0.60      13.23  0.70            9437 1451  330
    ******************************************************        9437 1451  331
     (*) GWIN 1971 DATA                                           9437 1451  332
                                                                  9437 1451  333
   IF ONE EXCEPTS THE ENERGY RANGE 37.5-50 EV, THE CALCULATED AB- 9437 1451  334
SORPTION VALUES AGREE WELL WITH GWIN EXPERIMENTAL DATA; THEY ARE  9437 1451  335
ON AVERAGE 1.2% LOWER IN THE ENERGY RANGE FROM 50 EV TO 1000 EV.  9437 1451  336
                                                                  9437 1451  337
***************************************************************** 9437 1451  338
      COMMENTS ON THE 1 KEV TO 2 KEV ENERGY RANGE                 9437 1451  339
***************************************************************** 9437 1451  340
                                                                  9437 1451  341
   PRELIMINARY RESONANCE PARAMETERS WERE OBTAINED IN 1989 FROM THE9437 1451  342
ANALYSIS OF THE HARVEY THICK SAMPLE TRANSMISSION DATA AND OF THE  9437 1451  343
PRELIMINARY RESULTS OF WESTON 88 FISSION MEASUREMENT.  DUE TO LACK9437 1451  344
OF TIME, THE MEDIUM AND THIN SAMPLE TRANSMISSION DATA WERE NOT    9437 1451  345
INCLUDED IN THE SAMMY DATA BASE, AND THE CONTRIBUTION OF THE      9437 1451  346
TRUNCATED EXTERNAL RESONANCES WAS NOT CAREFULLY INVESTIGATED.     9437 1451  347
NEVERTHELESS, THE RESULTS WERE USED IN THE ENDF/B-VI FILE, ALONG  9437 1451  348
WITH A SMOOTH FILE IN ORDER TO AGREE WITH THE AVERAGE VALUES OF A 9437 1451  349
PREVIOUS ENDF/B-VI EVALUATION (THIS PRELIMINARY SET OF PARAMETERS 9437 1451  350
WAS CONSIDERED AS MORE USEFUL THAN THE STATISTICAL PARAMETERS IN  9437 1451  351
THE ENERGY RANGE 1 KEV TO 2 KEV FOR THE CALCULATION OF THE SELF-  9437 1451  352
SHIELDING FACTORS).                                               9437 1451  353
   THE ANALYSIS WAS RESTARTED IN APRIL 1991 AT JAERI(TOKAI        9437 1451  354
RESEARCH ESTABLISHMENT) WITH AN UPDATED VERSION OF SAMMY ADAPTED  9437 1451  355
BY T.NAKAGAWA TO THE FACOM 780. THE PRELIMINARY SET OF PARAMETERS 9437 1451  356
OBTAINED AT OAK RIDGE IN 1989 WAS USED AS PRIOR INFORMATIONS TO   9437 1451  357
START THE SAMMY CALCULATIONS. ALSO PRIOR TO THE ANALYSIS, THE CON-9437 1451  358
TRIBUTION OF THE EXTERNAL RESONANCES WAS CALCULATED BY USING THE  9437 1451  359
SET OF THE 0 KEV TO 1 KEV KNOWN RESONANCES, SHIFTED IN THE ENERGY 9437 1451  360
RANGES -1 KEV TO 0 KEV, 2 KEV TO 3KEV AND 3 KEV TO 4 KEV; EQUIVA- 9437 1451  361
LENT CONTRIBUTION WAS OBTAINED BY USING 3 FICTICIOUS RESONANCES   9437 1451  362
BELOW 1 KEV AND 3 FICTICIOUS RESONANCES ABOVE 2 KEV(SEE DETAILS IN9437 1451  363
REF./13/). THE ANALYSIS WAS PERFORMED ON THE THICK AND MEDIUM     9437 1451  364
SAMPLE TRANSMISSIONS OF HARVEY DATA (THE THIN SAMPLE DATA WAS NOT 9437 1451  365
USEFUL IN THE HIGH ENERGY RANGE) AND ON THE 1988 FISSION DATA RE- 9437 1451  366
LEASED BY WESTON AT THE BEGINNING OF 1991/7/. THE DEFINITIVE      9437 1451  367
SAMMY FITS WERE PERFORMED IN APRIL 1992 AFTER RENORMALIZATION OF  9437 1451  368
THE 1988 DATA OF WESTON ON THE ENDF/B-VI STANDARD VALUES BETWEEN 19437 1451  369
KEV AND 2 KEV, IN AGREEMENT WITH THE 1991 NEW MEASUREMENTS OF     9437 1451  370
WESTON AND TODD.                                                  9437 1451  371
   THE AVERAGE CROSS SECTIONS CALCULATED FROM THE RESONANCE       9437 1451  372
PARAMETERS ARE COMPARED TO THE EXPERIMENTAL VALUES IN THE FOLLO-  9437 1451  373
WING TABLE:                                                       9437 1451  374
                                                                  9437 1451  375
                                                                  9437 1451  376
**************************************************************    9437 1451  377
                        CROSS-SECTIONS(BARN)                      9437 1451  378
           ---------------------------------------------------    9437 1451  379
                 TOTAL           FISSION         CAPTURE          9437 1451  380
  ENERGY    --------------    -------------    -------------      9437 1451  381
   KEV     CALC(A)   EXP(B)  CALC(A)   EXP(C) CALC(A)  EXP(D)     9437 1451  382
**************************************************************    9437 1451  383
  1.0-1.1   24.47    24.95    5.549    5.581   4.728   5.04       9437 1451  384
  1.1-1.2   22.82    23.10    5.985    6.017   3.757   2.95       9437 1451  385
  1.2-1.3   22.29    22.90    4.601    4.501   4.287   4.00       9437 1451  386
  1.3-1.4   22.63    22.85    6.997    6.997   3.012   2.52       9437 1451  387
  1.4-1.5   20.42    20.95    4.041    4.059   3.450   3.57       9437 1451  388
  1.5-1.6   18.30    18.95    2.564    2.613   3.521   3.89       9437 1451  389
  1.6-1.7   21.82    21.90    3.952    3.955   3.833   4.36       9437 1451  390
  1.7-1.8   21.26    21.35    3.400    3.425   4.091   4.37       9437 1451  391
  1.8-1.9   23.76    23.30    5.178    5.187   3.639   3.14       9437 1451  392
  1.9-2.0   18.48    18.90    2.152    2.180   3.205   4.06       9437 1451  393
**************************************************************    9437 1451  394
  1.0-2.0   21.63    21.92    4.442    4.446   3.752   3.79       9437 1451  395
**************************************************************    9437 1451  396
 (A) TOTAL, FISSION AND CAPTURE CROSS SECTIONS CALCULATED BY      9437 1451  397
     RESENDD FROM THE RESONANCE PARAMETERS.                       9437 1451  398
 (B) EXPERIMENTAL TOTAL CROSS SECTIONS FROM REFERENCE/19/.        9437 1451  399
 (C) WESTON AND TODD 1988 HIGH RESOLUTION FISSION CROSS SECTIONS  9437 1451  400
     FROM REFERENCE/7/ NORMALIZED TO ENDF/B-VI STANDARD IN THE    9437 1451  401
     ENERGY RANGE FROM 1.0 KEV TO 2.0 KEV.                        9437 1451  402
 (D) GWIN 1971 EXPERIMENTAL DATA NORMALIZED TO GWIN 1976 DATA.    9437 1451  403
**************************************************************    9437 1451  404
                                                                  9437 1451  405
   THE DIFFERENCE OF 1.3% BETWEEN THE AVERAGE CALCULATED TOTAL    9437 1451  406
CROSS SECTION AND THE AVERAGE EXPERIMENTAL CROSS SECTION IN THE   9437 1451  407
ENERGY RANGE FROM 1.0 KEV AND 2.0 KEV IS MAINLY DUE TO THE METHOD 9437 1451  408
OF EVALUATING THE TOTAL CROSS SECTION FROM THE EFFECTIVE CROSS    9437 1451  409
SECTION IN REFERENCE/19/. THE ACCURACY OF THE SAMMY FIT OF THE    9437 1451  410
EXPERIMENTAL TRANSMISSION DATA IS BETTER THAN 0.5% ON THE CROSS   9437 1451  411
SECTION. THE CALCULATED FISSION CROSS SECTIONS ARE IN VERY GOOD   9437 1451  412
AGREEMENT WITH THE EXPERIMENTAL DATA. THE CAPTURE DATA /1/ ARE    9437 1451  413
AVERAGE VALUES OBTAINED FROM THE DATA AVAILABLE IN THE EXFOR FILE 9437 1451  414
AND NORMALIZED TO GWIN 1976 AVERAGE VALUES; THERE ARE LARGE       9437 1451  415
DIFFERENCES BETWEEN THE CALCULATED DATA AND THE EXPERIMENTAL DATA 9437 1451  416
AVERAGED OVER 0.1 KEV INTERVALS; BUT ON THE INTERVAL FROM 1.0 KEV 9437 1451  417
TO 2.0 KEV THE AVERAGE VALUES ARE CONSISTENT WITHIN 1.0%.         9437 1451  418
                                                                  9437 1451  419
***************************************************************** 9437 1451  420
   COMMENTS ON THE 2.0 KEV TO 2.5 KEV REGION                      9437 1451  421
***************************************************************** 9437 1451  422
                                                                  9437 1451  423
   THIS ENERGY RANGE WAS ALSO ANALYSED AT JAERI /13/. NO          9437 1451  424
PRELIMINARY SET OF RESONANCE PARAMETERS WAS AVAILABLE PRIOR TO THE9437 1451  425
ANALYSIS. MORE THAN 90% OF THE RESONANCES, COMPARED TO THE LOW    9437 1451  426
ENERGY RANGE, COULD STILL BE IDENTIFIED IN THE TRANSMISSION DATA  9437 1451  427
BETWEEN 2 KEV AND 2.5 KEV. THEREFORE THE CORRELATED SAMMY ANALYSIS9437 1451  428
OF HARVEY TRANSMISSIONS AND WESTON FISSION WAS STILL FEASIBLE IN  9437 1451  429
THIS ENERGY RANGE. THE RESONANCE PARAMETERS OBTAINED ARE          9437 1451  430
CONSISTENT AND HAS NEARLY THE SAME STATISTICAL PROPERTIES AS THOSE9437 1451  431
OF THE RESONANCES IN THE 0 TO 2 KEV ENERGY RANGE. A QUITE GOOD FIT9437 1451  432
OF THE TRANSMISSION AND FISSION DATA WAS OBTAINED WITHOUT         9437 1451  433
BACKGROUND AND NORMALISATION ADJUSTMENT. HOWEVER, THE CALCULATED  9437 1451  434
FISSION CROSS SECTIONS ARE, ON AVERAGE, 1.4% LOWER THAN THE       9437 1451  435
EXPERIMENTAL VALUES.  THIS DIFFERENCE,WHICH HOWEVER IS NOT LARGER 9437 1451  436
THAN THE SYSTEMATIC ERRORS ON THE EXPERIMENTAL DATA, COULD BE DUE 9437 1451  437
TO THE DIFFICULTIES OF IDENTIFYING THE WIDE J=0+ RESONANCES IN THE9437 1451  438
EXPERIMENTAL DATA, BECAUSE THE EFFECTS OF THE INCREASING          9437 1451  439
RESOLUTION AND DOPPLER WIDTHS. PRIOR TO THE SAMMY FITS, THE       9437 1451  440
FISSION DATA OF WESTON AND TODD (1988 HIGH RESOLUTION DATA) WERE  9437 1451  441
NORMALIZED TO THE ENDF/B-VI STANDARD IN THE ENERGY RANGE FROM 1   9437 1451  442
KEV TO 2 KEV.                                                     9437 1451  443
   THE CROSS SECTIONS,CALCULATED FROM THE RESONANCE PARAMETERS    9437 1451  444
AND AVERAGED OVER 0.1 KEV INTERVALS,ARE GIVEN IN THE FOLLOWING    9437 1451  445
TABLE:                                                            9437 1451  446
                                                                  9437 1451  447
**************************************************************    9437 1451  448
                         CR0SS-SECTIONS(BARN)                     9437 1451  449
                ------------------------------------------        9437 1451  450
                    TOTAL            FISSION       CAPTURE        9437 1451  451
      ENERGY    --------------    --------------   -------        9437 1451  452
       (KEV)   CALC(A)   EXP(B)  CALC(A)   EXP(C)  CALC(A)        9437 1451  453
**************************************************************    9437 1451  454
      2.0-2.1   17.34    17.30    2.034    2.062    3.223         9437 1451  455
      2.1-2.2   20.27    19.80    2.949    2.999    4.051         9437 1451  456
      2.2-2.3   19.34    19.10    2.357    2.393    3.324         9437 1451  457
      2.3-2.4   21.28    21.20    3.646    3.679    3.640         9437 1451  458
      2.4-2.5   20.03    20.60    3.956    4.024    3.128         9437 1451  459
**************************************************************    9437 1451  460
      2.0-2.5   19.65    19.60    2.989    3.031    3.473         9437 1451  461
**************************************************************    9437 1451  462
  (A) TOTAL, FISSION AND CAPTURE CROSS SECTIONS CALCULATED BY     9437 1451  463
      RESENDD, 1% ACCURACY, AT 300 K,FROM THE RESONANCE PARAME-   9437 1451  464
      TERS.                                                       9437 1451  465
  (B) AVERAGE TOTAL CROSS SECTIONS OBTAINED FROM THE AVERAGE      9437 1451  466
      EXPERIMENTAL EFFECTIVE CROSS SECTIONS IN REFERENCE/19/.     9437 1451  467
  (C) 1988 HIGH RESOLUTION DATA OF WESTON AND TODD NORMALIZED     9437 1451  468
      TO ENDF/B-VI STANDARD IN THE ENERGY RANGE FROM 1 KEV TO     9437 1451  469
      2 KEV.                                                      9437 1451  470
***************************************************************** 9437 1451  471
                                                                  9437 1451  472
                                                                  9437 1451  473
***************************************************************** 9437 1451  474
      FISSION AND CAPTURE RESONANCE INTEGRALS                     9437 1451  475
***************************************************************** 9437 1451  476
                                                                  9437 1451  477
THE FISSION AND CAPTURE RESONANCE INTEGRALS ARE COMPARED TO       9437 1451  478
JENDL-3 DATA IN THE FOLLOWING TABLE:                              9437 1451  479
                                                                  9437 1451  480
   **********************************************************     9437 1451  481
     ENERGY RANGE(EV)    FISSION(BARN)      CAPTURE(BARN)         9437 1451  482
   **********************************************************     9437 1451  483
                        JENDL-3  PRESENT    JENDL-3  PRESENT      9437 1451  484
       0.5 -   5.0       85.725   84.879     28.651   28.723      9437 1451  485
       5.0 -  10.0       25.081   25.147     19.059   18.950      9437 1451  486
      10.0 -  50.0       96.856   99.715     77.181   74.686      9437 1451  487
      50.0 - 100.0       40.479   41.552     25.930   25.376      9437 1451  488
     100.0 - 301.0       19.677   20.252     17.952   17.729      9437 1451  489
     301.0 -1000.0       10.047   10.317      8.348    8.418      9437 1451  490
    1000.0 -2000.0        3.484    3.206      2.840    2.634      9437 1451  491
    2000.0 -2.E+07       17.783  (17.783)     5.224   (5.224)     9437 1451  492
   **********************************************************     9437 1451  493
         TOTAL          299.132  302.851    185.185  181.739      9437 1451  494
   **********************************************************     9437 1451  495
                                                                  9437 1451  496
   THE JENDL-3 RESONANCE PARAMETERS ARE THOSE OBTAINED IN 1987 IN 9437 1451  497
THE ENERGY RANGE 0 KEV TO 1 KEV. THEY ARE SLIGTHLY DIFFERENT FROM 9437 1451  498
THOSE PUBLISHED IN 1989. THAT EXPLAINS THE SMALL DIFFERENCES OB-  9437 1451  499
SERVED BETWEEN JENDL-3 AND THE PRESENT RESULTS IN THIS ENERGY RAN-9437 1451  500
GE. IN THE ENERGY RANGE 1 KEV TO 2 KEV JENDL-3 IS UNRESOLVED      9437 1451  501
RANGE.  THE FISSION AND CAPTURE RESONANCE INTEGRALS CALCULATED    9437 1451  502
FROM ENDF/B-V AND THOSE FOUND IN BNL-325 ARE THE FOLLOWING:       9437 1451  503
                                                                  9437 1451  504
      ENDF/B-V     FISSION: 302.13 B    CAPTURE: 194.10 B         9437 1451  505
       BNL-325     FISSION: 310+-10 B   CAPTURE: 200+-20 B        9437 1451  506
                                                                  9437 1451  507
   THE CONSEQUENCE OF CHANGING FROM THE OLD SETS OF RESONANCE     9437 1451  508
PARAMETERS(ENDF/B-V AND PREVIOUS SETS) TO THE NEW SET IS THAT     9437 1451  509
THE CAPTURE RESONANCE INTEGRAL WILL DECREASE BY 6.7% COMPARED     9437 1451  510
WITH ENDF/B-V VALUE.                                              9437 1451  511
                                                                  9437 1451  512
REFERENCES OF APPENDIX                                            9437 1451  513
 1) R.GWIN ET AL.,NUCL.SCI.ENG.,45,25(1971)                       9437 1451  514
 2) R.GWIN ET AL.,NUCL.SCI.ENG.,59,79(1976)                       9437 1451  515
 3) R.GWIN ET AL.,NUCL.SCI.ENG.,61,116(1976)                      9437 1451  516
 4) R.GWIN ET AL.,NUCL.SCI.ENG.,88,37(1984)                       9437 1451  517
 5) J.BLONS, NUCL.SCI.ENG.,51,130(1973)                           9437 1451  518
 6) L.W.WESTON ET AL.,NUCL.SCI.ENG.88,567(1984)                   9437 1451  519
 7) L.W.WESTON ET AL.,TO BE PUBLISHED(HIGH RESOLUTION 1988 DATA)  9437 1451  520
 8) R.R.SPENCER ET AL.,NUCL.SCI.ENG.,96,318(1987)                 9437 1451  521
 9) J.A.HARVEY ,MITO 1988,PAGE 115                                9437 1451  522
10) A.CARLSON ET AL.,PRELIMINARY RESULTS OF THE ENDF/B-6 STANDARD 9437 1451  523
   EVALUATION(SEPT 8 1987)                                        9437 1451  524
11) H.DERRIEN AND G. DE SAUSSURE,ORNL-TM-10986(1988)              9437 1451  525
12) H.DERRIEN ET AL.,NUCL.SCI.ENG.,106,434(1990)                  9437 1451  526
13) H.DERRIEN, J.NUCL>SCI.TECHNOL.,30,845(1993).                  9437 1451  527
14) N.M.LARSON ET AL.,ORNL/TM-7485,ORNL/TM-9179,ORNL/TM-9719/R1   9437 1451  528
15) L.LEAL AND R.N.HWANG,TRANS.AM.NUC.SOC.,55,340(1987)           9437 1451  529
16) T.NAKAGAWA,RESENDD A JAERI VERSION OF RESEND,JAER=-M 84-192   9437 1451  530
    (1984).                                                       9437 1451  531
17) C.WAGEMANS ET AL.,MITO 1988,PAGE 91                           9437 1451  532
18) L.W.WESTON,PRIVATE COMMUNICATION(1992)                        9437 1451  533
19) H.DERRIEN,J.NUCL.SCI.TECHNOL.,29,794(1992).                   9437 1451  534
   **********************************************************     9437 1451  535
                                                                  9437 1451  536
                                                                  9437 1451  537
                                                                  9437 1451  538
                                                                  9437 1451  539
   **********************************************************     9437 1451  540
 ***************** Program LINEAR (VERSION 2002-1) ***************9437 1451  541
 For All Data Greater than 1.0000E-10 barns in Absolute Value     9437 1451  542
 Data Linearized to Within an Accuracy of .100000000 per-cent     9437 1451  543
 ***************** Program RECENT (VERSION 2002-1) ***************9437 1451  544
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9437 1451  545
 Data Linearized to within an Accuracy of .100000000 per-cent     9437 1451  546
 ***************** Program SIGMA1 (VERSION 2002-1) ***************9437 1451  547
 Data Doppler Broadened to 300.000000 Kelvin                      9437 1451  548
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9437 1451  549
 Data Linearized to Within an Accuracy pf .100000000 per-cent     9437 1451  550
 ***************** Program FIXUP (Version 2002-1) ****************9437 1451  551
 Corrected ZA/AWR in All Sections-----------------------------Yes 9437 1451  552
 Corrected Thresholds-----------------------------------------Yes 9437 1451  553
 Extended Cross Sections to 20 MeV----------------------------No  9437 1451  554
 Allow Cross Section Deletion---------------------------------No  9437 1451  555
 Allow Cross Section Reconstruction---------------------------No  9437 1451  556
 Make All Cross Sections Non-Negative-------------------------Yes 9437 1451  557
 Delete Energies Not in Ascending Order-----------------------Yes 9437 1451  558
 Deleted Duplicate Points-------------------------------------Yes 9437 1451  559
 Check for Ascending MAT/MF/MT Order--------------------------Yes 9437 1451  560
 Check for Legal MF/MT Numbers--------------------------------Yes 9437 1451  561
 Allow Creation of Missing Sections---------------------------No  9437 1451  562
 Allow Insertion of Energy Points-----------------------------No  9437 1451  563
 Create Uniform Energy Grid-----------------------------------No  9437 1451  564
 Delete Section if Cross Section =0 at All Energies-----------Yes 9437 1451  565
 ***************** Program GROUPIE (VERSION 2002-1) **************9437 1451  566
 Unshielded Group Averages Using  640 Groups                      9437 1451  567
 Weighting Spectrum: Flat (Constant) Spectrum                     9437 1451  568
                                1        451        572          19437 1451  569
                                2        151          4          39437 1451  570
                                3         18        217          19437 1451  571
                               33         18         18          09437 1451  572
                                                                  9437 1  099999
                                                                  9437 0  0    0
 9.42390E+4 2.36999E+2          0          0          1          09437 2151    1
 9.42390E+4 1.00000E+0          0          0          1          09437 2151    2
 1.00000E-5 1.00000E+3          0          0          0          09437 2151    3
 5.00000E-1 9.41000E-1          0          0          0          09437 2151    4
                                                                  9437 2  099999
                                                                  9437 0  0    0
 9.42390E+4 2.36999E+2          0          0          0          09437 3 18    1
 1.99219E+8 1.99219E+8          0          0          1        6419437 3 18    2
        641          1                                            9437 3 18    3
 .000100000 11417.9620 .000105000 11151.7657 .000110000 10898.87749437 3 18    4
 .000115000 10665.8514 .000120000 10393.4353 .000127500 10091.19469437 3 18    5
 .000135000 9815.06416 .000142500 9561.30914 .000150000 9286.678129437 3 18    6
 .000160000 9000.58665 .000170000 8740.28134 .000180000 8501.343689437 3 18    7
 .000190000 8279.03421 .000200000 8076.06236 .000210000 7885.101369437 3 18    8
 .000220000 7707.73139 .000230000 7542.93171 .000240000 7349.490919437 3 18    9
 .000255000 7136.93344 .000270000 6972.91683 .000280000 6790.337609437 3 18   10
 .000300000 6567.67848 .000320000 6366.07015 .000340000 6181.431249437 3 18   11
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 95-Am-241 JAERI      EVAL-MAR88 T.NAKAGAWA                       9543 1451    5
                      DIST-Feb2004                                9543 1451    6
----IRDF-2002         MATERIAL 9543                               9543 1451    7
-----INCIDENT NEUTRON DATA                                        9543 1451    8
------ENDF-6 FORMAT                                               9543 1451    9
****************************************************************  9543 1451   10
 95-AM-241 JAERI      EVAL-MAR88 T.NAKAGAWA                       9543 1451   11
JAERI-M 89-008        DIST-SEP89                                  9543 1451   12
----JENDL-3.2         MATERIAL 9543                               9543 1451   13
 <DOSIMETRY CROSS SECTION>                                        9543 1451   14
      AM-241 FISSION                                              9543 1451   15
****************************************************************  9543 1451   16
HISTORY                                                           9543 1451   17
82-03 EVALUATION FOR JENDL-2 WAS MADE BY Y.KIKUCHI (JAERI) /1/.   9543 1451   18
88-03 RE-EVALUATION FOR JENDL-3 WAS MADE BY T.NAKAGAWA (JAERI)    9543 1451   19
      /2/.                                                        9543 1451   20
                                                                  9543 1451   21
MF=1  GENERAL INFORMATION                                         9543 1451   22
  MT=451   COMMENT AND DICTIONARY                                 9543 1451   23
                                                                  9543 1451   24
MF=2,MT=151   RESONANCE PARAMETERS                                9543 1451   25
  RESOLVED RESONANCES FOR MLBW FORMULA : 1.0E-5 - 150 EV          9543 1451   26
        DATA OF DERRIEN AND LUCAS /5/ WERE ADOPTED AND 5 NEGATIVE 9543 1451   27
        RESONANCES WERE ADDED.  VALUES OF TOTAL SPIN J WERE       9543 1451   28
        REPLACED WITH ARBITRARILY ASSUMED VALUES.                 9543 1451   29
                                                                  9543 1451   30
  UNRESOLVED RESONANCES : 150 EV - 30 KEV                         9543 1451   31
        PARAMETERS WERE DETERMINED BY USING ASREP/6/ SO AS TO     9543 1451   32
        REPRODUCE THE CAPTURE CROSS SECTION MEASURED BY VANPRAET  9543 1451   33
        ET AL. /7/ AND THE FISSION CROSS SECTION BY DABBS ET AL.  9543 1451   34
        /8/.                                                      9543 1451   35
          ENERGY INDEPENDENT PARAMETERS:                          9543 1451   36
            R=9.37 FM, GAM-G=0.044 EV,  DOBS=0.4 EV               9543 1451   37
          ENERGY DEPENDENT PARAMETERS:                            9543 1451   38
            AT 150 EV: S0= 1.08E-4, S1=2.72E-4, WF=0.24 MILLI-EV  9543 1451   39
            AT 30 KEV: S0= 0.79E-4, S1=1.99E-4, WF=0.30 MILLI-EV  9543 1451   40
                                                                  9543 1451   41
  CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS      9543 1451   42
                      2200 M/S VALUE       RES. INT.              9543 1451   43
        TOTAL           614.6   B            -                    9543 1451   44
        ELASTIC          11.13  B            -                    9543 1451   45
        FISSION           3.018 B           13.9  B               9543 1451   46
        CAPTURE         600.4   B           1300  B               9543 1451   47
                                                                  9543 1451   48
MF=3  NEUTRON CROSS SECTIONS                                      9543 1451   49
                                                                  9543 1451   50
  MT=1,2  TOTAL AND ELASTIC SCATTERING CROSS SECTIONS             9543 1451   51
        CALCULATED WITH OPTICAL AND STATISTICAL MODELS BY USING   9543 1451   52
        CASTHY/9/.  OPTICAL POTENTIAL PARAMETERS/10/ WERE OBTAINED9543 1451   53
        BY FITTING THE DATA OF PHILLIPS AND HOWE /11/ :           9543 1451   54
           V = 43.4 - 0.107*EN                      (MEV)         9543 1451   55
           WS= 6.95 - 0.339*EN + 0.0531*EN**2       (MEV)         9543 1451   56
           WV= 0             , VSO = 7.0            (MEV)         9543 1451   57
           R = RSO = 1.282   , RS = 1.29            (FM)          9543 1451   58
           A = ASO = 0.60    , B  = 0.5             (FM)          9543 1451   59
                                                                  9543 1451   60
                                                                  9543 1451   61
  MT=18      FISSION CROSS SECTION                                9543 1451   62
        EVALUATED ON THE BASIS OF THE DATA BY DABBS ET AL./8/     9543 1451   63
                                                                  9543 1451   64
MF=33  COVARIANCES OF NEUTRON CROSS SECTIONS FROM JENDL/D-99      9543 1451   65
 MT=18                                                            9543 1451   66
     ADOPTED FROM ENDF/B-VI/12/.                                  9543 1451   67
                                                                  9543 1451   68
                                                                  9543 1451   69
REFERENCES                                                        9543 1451   70
 1) KIKUCHI Y.: JAERI-M 82-096 (1982).                            9543 1451   71
 2) NAKAGAWA T.: JAERI-M 88-008 (1989).                           9543 1451   72
 5) DERRIEN H. AND LUCAS B.: 1975 WASHINGTON, P.637,              9543 1451   73
    NBS-SP-425 (1975).                                            9543 1451   74
 6) KIKUCHI Y.: PRIVATE COMMUNICATION.                            9543 1451   75
 7) VANPRAET G. ET AL.: 1985 SANTA FE, 1, 493 (1986).             9543 1451   76
 8) DABBS J.W.T. ET AL.: NUCL. SCI. ENG., 83, 22 (1983).          9543 1451   77
 9) IGARASI S.: J.NUCL.SCI.TECHNOL.,12,67 (1975).                 9543 1451   78
10) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              9543 1451   79
11) PHILLIPS T.W. AND HOWE R.E.: NUCL. SCI. ENG., 69, 375 (1979). 9543 1451   80
12) ZHOU DELIN, GU FUHUA ET AL.: ENDF/B-VI (MAT=9543) (1988).     9543 1451   81
****************************************************************  9543 1451   82
                                                                  9543 1451   83
                                                                  9543 1451   84
                                                                  9543 1451   85
                                                                  9543 1451   86
 ***************** Program LINEAR (VERSION 2002-1) ***************9543 1451   87
 For All Data Greater than 1.0000E-10 barns in Absolute Value     9543 1451   88
 Data Linearized to Within an Accuracy of .100000000 per-cent     9543 1451   89
 ***************** Program RECENT (VERSION 2002-1) ***************9543 1451   90
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9543 1451   91
 Data Linearized to within an Accuracy of .100000000 per-cent     9543 1451   92
 ***************** Program SIGMA1 (VERSION 2002-1) ***************9543 1451   93
 Data Doppler Broadened to 300.000000 Kelvin                      9543 1451   94
 for All Data Greater than 1.0000E-10 barns in Absolute Value     9543 1451   95
 Data Linearized to Within an Accuracy pf .100000000 per-cent     9543 1451   96
 ***************** Program FIXUP (Version 2002-1) ****************9543 1451   97
 Corrected ZA/AWR in All Sections-----------------------------Yes 9543 1451   98
 Corrected Thresholds-----------------------------------------Yes 9543 1451   99
 Extended Cross Sections to 20 MeV----------------------------No  9543 1451  100
 Allow Cross Section Deletion---------------------------------No  9543 1451  101
 Allow Cross Section Reconstruction---------------------------No  9543 1451  102
 Make All Cross Sections Non-Negative-------------------------Yes 9543 1451  103
 Delete Energies Not in Ascending Order-----------------------Yes 9543 1451  104
 Deleted Duplicate Points-------------------------------------Yes 9543 1451  105
 Check for Ascending MAT/MF/MT Order--------------------------Yes 9543 1451  106
 Check for Legal MF/MT Numbers--------------------------------Yes 9543 1451  107
 Allow Creation of Missing Sections---------------------------No  9543 1451  108
 Allow Insertion of Energy Points-----------------------------No  9543 1451  109
 Create Uniform Energy Grid-----------------------------------No  9543 1451  110
 Delete Section if Cross Section =0 at All Energies-----------Yes 9543 1451  111
 ***************** Program GROUPIE (VERSION 2002-1) **************9543 1451  112
 Unshielded Group Averages Using  640 Groups                      9543 1451  113
 Weighting Spectrum: Flat (Constant) Spectrum                     9543 1451  114
                                1        451        118          19543 1451  115
                                2        151          4          19543 1451  116
                                3         18        217          19543 1451  117
                               33         18         16          09543 1451  118
                                                                  9543 1  099999
                                                                  9543 0  0    0
 9.52410E+4 2.38986E+2          0          0          1          09543 2151    1
 9.52410E+4 1.00000E+0          0          0          1          09543 2151    2
 1.00000E-5 1.50000E+2          0          0          0          09543 2151    3
 2.50000E+0 9.37000E-1          0          0          0          09543 2151    4
                                                                  9543 2  099999
                                                                  9543 0  0    0
 9.52410E+4 2.38986E+2          0          0          0          09543 3 18    1
 1.99999E+8 1.99999E+8          0          0          1        6419543 3 18    2
        641          1                                            9543 3 18    3
 .000100000 51.3052773 .000105000 50.1079487 .000110000 48.97045709543 3 18    4
 .000115000 47.9222736 .000120000 46.6968760 .000127500 45.33727459543 3 18    5
 .000135000 44.0950790 .000142500 42.9534963 .000150000 41.71795199543 3 18    6
 .000160000 40.4307858 .000170000 39.2595742 .000180000 38.18445049543 3 18    7
 .000190000 37.1841024 .000200000 36.2707160 .000210000 35.41134409543 3 18    8
 .000220000 34.6130933 .000230000 33.8713750 .000240000 33.00070879543 3 18    9
 .000255000 32.0439328 .000270000 31.3056049 .000280000 30.48366259543 3 18   10
 .000300000 29.4812057 .000320000 28.5734378 .000340000 27.74200399543 3 18   11
 .000360000 26.9761460 .000380000 26.2769608 .000400000 25.54796499543 3 18   12
 .000425000 24.8019302 .000450000 24.1202708 .000475000 23.49517349543 3 18   13
 .000500000 22.9072419 .000525000 22.3699039 .000550000 21.86226549543 3 18   14
 .000575000 21.3900875 .000600000 20.9060918 .000630000 20.40814609543 3 18   15
 .000660000 19.9524634 .000690000 19.5153070 .000720000 19.05007149543 3 18   16
 .000760000 18.5511751 .000800000 18.0878986 .000840000 17.66326379543 3 18   17
 .000880000 17.2596280 .000920000 16.8895239 .000960000 16.53503649543 3 18   18
 .001000000 16.1675054 .001050000 15.7837856 .001100000 15.42401349543 3 18   19
 .001150000 15.0924242 .001200000 14.7011985 .001275000 14.27109619543 3 18   20
 .001350000 13.8777583 .001425000 13.5105958 .001500000 13.12041729543 3 18   21
 .001600000 12.7123489 .001700000 12.3397233 .001800000 11.99500599543 3 18   22
 .001900000 11.6800064 .002000000 11.3878334 .002100000 11.11357199543 3 18   23
 .002200000 10.8622996 .002300000 10.6219594 .002400000 10.34754989543 3 18   24
 .002550000 10.0424243 .002700000 9.80361723 .002800000 9.543892829543 3 18   25
 .003000000 9.22394878 .003200000 8.93261626 .003400000 8.666118549543 3 18   26
 .003600000 8.42306741 .003800000 8.19866358 .004000000 7.964785439543 3 18   27
 .004250000 7.72734253 .004500000 7.51048463 .004750000 7.307647269543 3 18   28
 .005000000 7.12124209 .005250000 6.94814792 .005500000 6.784296339543 3 18   29
 .005750000 6.63379085 .006000000 6.47555913 .006300000 6.317125229543 3 18   30
 .006600000 6.16762235 .006900000 6.02971171 .007200000 5.879208639543 3 18   31
 .007600000 5.71777295 .008000000 5.56999636 .008400000 5.431170789543 3 18   32
 .008800000 5.30182317 .009200000 5.18150547 .009600000 5.066938199543 3 18   33
 .010000000 4.94821064 .010500000 4.82262453 .011000000 4.707663779543 3 18   34
 .011500000 4.59795348 .012000000 4.47213784 .012750000 4.332816099543 3 18   35
 .013500000 4.20373606 .014250000 4.08529824 .015000000 3.958938599543 3 18   36
 .016000001 3.82620741 .017000001 3.70438526 .017999999 3.593050599543 3 18   37
 .018999999 3.49065480 .020000000 3.39456853 .021000000 3.306660139543 3 18   38
 .022000000 3.22388318 .023000000 3.14682311 .024000000 3.056392539543 3 18   39
 .025500000 2.95907786 .027000001 2.88205910 .028000001 2.798584939543 3 18   40
 .029999999 2.69607102 .032000002 2.60300703 .034000002 2.518435849543 3 18   41
 .035999998 2.44168652 .037999999 2.37134032 .039999999 2.298442269543 3 18   42
 .042500000 2.22520397 .045000002 2.15915714 .047499999 2.098291019543 3 18   43
 .050000001 2.04303612 .052499998 1.99258453 .055000000 1.945325219543 3 18   44
 .057500001 1.90302922 .059999999 1.85914432 .063000001 1.816529909543 3 18   45
 .066000000 1.77732441 .068999998 1.74195361 .071999997 1.705121189543 3 18   46
 .075999998 1.66726015 .079999998 1.63503985 .083999999 1.606556369543 3 18   47
 .088000000 1.58222929 .092000000 1.56226398 .096000001 1.544740649543 3 18   48
 .100000001 1.52947423 .104999997 1.51748803 .109999999 1.510657309543 3 18   49
 .115000002 1.50769305 .119999997 1.51101174 .127499998 1.524423069543 3 18   50
 .135000005 1.54870410 .142499998 1.58430580 .150000006 1.642207309543 3 18   51
 .159999996 1.73260227 .170000002 1.85412976 .180000007 2.015956329543 3 18   52
 .189999998 2.22915507 .200000003 2.51245839 .209999993 2.894467449543 3 18   53
 .219999999 3.41860254 .230000004 4.16063103 .239999995 5.626778769543 3 18   54
 .254999995 8.82815710 .270000011 13.8569548 .280000001 24.68428309543 3 18   55
 .300000012 32.9036091 .319999993 20.0317145 .340000004 8.912000729543 3 18   56
 .360000014 4.55430795 .379999995 2.78968183 .400000006 1.902517629543 3 18   57
 .425000012 1.45804726 .449999988 1.32153894 .474999994 1.452995389543 3 18   58
 .500000000 2.06823238 .524999976 4.16458177 .550000012 8.955286699543 3 18   59
 .574999988 9.04637758 .600000024 3.80727810 .629999995 1.488845779543 3 18   60
 .660000026 .835810765 .689999998 .583407230 .720000029 .4509664349543 3 18   61
 .759999990 .380905725 .800000012 .353868563 .839999974 .3527661479543 3 18   62
 .879999995 .372648705 .920000017 .414908308 .959999979 .4864857529543 3 18   63
 1.00000000 .623933129 1.04999995 .908768459 1.10000002 1.544761279543 3 18   64
 1.14999998 3.46717767 1.20000005 21.5180722 1.27499998 21.98491769543 3 18   65
 1.35000002 2.79636200 1.42499995 .910301031 1.50000000 .4298381579543 3 18   66
 1.60000002 .249932347 1.70000005 .205604116 1.79999995 .5592888289543 3 18   67
 1.89999998 1.47115486 2.00000000 .219907486 2.09999990 .1377515599543 3 18   68
 2.20000005 .252101211 2.29999995 1.80450792 2.40000010 .8271200229543 3 18   69
 2.54999995 2.20098818 2.70000005 .199515711 2.79999995 .0688983929543 3 18   70
 3.00000000 .039982739 3.20000005 .034907434 3.40000010 .0396874759543 3 18   71
 3.59999990 .072453611 3.79999995 1.31740811 4.00000000 .4545130579543 3 18   72
 4.25000000 .072191967 4.50000000 .118200170 4.75000000 2.114117579543 3 18   73
 5.00000000 1.19108663 5.25000000 13.7127105 5.50000000 1.312201169543 3 18   74
 5.75000000 .244578528 6.00000000 1.24055456 6.30000019 .0703622439543 3 18   75
 6.59999990 .156676942 6.90000010 .024090727 7.19999981 .0253565279543 3 18   76
 7.59999990 .064327211 8.00000000 .192074768 8.39999962 .0303044469543 3 18   77
 8.80000019 .786315512 9.19999981 .179092954 9.60000038 4.106449809543 3 18   78
 10.0000000 .356873590 10.5000000 .252712792 11.0000000 .2142557149543 3 18   79
 11.5000000 .036851057 12.0000000 .018356860 12.7500000 .0459599409543 3 18   80
 13.5000000 .052559219 14.2500000 2.89463552 15.0000000 .1253619489543 3 18   81
 16.0000000 .965078754 17.0000000 .385138061 18.0000000 .0207186779543 3 18   82
 19.0000000 .018943345 20.0000000 .061033820 21.0000000 .0530467249543 3 18   83
 22.0000000 .082007664 23.0000000 .355252688 24.0000000 .2939772919543 3 18   84
 25.5000000 .560448508 27.0000000 .183892344 28.0000000 .1891116289543 3 18   85
 30.0000000 .272887127 32.0000000 .085314866 34.0000000 .2306432359543 3 18   86
 36.0000000 .807807646 38.0000000 .551630875 40.0000000 .1508855449543 3 18   87
 42.5000000 .271310533 45.0000000 .165348949 47.5000000 .1528098829543 3 18   88
 50.0000000 .296220510 52.5000000 .060686151 55.0000000 .1331005929543 3 18   89
 57.5000000 .040280714 60.0000000 .043411491 63.0000000 .1992882169543 3 18   90
 66.0000000 .068171197 69.0000000 .310106001 72.0000000 .0561975089543 3 18   91
 76.0000000 .260455098 80.0000000 .175890724 84.0000000 .1405369599543 3 18   92
 88.0000000 .078253970 92.0000000 .258987041 96.0000000 .1515834449543 3 18   93
 100.000000 .251279864 105.000000 .293826556 110.000000 .1412264799543 3 18   94
 115.000000 .126536451 120.000000 .174290158 127.500000 .1521780509543 3 18   95
 135.000000 .282033747 142.500000 .159172258 150.000000 .1800625889543 3 18   96
 160.000000 .170428121 170.000000 .161564109 180.000000 .1533616509543 3 18   97
 190.000000 .145733788 200.000000 .140323995 210.000000 .1370180329543 3 18   98
 220.000000 .133936250 230.000000 .131052574 240.000000 .1280735459543 3 18   99
 255.000000 .129565957 270.000000 .132107517 280.000000 .1351273289543 3 18  100
 300.000000 .139126207 320.000000 .143089220 340.000000 .1453491219543 3 18  101
 360.000000 .137595202 380.000000 .128697674 400.000000 .1193435079543 3 18  102
 425.000000 .109672615 450.000000 .103294662 475.000000 .0998990509543 3 18  103
 500.000000 .096778133 525.000000 .093855034 550.000000 .0911159329543 3 18  104
 575.000000 .088568598 600.000000 .086145871 630.000000 .0838297369543 3 18  105
 660.000000 .081694916 690.000000 .079662060 720.000000 .0774746649543 3 18  106
 760.000000 .075146614 800.000000 .072809837 840.000000 .0704543959543 3 18  107
 880.000000 .068255689 920.000000 .066195938 960.000000 .0642602369543 3 18  108
 1000.00000 .062210457 1050.00000 .060053350 1100.00000 .0580342259543 3 18  109
 1150.00000 .056137361 1200.00000 .053921502 1275.00000 .0514492349543 3 18  110
 1350.00000 .049160922 1425.00000 .047032897 1500.00000 .0451896189543 3 18  111
 1600.00000 .043598478 1700.00000 .042151847 1800.00000 .0408282849543 3 18  112
 1900.00000 .039610752 2000.00000 .038898213 2100.00000 .0386550219543 3 18  113
 2200.00000 .038422564 2300.00000 .038254526 2400.00000 .0380639089543 3 18  114
 2550.00000 .037914118 2700.00000 .037820646 2800.00000 .0377258699543 3 18  115
 3000.00000 .037612621 3200.00000 .037514037 3400.00000 .0372424449543 3 18  116
 3600.00000 .035884975 3800.00000 .034439064 4000.00000 .0329269199543 3 18  117
 4250.00000 .031371299 4500.00000 .030103309 4750.00000 .0290752989543 3 18  118
 5000.00000 .028126982 5250.00000 .027235710 5500.00000 .0263973269543 3 18  119
 5750.00000 .025613688 6000.00000 .024934246 6300.00000 .0243536219543 3 18  120
 6600.00000 .023821664 6900.00000 .023316969 7200.00000 .0227771749543 3 18  121
 7600.00000 .022205621 8000.00000 .021788948 8400.00000 .0215181129543 3 18  122
 8800.00000 .021270344 9200.00000 .021042443 9600.00000 .0208317459543 3 18  123
 10000.0000 .020546983 10500.0000 .020192328 11000.0000 .0198674259543 3 18  124
 11500.0000 .019576077 12000.0000 .019222437 12750.0000 .0188465129543 3 18  125
 13500.0000 .018497288 14250.0000 .018185644 15000.0000 .0178422659543 3 18  126
 16000.0000 .017476674 17000.0000 .017145879 18000.0000 .0168440749543 3 18  127
 19000.0000 .016566722 20000.0000 .016388102 21000.0000 .0163000329543 3 18  128
 22000.0000 .016214043 23000.0000 .016140548 24000.0000 .0160465039543 3 18  129
 25500.0000 .015872482 27000.0000 .015713719 28000.0000 .0155446019543 3 18  130
 30000.0000 .015288990 32000.0000 .015067719 34000.0000 .0148486819543 3 18  131
 36000.0000 .014654185 38000.0000 .014466451 40000.0000 .0143010409543 3 18  132
 42500.0000 .014183715 45000.0000 .014067238 47500.0000 .0139508309543 3 18  133
 50000.0000 .013890910 52500.0000 .013880060 55000.0000 .0138692109543 3 18  134
 57500.0000 .013858361 60000.0000 .013885258 63000.0000 .0139499019543 3 18  135
 66000.0000 .014014545 69000.0000 .014084321 72000.0000 .0142046139543 3 18  136
 76000.0000 .014348622 80000.0000 .014493936 84000.0000 .0146569249543 3 18  137
 88000.0000 .014825487 92000.0000 .014994050 96000.0000 .0151626919543 3 18  138
 100000.000 .015403193 105000.000 .015708931 110000.000 .0160146689543 3 18  139
 115000.000 .016320406 120000.000 .016682486 127500.000 .0170962199543 3 18  140
 135000.000 .017509885 142500.000 .017920799 150000.000 .0185436539543 3 18  141
 160000.000 .019360592 170000.000 .020182545 180000.000 .0210017579543 3 18  142
 190000.000 .021806431 200000.000 .022747752 210000.000 .0238300509543 3 18  143
 220000.000 .024912350 230000.000 .025994650 240000.000 .0273818179543 3 18  144
 255000.000 .029406033 270000.000 .031175424 280000.000 .0333227389543 3 18  145
 300000.000 .036527646 320000.000 .039974586 340000.000 .0436548709543 3 18  146
 360000.000 .048189873 380000.000 .053051429 400000.000 .0597991209543 3 18  147
 425000.000 .068832543 450000.000 .079815112 475000.000 .0932258019543 3 18  148
 500000.000 .109295188 525000.000 .128456223 550000.000 .1509415839543 3 18  149
 575000.000 .177229849 600000.000 .211489704 630000.000 .2555620199543 3 18  150
 660000.000 .310099562 690000.000 .374384670 720000.000 .4607357799543 3 18  151
 760000.000 .571055740 800000.000 .691648328 840000.000 .8188009279543 3 18  152
 880000.000 .949580070 920000.000 1.08120574 960000.000 1.211948679543 3 18  153
 1000000.00 1.41154490 1100000.00 1.62499311 1200000.00 1.729994809543 3 18  154
 1300000.00 1.78999595 1400000.00 1.82499899 1500000.00 1.844999989543 3 18  155
 1600000.00 1.86499860 1700000.00 1.87499876 1800000.00 1.884998939543 3 18  156
 1900000.00 1.89499909 2000000.00 1.89999959 2100000.00 1.899999869543 3 18  157
 2200000.00 1.89806653 2300000.00 1.89420016 2400000.00 1.890333809543 3 18  158
 2500000.00 1.88646743 2600000.00 1.88237188 2700000.00 1.877296379543 3 18  159
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