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. Only liaison officers are authorised to submit online requests. Rules for requesters 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.