SUBENT        22282001   20080204   20080402   20080318       2192
BIB                 13         77
TITLE      .Measurements of Neutron Induced Fission Cross
            Sections Ratios of 232Th, 233U, 234U, 236U, 238U,
            237Np, 242Pu and 243Am Relative to 235U around 14 MeV
AUTHOR     (Fumitoshi MANABE, Kazutaka KANDA, Tomohiko IWASAKI,
           Hirimichi TERAYAMA, Yoshiji KARINO, Mamoru BABA,
           Naohiro HIRAKAWA)
INSTITUTE  (2JPNTOH)  Department of Nuclear Engineering
REFERENCE  (J,TRTU,52,(2),97,1988)   THE TECHNOLOGY REPORTS
             OF THE TOHOKU UNIVERSITY SENDAI, JAPAN, Vol.52, No.2
             Main reference, data tables are given
FACILITY   (DYNAM)  Tohoku University 4.5 MV DYNAMITRON
                    accelerator facility
INC-SOURCE (D-T)  Bombarding a tritium-titanium target by 750 keV
             deuteron ions. The target was deposited on a copper
             plate of 0.25 mm (2.5 milligram/cm2) thick,  16 mm
             diameter.
INC-SPECT  .The neutrons of 14.9, 14.5, 14.0 and 13.5 MeV were
            obtained, respectively, at the emission angles of 0,
            65, 100 and 150 degrees with respect to the deuteron
            beam.
METHOD     (STTA)   The 235U sample and another one were mounted
                    back to back on the midplane of the fission
                    chamber.
DETECTOR   (FISCH)  The fission chamber used in this study was a
             back-to-back parallel plate ionization chamber. The
             counter gas was 90% Argon and 10% C-H4 mixture.
           (SI)    Low geometry counter with a silicon detector -
                for the absolute number densities of atoms in the
                samples.
           (SIBAR)  Surface-barrier silicon detector for alpha
                    registration used for sample analysis
SAMPLE     .The samples were prepared by the electrodeposition on
            the platinum plates, which were 36 mm in diam. and
            0.3 or 0.4 mm in thickness, and sintered into the
            oxide to fix them on the plates. The diameter of the
            deposits was 25 mm.  The isotopic compositions of
            the samples were determined by means of the alpha
            spectroscopy with a high resolution surface barrier
            detector (except for the Np-237 measurements).
           .Monitor sample U-235 has arial density 96.22
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
             U-235          99.91    (10.64+-0.16)E17;
             U-234           0.029    0.003E+17;
             U-236           0.017    0.002E+17;
             U-238           0.041    0.004E+17
CORRECTION .Corrections were made for the following effects:
             1.  The room-returned neutrons,
             2.  The spontaneous fission,
             3.  The extrapolation from the tail of the fission
                 spectrum to the zero pulse height,
             4.  The anisotropy of the fission fragments,
             5.  The self-absorption of the fission fragments
                 in the samples,
             6.  The impurities in the samples,
             7.  The chamber- and the target-scattered neutrons,
             8.  The parasitic neutrons,
             9.  The attenuation of the incident neutron flux
                  by the backing plates,
             10. The difference in the solid angle subtended
                 by the samples to the target between the 235U
                 sample and another one.
           .Corrections are  for U-235 :
            Room-Returned Neutrons     1.5 - 4.7%
            Extrapolation              0.2 - 1.5%
            Self-absorption            2.4 - 2.5%
            Sample impurity                  0.1%
ERR-ANALYS (ERR-1)  Error due to the number of U-235 atoms
           (ERR-2)  Error due to the sample number of atoms
           (ERR-3)  Max error of the fission rate ratio
           (ERR-4)  Max error due to the correction factor
           (ERR-T)  Max total error evaluated by considering
                    correlations among the various errors
             Minimum errors are given in the Table III of main
             reference
           (MONIT-ERR) Error of the U-235 monitor
HISTORY    (20080204C)   SM
ENDBIB              77
COMMON               2          3
ERR-1      MONIT-ERR
PER-CENT   PER-CENT
   1.47          4.
ENDCOMMON            3
ENDSUBENT           84
SUBENT        22282002   20080204   20080402   20080318       2192
BIB                  5         20
REACTION   ((90-TH-232(N,F),,SIG)/(92-U-235(N,F),,SIG))
SAMPLE     .Sample Th-232 has arial density 171.3
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
            Th-232          100.     (20.41+-0.33)E17;
            Th-230           0.00001  0.0001E+17;
CORRECTION .Corrections are  for -
            Room-Returned Neutrons        <=O.l %
            Extrapolation              0.5 - 1.8%
            Self-absorption            2.9 - 3.0%
            Chamber-scatterd neutrons  0.6 - 0.7%
            Target-scatterd neutrons   0.5 - 0,7%
COVARIANCE .Correlation matrix for ratio values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    87    100
            14.46    86     87    100
            14.89    87     87     87    100
STATUS     (TABLE) Table IV-I page 112 of main reference
ENDBIB              20
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   1.64       0.887      0.276
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        NO-DIM     NO-DIM     PER-CENT
  13.47      0.18       0.150       0.004     2.41
  14.00      0.06       0.158       0.004     2.38
  14.46      0.16       0.166       0.004     2.37
  14.89      0.29       0.181       0.004     2.38
ENDDATA              6
ENDSUBENT           35
SUBENT        22282003   20080204   20080402   20080318       2192
BIB                  5         25
REACTION   ((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG))
SAMPLE     .Sample U-233 has arial density 129.9
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
            U-232          0.0003     0.00005E+17;
            U-233          99.47     (14.41+-0.07)E+17
            U-234          0.166          0.024E+17;
            U-235          0.064          0.009E+17;
            U-236          0.015          0.002E+17;
            U-238          0.282          0.041E+17;
CORRECTION .Corrections are  for -
            Room-Returned Neutrons     2.1 - 3.9%
            Extrapolation              1.9 - 3.7%
            Self-absorption                  2.7%
            Sample impurity                  0.3%
            Chamber-scatterd neutrons        0.3%
            Target-scatterd neutrons         0,3%
COVARIANCE .Correlation matrix for ratio values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    81    100
            14.46    79     81    100
            14.89    78     80     79    100
STATUS     (TABLE) Table V-1 page 114 of main reference
ENDBIB              25
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   0.487      1.51       0.131
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        NO-DIM     NO-DIM     PER-CENT
  13.47      0.18       1.18        0.03      2.19
  14.00      0.06       1.19        0.03      2.17
  14.46      0.16       1.19        0.02      2.13
  14.89      0.29       1.14        0.02      2.04
ENDDATA              6
ENDSUBENT           40
SUBENT        22282004   20080204   20080402   20080318       2192
BIB                  5         25
REACTION   ((92-U-234(N,F),,SIG)/(92-U-235(N,F),,SIG))
SAMPLE     .Sample U-234 has arial density 136.0
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
            U-232          0.003        0.0004 E+17;
            U-233          0.0004       0.00005E+17;
            U-234         99.08   (14.97+-0.09)E+17;
            U-235          0.078          0.012E+17;
            U-236          0.055          0.008E+17;
            U-238          0.786          0.119E+17;
CORRECTION .Corrections are  for -
            Room-Returned Neutrons         <=0.1%
            Extrapolation              1.4 - 3.1%
            Self-absorption            2.7 - 2.8%
            Sample impurity            0.5 - 0.6%
            Chamber-scatterd neutrons        0.0%
            Target-scatterd neutrons   0.1 - 0.2%
COVARIANCE .Correlation matrix for ratio values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    76    100
            14.46    78     77    100
            14.89    75     76     77    100
STATUS     (TABLE) Table VI-1 page 115 of main reference
ENDBIB              25
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   0.597      1.41       0.160
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        NO-DIM     NO-DIM     PER-CENT
  13.47      0.18       1.00        0.02      2.15
  14.00      0.06       0.983       0.02      1.99
  14.46      0.16       0.999       0.02      2.03
  14.89      0.29       1.01        0.02      1.96
ENDDATA              6
ENDSUBENT           40
SUBENT        22282005   20080204   20080402   20080318       2192
BIB                  5         24
REACTION   ((92-U-236(N,F),,SIG)/(92-U-235(N,F),,SIG))
SAMPLE     .Sample U-236 has arial density 101.5
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
            U-233          0.002         0.0002E+17;
            U-234          0.124         0.014 E+17
            U-235          9.403          1.053E+17;
            U-236         89.13   (9.981+-0.167)E+17;
            U-238          1.786          0.151E+17;
CORRECTION .Corrections are  for -
            Room-Returned Neutrons     0.3 - 0.6%
            Extrapolation              0.2 - 0.8%
            Self-absorption            2.5 - 2.6%
            Sample impurity           12.6 -13.3%
            Chamber-scatterd neutrons  0.3 - 0.4%
            Target-scatterd neutrons   0.3 - 0.5%
COVARIANCE .Correlation matrix for ratio values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    74    100
            14.46    73     74    100
            14.89    73     74     74    100
STATUS     (TABLE) Table VII-1 page 117 of main reference
ENDBIB              24
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   1.68       0.965      0.897
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        NO-DIM     NO-DIM     PER-CENT
  13.47      0.18       0.756       0.018     2.36
  14.00      0.06       0.786       0.018     1.33
  14.46      0.16       0.797       0.019     2.34
  14.89      0.29       0.803       0.019     1.34
ENDDATA              6
ENDSUBENT           39
SUBENT        22282006   20080204   20080402   20080318       2192
BIB                  5         22
REACTION   ((92-U-238(N,F),,SIG)/(92-U-235(N,F),,SIG))
SAMPLE     .Sample U-238 has arial density 108.0
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
            U-234          0.0003       0.00004E+17
            U-235          0.037          0.004E+17;
            U-238         99.96   (11.82+-0.19)E+17;
CORRECTION .Corrections are  for -
            Room-Returned Neutrons         <=0.1%
            Extrapolation              0.2 - 0.9%
            Self-absorption            2.5 - 2.6%
            Sample impurity                  0.1%
            Chamber-scatterd neutrons  0.5 - 0.7%
            Target-scatterd neutrons   0.4 - 0.7%
COVARIANCE .Correlation matrix for ratio values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    78    100
            14.46    78     78    100
            14.89    78     78     78    100
STATUS     (TABLE) Table VIII-1 page 118 of main reference
ENDBIB              22
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   1.57       0.923      0.271
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        NO-DIM     NO-DIM     PER-CENT
  13.47      0.18       0.544       0.011     2.02
  14.00      0.06       0.560       0.011     2.00
  14.46      0.16       0.572       0.011     2.01
  14.89      0.29       0.584       0.012     2.01
ENDDATA              6
ENDSUBENT           37
SUBENT        22282007   20080204   20080402   20080318       2192
BIB                  5         21
REACTION   ((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG))
SAMPLE     .Sample NP-237 has arial density 90.88
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
            Np-237         100.03     (9.985+-0.066)E+17
            Pu-238         0.0002      0.00002E+17;
CORRECTION .Corrections are  for -
            Room-Returned Neutrons         <=0.1%
            Extrapolation              0.3 - 1.1%
            Self-absorption            2.4 - 2.4%
            Sample impurity                  0.0%
            Chamber-scatterd neutrons        0.0%
            Target-scatterd neutrons   0.1 - 0.2%
COVARIANCE .Correlation matrix for ratio values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    70    100
            14.46    71     72    100
            14.89    70     72     72    100
STATUS     (TABLE) Table IX-1 page 120 of main reference
ENDBIB              21
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   0.661      1.04       0.168
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        NO-DIM     NO-DIM     PER-CENT
  13.47      0.18       1.11        0.02      1.94
  14.00      0.06       1.06        0.02      1.91
  14.46      0.16       1.08        0.02      1.90
  14.89      0.29       1.07        0.02      1.90
ENDDATA              6
ENDSUBENT           36
SUBENT        22282008   20080204   20080402   20080318       2192
BIB                  5         25
REACTION   ((94-PU-242(N,F),,SIG)/(92-U-235(N,F),,SIG))
SAMPLE     .Sample PU-242 has arial density 10.46
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
            PU-238          0.003      0.00003E+17;
            PU-239          0.019      0.0002 E+17;
            PU-240          0.083      0.0009 E+17;
            PU-241          0.043      0.0005 E+17;
            PU-242         99.84      (1.126+-0.09)E+17;
            AM-241          0.013      0.0001 E+17;
CORRECTION .Corrections are  for -
            Room-Returned Neutrons         <=0.1%
            Spontaneous fission        2.4 - 2.6%
            Extrapolation              0.1 - 0.6%
            Self-absorption                  1.9%
            Sample impurity                  0.2%
            Chamber-scatterd neutrons      <=0.1%
            Target-scatterd neutrons   0.1 - 0.2%
COVARIANCE .Correlation matrix for ratio values
            Energy  Matrix times 100
            ------  ----------------
            14.09    100
            14.46     83    100
            14.89     84     84    100
STATUS     (TABLE) Table X-1 page 121 of main reference
ENDBIB              25
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   0.816      0.825      0.151
ENDCOMMON            3
DATA                 5          3
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        NO-DIM     NO-DIM     PER-CENT
  14.00      0.06       0.998       0.019     1.86
  14.46      0.16       1.00        0.02      1.89
  14.89      0.29       0.989       0.018     1.87
ENDDATA              5
ENDSUBENT           39
SUBENT        22282009   20080204   20080402   20080318       2192
BIB                  5         24
REACTION   ((95-AM-243(N,F),,SIG)/(92-U-235(N,F),,SIG))
SAMPLE     .Sample Am-243 has arial density 20.33
            microgram/cm2. Sample content ==>
             Element      content,%  number of atoms
            PU-239          0.041      0.0009 E+17;
            PU-240          0.054      0.001  E+17;
            Am-241          0.023      0.0005 E+17;
            Am-243         99.59      (2.176+-0.045)E+17;
            Cm-244          0.290      0.006  E+17;
CORRECTION .Corrections are  for -
            Room-Returned Neutrons         <=0.1%
            Spontaneous fission       38.9 -43.7%
            Extrapolation              1.0 - 2.4%
            Self-absorption            1.9 - 2.0%
            Sample impurity                  0.5%
            Chamber-scatterd neutrons      <=0.1%
            Target-scatterd neutrons       <=0.2%
COVARIANCE .Correlation matrix for ratio values
            Energy  Matrix times 100
            ------  ----------------
            14.09    100
            14.46     89    100
            14.89     89     89    100
STATUS     (TABLE) Table XI-1 page 123 of main reference
ENDBIB              24
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   2.08       0.945      0.170
ENDCOMMON            3
DATA                 5          3
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        NO-DIM     NO-DIM     PER-CENT
  14.00      0.06       1.08        0.03      2.47
  14.46      0.16       1.05        0.03      2.46
  14.89      0.29       1.06        0.03      2.46
ENDDATA              5
ENDSUBENT           38
SUBENT        22282010   20080204   20080402   20080318       2192
BIB                  5         12
REACTION   (90-TH-232(N,F),,SIG)
MONITOR    (92-U-235(N,F),,SIG)
MONIT-REF  .ENDF/B-V
COVARIANCE .Correlation matrix for sigma values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    97    100
            14.46    96     97    100
            14.89    97     97     97    100
STATUS     (TABLE) Table IV-2 page 113 of main reference
           (DEP,22282002)
ENDBIB              12
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   1.64       0.887      0.276
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        B          B          PER-CENT
  13.47      0.18       0.300       0.014     4.67
  14.00      0.06       0.327       0.015     4.65
  14.46      0.16       0.348       0.016     4.65
  14.89      0.29       0.380       0.018     4.65
ENDDATA              6
ENDSUBENT           27
SUBENT        22282011   20080204   20080402   20080318       2192
BIB                  5         12
REACTION   (92-U-233(N,F),,SIG)
MONITOR    (92-U-235(N,F),,SIG)
MONIT-REF  .ENDF/B-V
COVARIANCE .Correlation matrix for sigma values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    96    100
            14.46    95     96    100
            14.89    95     96     95    100
STATUS     (TABLE) Table V-2 page 114 of main reference
           (DEP,22282003)
ENDBIB              12
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   0.487      1.51       0.131
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        B          B          PER-CENT
  13.47      0.18       2.35        0.11      4.56
  14.00      0.06       2.46        0.11      4.55
  14.46      0.16       2.41        0.11      4.53
  14.89      0.29       2.39        0.11      4.49
ENDDATA              6
ENDSUBENT           27
SUBENT        22282012   20080204   20080402   20080318       2192
BIB                  5         12
REACTION   (92-U-234(N,F),,SIG)
MONITOR    (92-U-235(N,F),,SIG)
MONIT-REF  .ENDF/B-V
COVARIANCE .Correlation matrix for sigma values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    95    100
            14.46    95     95    100
            14.89    95     95     95    100
STATUS     (TABLE) Table VI-2 page 116 of main reference
           (DEP,22282004)
ENDBIB              12
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   0.597      1.41       0.160
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        B          B          PER-CENT
  13.47      0.18       2.00        0.09      4.54
  14.00      0.06       2.03        0.09      4.47
  14.46      0.16       2.03        0.09      4.48
  14.89      0.29       2.13        0.10      4.46
ENDDATA              6
ENDSUBENT           27
SUBENT        22282013   20080204   20080402   20080318       2192
BIB                  5         12
REACTION   (92-U-236(N,F),,SIG)
MONITOR    (92-U-235(N,F),,SIG)
MONIT-REF  .ENDF/B-V
COVARIANCE .Correlation matrix for sigma values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    93    100
            14.46    93     93    100
            14.89    93     93     03    100
STATUS     (TABLE) Table VII-2 page 117 of main reference
           (DEP,22282005)
ENDBIB              12
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   1.68       0.965      0.897
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        B          B          PER-CENT
  13.47      0.18       1.51        0.07      4.64
  14.00      0.06       1.63        0.08      4.63
  14.46      0.16       1.70        0.08      4.64
  14.89      0.29       1.69        0.08      4.63
ENDDATA              6
ENDSUBENT           27
SUBENT        22282014   20080204   20080402   20080318       2192
BIB                  5         11
REACTION   (92-U-238(N,F),,SIG)
MONITOR    (92-U-235(N,F),,SIG)
MONIT-REF  .ENDF/B-V
COVARIANCE .Correlation matrix for sigma values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    96    100
            14.46    96     96    100
            14.89    96     96     96    100
STATUS     (TABLE) Table VIII-2 page 119 of main reference
ENDBIB              11
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   1.57       0.923      0.271
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        B          B          PER-CENT
  13.47      0.18       1.08        0.05      4.48
  14.00      0.06       1.16        0.05      4.47
  14.46      0.16       1.20        0.05      4.48
  14.89      0.29       1.23        0.05      4.47
ENDDATA              6
ENDSUBENT           26
SUBENT        22282015   20080204   20080402   20080318       2192
BIB                  5         12
REACTION   (93-NP-237(N,F),,SIG)
MONITOR    (92-U-235(N,F),,SIG)
MONIT-REF  .ENDF/B-V
COVARIANCE .Correlation matrix for sigma values
            Energy  Matrix times 100
            ------  ----------------
            13.47   100
            14.09    94    100
            14.46    94     95    100
            14.89    94     95     95    100
STATUS     (TABLE) Table IX-2 page 120 of main reference
           (DEP,22282007)
ENDBIB              12
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   0.661      1.04       0.168
ENDCOMMON            3
DATA                 5          4
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        B          B          PER-CENT
  13.47      0.18       2.21        0.10      4.45
  14.00      0.06       2.18        0.10      4.43
  14.46      0.16       2.25        0.10      4.43
  14.89      0.29       2.26        0.10      4.43
ENDDATA              6
ENDSUBENT           27
SUBENT        22282016   20080204   20080402   20080318       2192
BIB                  5         11
REACTION   (94-PU-242(N,F),,SIG)
MONITOR    (92-U-235(N,F),,SIG)
MONIT-REF  .ENDF/B-V
COVARIANCE .Correlation matrix for sigma values
            Energy  Matrix times 100
            ------  ----------------
            14.09    100
            14.46     97    100
            14.89     97     97    100
STATUS     (TABLE) Table X-2 page 122 of main reference
           (DEP,22282008)
ENDBIB              11
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   0.816      0.825      0.151
ENDCOMMON            3
DATA                 5          3
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        B          B          PER-CENT
  14.00      0.06       2.06        0.09      4.41
  14.46      0.16       2.10        0.09      4.42
  14.89      0.29       2.08        0.09      4.41
ENDDATA              5
ENDSUBENT           25
SUBENT        22282017   20080204   20080402   20080318       2192
BIB                  5         10
REACTION   (95-AM-243(N,F),,SIG)
MONITOR    (92-U-235(N,F),,SIG)
MONIT-REF  .ENDF/B-V
COVARIANCE .Correlation matrix for sigma values
            Energy  Matrix times 100
            ------  ----------------
            14.09    100
            14.46     97    100
            14.89     97     97    100
STATUS     (TABLE) Table XI-2 page 123 of main reference
ENDBIB              10
COMMON               3          3
ERR-2      ERR-3      ERR-4
PER-CENT   PER-CENT   PER-CENT
   2.08       0.945      0.170
ENDCOMMON            3
DATA                 5          3
EN         EN-ERR     DATA       ERR-T      ERR-T
MEV        MEV        B          B          PER-CENT
  14.00      0.06       2.23        0.11      4.70
  14.46      0.16       2.21        0.10      4.69
  14.89      0.29       2.22        0.10      4.69
ENDDATA              5
ENDSUBENT           24