NEA-1518 ZZ-WIMKAL-88.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-WIMKAL-88.

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.

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.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

6. TYPICAL RUNNING TIME:

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS:  WIMS-D/4 and WIMD5A.

10. 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)

11. MACHINE REQUIREMENTS:

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHORS

         Korea Atomic Energy Research Institute
         P.O. Box 105,
         Yusung, TAEJON
         REPUBLIC OF KOREA

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