Computer Programs
NEA-1518 ZZ-WIMKAL-88.
last modified: 09-SEP-1996 | catalog | categories | new | search |

NEA-1518 ZZ-WIMKAL-88.

ZZ WIMKAL-88, 69-Group KAERI WIMS Library for Thermal Reactors

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-WIMKAL-88.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-WIMKAL-88 NEA-1518/01 Tested 09-SEP-1996

Machines used:

Package ID Orig. computer Test computer
NEA-1518/01 Many Computers VAX under VMS
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3. DESCRIPTION OF PROGRAM OR FUNCTION


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  FORMAT: WIMS

  NUMBER OF GROUPS:  69 energy groups

  NUCLIDES:
                The following nuclides are included:
H-1, H-1 (in H2O), H-1 (in ZrH), H-2, H-2 (in D2O), He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C, C (in graphite), N-14, 0-16, F, Na, Al, Si, P-31, S-32, K, Ti, V, Cr, Mn-55, Fe, Co-59, Ni, Cu, Cu-63, Zr, Zircaloy-2, Nb-93, Mo, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-99, Mo-100, Ag-107, Ag-109, Cd, In-113, In-115, Sn, Gd, Dy-164, Er-166, Er-167, Lu-176, Hf, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179,  Hf-180, Ta-181, Au-197, Pb.
                The following fission products are included:
Kr-83, Mo-95, Tc-99, Ru-101, Ru-103, Rh-103, Rh-105, Pd-105, Pd-108, Ag-109, Cd-113, In-115, I-127, I-135, Xe-131, Xe-135, Cs-133, Cs-134, Cs-135, Nd-143, Nd-145, Pm-147, Pm-148g, Pm-148m, Pm-149, Sm-147, Sm-148, Sm-149, Sm-150, Sm-151, Sm-152, Eu-153, Eu-154, Eu-155, Gd-157, Pseudo F.P.
                The following actinides are included:
Th-232, Pa-233, U-233, U234, U-235, U-236, U-237, U-238, Np-237, Np-238, Np-239, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242g, Am-242m, Am-243, Cm-242, Cm-244.

ORIGIN: ENDF/B-V or IV and JENDL-2(Rev.1); and from ENDL-84, where  data was not available in ENDF/B.

  WEIGHTING SPECTRUM: Within-group weighting fluxes were computed.

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Neutron cross section library for thermal reactor design analysis  with  69 energy WIMS  groups structure.
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4. METHOD OF SOLUTION

The library was produced using NJOY and by processing nuclides from ENDF/B-V or IV and JENDL-2 (Rev.1); and from ENDL-84, where data was not available in ENDF/B.
Transport cross sections were computed using P1 scattering matrix data. Within-group weighting fluxes for actinides were computed on an ultra-fine group basis for accurate intermediate resonance self-shielding. A more explicit representation was adapted for the fission-product chain.
A more extensive representation of the actinide burnup chain including Th cycle was selected.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:  WIMS-D/4 and WIMD5A.
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9. STATUS
Package ID Status date Status
NEA-1518/01 09-SEP-1996 Screened
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10. REFERENCES:
NEA-1518/01, included references:
- Jung-Do Kim:
  WIMKAL-88, The 1988 Version of WIMS-KAERI Library
  IAEA-NDS-92, Rev. 0 (August 1990)
- Jung-Do Kim, Jong Tai Lee, Choong-Sup Gil and Hark Rho Kim:
  Generation and Benchmarking of a 69-group Cross Section Library
  for Thermal Reactor Applications
  Journal of the Korean Nuclear Society, Volume 21, Number 4
  (December 1989)
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

         Korea Atomic Energy Research Institute
         P.O. Box 105,
         Yusung, TAEJON
         REPUBLIC OF KOREA
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16. MATERIAL AVAILABLE
NEA-1518/01
File name File description Records
NEA1518_01.001 Information file 53
NEA1518_01.002 WIMKAL-88 library 60443
NEA1518_01.003 Test1 using WIMSD4 with standard lib /input 218
NEA1518_01.004 Test1 using WIMSD4 with standard lib /output 43311
NEA1518_01.005 Test1 using WIMSD4 with WIMKAL88 lib /input 218
NEA1518_01.006 Test1 using WIMSD4 with WIMKAL88 lib /output 45092
NEA1518_01.007 Test1 using WIMSD5A with new lib / input 217
NEA1518_01.008 Test1 using WIMSD5A with new lib / output 32967
NEA1518_01.009 Test2 using WIMSD5A with new lib / input 28
NEA1518_01.010 Test2 using WIMSD5A with new lib / output 667
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • Z. Data.

Keywords: ENDF/B, data library, evaluated data, neutron cross sections, thermal reactors.