Page 1 of 5
                                              ID#:            D00113I303302
        TAPE#     1 DC 6150 tape              RSIC#           DLC-113C
        DENSITY                               CODE PKG NAME:  VITAMIN-E
                                              COMPUTER:       IBM 3033
                                              PACKAGED:       10/1/87
                                              PREVIOUS RELEASES:  7/31/84
                                                                  8/26/85
                                       PORTED TO UNIX TAR FORMAT:10/18/94
      **************************************************************************
                                                             LOGICAL    DCB
      DESCRIPTION                                            RECORDS PARAMETERS
      **************************************************************************
       
       To extract files (for UNIX systems):
       1.   tar -xvf /dev/rst0
            where 'rst0' is your tape drive.
       2.   tar -xvf d00113i303302.tar.Z
       3.   uncompress *

       
       1. 174 group neutron cross sections (16 materials)   351,889 FB 12800  80
          These materials are used in the sample problems.

           ID   Material       ID   Material      ID   Material
         130301   Li-6       139701   Li-7      130601   C-12
         127601   O-16       131101   Na-23     132401   Cr
         132502   Mn-55      132603   Fe        132802   Ni
         118901   Nb         132101   Mo        139501   U-235
         139801   U-238      139901   Pu-239    138001   Pu-240
         138101   Pu-241

       2. 174 group neutron cross sections (20 materials)   350,993 FB 12800  80

           ID   Material       ID   Material      ID   Material
           9301   H-1        130401   Be-9         104   Be-9
         130501   B-10         8811   B-11      127501   N-14
         130902   F-19       131201   Mg        131301   Al-27
         131401   Si         131501   P-31      134701   S
         114901   Cl           8824   Ar        115001   K
         132003   Ca         132201   Ti        132301   V
         132703   Co-59      132901   Cu

       3. 174 group neutron cross sections (20 materials)   242,877 FB 12800  80

           ID   Material       ID   Material      ID   Material
         135801   Ga           8841   Zr          8847   Cd
           8850   Sn           8853   Gd        128502   Ta-181
            182   W-182         183   W-183        184   W-184
            186   W-186        8861   Au-197    138202   Pb
         139001   Th-232     134201   Pu-242    136101   Am-241
         136901   Am-242m    136301   Am-243    864201   Cm-242
         134301   Cm-243     134401   Cm-244

       4. 174 group neutron cross sections (21 materials)   119,653 FB 12800  80
          * Materials processed with COMET for DLC113B.

           ID   Material       ID   Material      ID   Material
         116901   H-3        127000   He-4      116000   B-11
         920201   Y-89       134002 * Zr        966901 * Cs-137
         137401 * Hf-174     137601 * Hf-176    137701 * Hf-177
         137801 * Hf-178     138301 * Hf-179    138401 * Hf-180
         108301 * Re-185     108401 * Re-187    139101   Pa-233
         139301   U-233        9394   U-234     139601   U-236
         133701   Np-237     133801   Pu-238    854201   Am-242
                                                      Page 2 of 5

       5. 174 neutron group cross sections (5 materials)     93,959 FB 12800  80
          File 5 includes new materials processed for DLC113B, 8/26/85
           ID   Material       ID   Material      ID   Material
         930101   H-1        930202   H-2          260   Fe
         135301   Ba-138     137501   Bi-209

       6. 174 neutron group cross sections (4 materials)     53,710 FB 12800  80
          File 6 includes new materials processed for DLC113C, 10/1/87
           ID   Material       ID   Material      ID   Material
         932604   Fe         960601   I-127     135501  Cs-133
           8860   Pt

       7. 174 neutron, 38 photon group cross sections        48,549 FB 12800  80
          (62 materials)  *  4 added and ** 1 revised for DLC113B - 8/26/85
                          #  2 added for DLC113C - 10/1/87
                          $ 10 replaced for DLC113C - 10/1/87

           ID   Material       ID   Material      ID   Material
         130101   H-1        130202 * H-2        130301   Li-6
         139701   Li-7       130401   Be-9          104   Be-9
         130501 $ B-10         8811   B-11       130601   C
         127501   N-14       127601   O-16       130902 **$ F-19
         131103   Na-23      131201   Mg         131301   Al-27
         131403   Si         131501   P-31       134701   S
         114901   Cl           8824   Ar         115001   K
         132003 $ Ca         132201   Ti         132301 $ V
         132402   Cr         132502 $ Mn-55      132603   Fe
         932604 #$ Fe
            260 * Fe         132703   Co-59      132801   Ni
         132901 $ Cu         135801   Ga           8841   Zr
         118901   Nb-93      132101 $ Mo           8847   Cd
           8850   Sn         135301 * Ba-138       8853   Gd
         128501   Ta-181        182   W-182         183   W-183
            184   W-184         186   W-186        8860 # Pt
           8861   Au-197
         138202   Pb         137501 * Bi-209     139001   Th-232
         139501   U-235      139801   U-238      139901 $ Pu-239
         138001   Pu-240     138101   Pu-241     134201   Pu-242
         136101   Am-241     136901 $ Am-242m    136301   Am-243
         864201   Cm-242     134301   Cm-243     134401   Cm-244

                                                      Page 3 of 5

       8. 38 group photon interaction library                76,062 FB 12800  80

           ID Material    ID Material   ID Material   ID Material
            1   H          2    He       3    Li       4    Be
            5   B          6    C        7    N        8    O
            9   F         10    Ne      11    Na      12    Mg
           13   Al        14    Si      15    P       16    S
           17   Cl        18    Ar      19    K       20    Ca
           21   Sc        22    Ti      23    V       24    Cr
           25   Mn        26    Fe      27    Co      28    Ni
           29   Cu        30    Zn      31    Ga      32    Ge
           33   As        34    Se      35    Br      36    Kr
           37   Rb        38    Sr      39    Y       40    Zr
           41   Nb        42    Mo      43    Tc      44    Ru
           45   Rh        46    Pd      47    Ag      48    Cd
           49   In        50    Sn      51    Sb      52    Te
           53   I         54    Xe      55    Cs      56    Ba
           57   La        58    Ce      59    Pr      60    Nd
           61   Pm        62    Sm      63    Eu      64    Gd
           65   Tb        66    Dy      67    Ho      68    Er
           69   Tm        70    Yb      71    Lu      72    Hf
           73   Ta        74    W       75    Re      76    Os
           77   Ir        78    Pt      79    Au      80    Hg
           81   Tl        82    Pb      83    Bi      84    Po
           85   At        86    Rn      87    Fr      88    Ra
           89   Ac        90    Th      91    Pa      92    U
           93   Np        94    Pu      95    Am      96    Cm
           97   Bk        98    Cf      99    Es     100    Fm

       9. 174 group neutron special purpose dosimetry         2,888 FB 12800  80
          (26 materials) # 15 replaced with ENDF/B-V Rev. 2 for DLC113C, 10/1/87

           ID   Material       ID   Material      ID   Material
          631101  Na-23       631301  Al-27      632501  Mn-55
          632702 #Co-59       633703 #Np-237     637902 #Au-197
          639002 #Th-232      639502 #U-235      639803 #U-238
          639902 #Pu-239      642402 #Li-6       642502 #B-10
          642602 #Sc-45       642702  Ti-46      642802 #Ti-47
          642902  Ti-48       643003 #Fe-54      643101  Fe-56
          643202  Fe-58       643303 #Ni-58      643402  Ni-60
          643502 #Cu-63       643601  Cu-65      643703 #In-115
          643802  I-127       643901  S-32
                                                      Page 4 of 5

      10. 174 group neutron special purpose activation        6,740 FB 12800  80
          (53 materials) # 4 replaced with ENDF/B-V Rev. 2 for DLC113C, 10/1/87
           ID   Material       ID   Material      ID   Material
          703601  Li-6        703701  Li-7       705001  B-10
          707401  N-14        708601  O-16       709901  F-19
          711301  Na-23       712401  Mg-24      713701  Al-27
          715101  P-31        716201  S-32       718001  Ar-40
          719101  K-41        721501  Sc-45      722001  Ti-50
          722601  Ti-46       722701  Ti-47      722801  Ti-48
          724002 #Cr-50       724201  Cr-52      725501  Mn-55
          726401  Fe-54       726601  Fe-56      726801  Fe-58
          727901  Co-59       728001  Ni-60      728201  Ni-62
          728801  Ni-58       729301  Cu-63      729501  Cu-65
          740002 #Zr-90       740201  Zr-92      740401  Zr-94
          741301  Nb-93       742001  Mo-100     742201  Mo-92
          742801  Mo-98       747902 #Ag-109     749502 #In-115
          750001  Sn-120      750201  Sn-122     750401  Sn-124
          753701  I-127       757901  La-139     766401  Dy-164
          773101  Ta-181      779702  Au-197     790201  Th-232
          791101  Pa-231      791301  Pa-233     792301  U-233
          792801  U-238       795101  Am-241

      11. 174 group neutron special purpose gas production    1,296 FB 12800  80
          (18 materials) # 1 replaced with ENDF/B-V Rev. 2 for DLC113C, 10/1/87

           ID   Material       ID   Material      ID   Material
          516001  B-11        527501  N-14       530301  Li-6
          530402  Be-9        530501  B-10       530601  C-0
          530900  F-19        531301  Al-27      531400  Si-28
          532201  Ti-0        532301  V-0        532401  Cr-0
          532502  Mn-55       532601  Fe-0       532702  Co-59
          532802  Ni-0        532901  Cu-0       539702 #Li-7

      12. JCL to create subroutine library                       99  FB 12800 80
      13. ALIAS - PL1 source used to create subroutine library   63   |   |    |
      14. Step 1 of ZPR-6/7 infinite medium problem             178   |   |    |
          JCL and sample problem input to compile, link and           |   |    |
          execute AIM, AJAX, BONAMI, RADE, and NITAWL.                |   |    |
          NITAWL creates an AMPX working library for XSDRNPM and      |   |    |
          an ANISN binary tape for GIP.                (10/87)        |   |    |
      15. Step 2 of ZPR-6/7 infinite medium problem via XSDRNPM  71   |   |    |
      16. Step 2 of ZPR-6/7 infinite medium problem via ANISN   107   |   |    |
      17. Step 1 of CTR standard blanket problem                269   |   |    |
          JCL and sample problem input to compile, link and           |   |    |
          execute AIM, CHOX, RADE, DIAL, MALOCS and NITAWL.           |   |    |
      18. Step 2 of CTR standard blanket problem via XSDRNPM     71   |   |    |
      19. Step 2 of CTR standard blanket problem via ANISN      154   |   |    |
                                                          ---------
                   Total logical records (LRECL=80)       1,349,628
                   Total bytes (LRECL=80)               107,970,240
                                                      Page 5 of 5

      20. Output from step 1 of ZPR sample problem     (10/87) 1732  FB 3990 133
      21. Output of step 2 ZPR sample problem(XSDRNPM)(10/87)   911   |   |    |
      22. Output from step 2 ZPR sample problem(ANISN) (10/87) 1362   |   |    |
      23. Output from step 1 of CTR sample problem             4979   |   |    |
      24. Output from step 2 of CTR sample problem (XSDRNPM)   4894   |   |    |
      25. Output from step 2 of CTR sample problem (ANISN)     2462   |   |    |
                                                          ---------
                   Total logical records (LRECL=133)         16,340
                   Total bytes (LRECL=133)                2,173,220

                   Total logical records in package       1,365,968
                   Total bytes in package               110,143,460

    Requires approximately 75% of 2400 foot 9-track 6250 BPI tape blocked 12800

      NOTES:
      Data in files 1-11 are in AMPX master library format.  Data on files
      9, 10, and 11 are reaction cross sections based on the particular
      ENDF/B-V special purpose file.
      
      In the DLC-113C package the ENDF/B-V dosimetry and activation files were
      processed with the XLACS2, NITAWL and WORM modules of AMPX-III.  The gas
      production file was processed with XLACS2.  Since the special purpose
      files do not contain data for all reaction types NITAWL expects to see in
      creating working libraries for transport calculations, some of the data
      in the working libraries are meaningless and are reported as errors by
      RADE.  Tables 3 and 4 in the DLC-113 document list the reaction types
      included in the dosimetry and activation files. 

      Files 4, 5, and 7 were the only files modified in the 8/26/85 update of
      DLC113B.  File 6 is a new file for DLC113C.  Files 7, 9, 10, 11, 14,
      20, 21, and 22 were updated for DLC113C.

      The JCL and input data are structured as though PSR117/MARS is being
      used to execute the sample problems.  The MARS package is recommended
      for use with this data package.  Modifications were made to the AIM
      and BONAMI modules of PSR-063/AMPX II and PSR-117/MARS packages.  Users
      are urged to request these updates.  The new modules were used to
      execute the ZPR sample case in this package.  The revised version of AIM,
      which retains six digits of significance in lieu of seven in the older
      version, was used to create the formatted cross section data in files
      1-11.