1. NAME AND TITLE OF DATA LIBRARY

WIMKAL-88: 69 Energy-Group, Neutron Cross-Section Library for Thermal Reactor Applications in WIMSD Format.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

None is included.

3. CONTRIBUTOR

Korea Atomic Energy Research Institute, Yusung, Taejon, Republic of Korea, through the OECD NEA Data Bank, Issy les-Moulineaux, France

4. HISTORICAL BACKGROUND AND INFORMATION

WIMKAL-88 is a neutron cross section library for thermal reactor design analysis using the 69 energy group WIMS structure.

5. APPLICATION OF THE DATA

WIMKAL-88 can be read by either CCC-576/WIMS-D4 or CCC-656/WIMSD5. Using the WIMS-KAERI code, WIMKAL-88 was validated by comparing results with those of criticality experiments and depletion results for PWR's.

6. SOURCE AND SCOPE OF DATA

The library was produced using the NJOY code system to process 130 nuclides from ENDF/B-V or IV and JENDL-2 (Rev.1) and from ENDL-84, where data were 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.

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, O-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, and Gd-157.

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.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

No retrieval code is included in the package. The data can be converted to binary form using the Willie program from the WIMSD5 package.

8. DATA FORMAT AND COMPUTER

Card images in WIMSD format; many computers (D00193/MNYCP/00).

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

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).

Jung-Do Kim, "WIMKAL-88, The 1988 Version of WIMS-KAERI Library," IAEA-NDS-92, Rev. 0 (NEA-1518/01) (August 1990).

11. CONTENTS OF LIBRARY

Included are the referenced documents and a Unix tar file including the ASCII data and a brief information file transmitted on a CD-ROM or cartridge tape.

12. DATE OF ABSTRACT

December 1997.