NEA-1649 ZZ-KASHIL-E6.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-KASHIL-E6.

3. DESCRIPTION OF PROGRAM OR FUNCTION


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  FORMAT: MATXS

  NUMBER OF GROUPS: 175 neutron-, 42 photon-groups

  176 NUCLIDES: 1-H-1, 1-H-2, 1-H-3, 2-He-3, 2-He-4, 3-Li-6, 3-Li-7, 4-Be-9, 5-B-10, 5-B-11, 6-C- nat., 7-N-14, 7-N-15, 8-O-16, 8-O-17, 9-F-19, 11-Na-23, 12-Mg-nat., 13-Al-27, 14-Si-nat., 14-Si-28, 14-Si-29, 14-Si-30, 15-P-31, 16-S-32, 17-Cl-nat., 19-K-nat., 20-Ca-nat., 21-Sc-45, 22-Ti-nat., 23-V-nat., 24-Cr-50, 24-Cr-52, 24-Cr-53, 24-Cr-54, 25-Mn-25, 26-Fe-54, 26-Fe-56, 26-Fe-57, 26-Fe-58, 27-Co-59, 28-Ni-58, 28-Ni-60, 28-Ni-61, 28-Ni-62, 28-Ni-64, 29-Cu-63, 29-Cu-65, 31-Ga-nat., 39-Y-89, 40-Zr-nat., 40-Zr-90, 40-Zr-91, 40-Zr-92, 40-Zr-94, 40-Zr-96, 41-Nb-93, 42-Mo-nat., 46-Pd-102, 46-Pd-104, 46-Pd-105, 46-Pd-106, 46-Pd-108, 46-Pd-110, 47-Ag-107, 47-Ag-109, 48-Cd-106, 48-Cd-108, 48-Cd-110, 48-Cd-112, 48-Cd-113, 48-Cd-114, 48-Cd-116, 49-In-nat., 53-I-127, 54-Xe-124, 54-Xe-126, 54-Xe-128, 54-Xe-129, 54-Xe-130, 54-Xe-131, 54-Xe-132, 54-Xe-134, 54-Xe-136, 55-Cs-133, 56-Ba-138, 59-Pr-141, 60-Nd-143, 60-Nd-145, 60-Nd-146, 60-Nd-148, 60-Nd-150, 61-Pm-147, 62-Sm-147, 62-Sm-151, 62-Sm-152, 63-Eu-151, 63-Eu-152, 63-Eu-153, 63-Eu-154, 63-Eu-155, 64-Gd-152, 64-Gd-154, 64-Gd-155, 64-Gd-156, 64-Gd-157, 64-Gd-158, 64-Gd-160, 66-Dy-164, 67-Ho-165, 71-Lu-175, 71-Lu-176, 72-Hf-174, 72-Hf-176, 72-Hf-177, 72-Hf-178, 72-Hf-179, 72-Hf-180, 73-Ta-181, 73-Ta-182, 74-W-nat., 74-W-182, 74-W-183, 74-W-184, 74-W-186, 75-Re-185, 75-Re-187, 77-Ir-191, 77-Ir-193, 79-Au-197, 82-Pb-206, 82-Pb-207, 82-Pb-208, 83-Bi-209, 90-Th-232, 90-Th-232, 91-Pa-231, 91-Pa-233, 92-U-232, 92-U-233, 92-U-234, 92-U-235, 92-U-236, 92-U-237, 92-U-238, 93-Np-237, 93-Np-238, 93-Np-239, 94-Pu-236, 94-Pu-237, 94-Pu-238, 94-Pu-239, 94-Pu-240, 94-Pu-241, 94-Pu-242, 94-Pu-243, 94-Pu-244, 95-Am-241, 95-Am-242, 95-Am-242m, 95-Am-243, 96-Cm-241, 96-Cm-242, 96-Cm-243, 96-Cm-244, 96-Cm-245, 96-Cm-246, 96-Cm-247, 96-Cm-248, 97-Bk-249, 98-Cf-249, 98-Cf-250, 98-Cf-251, 98-Cf-252, 98-Cf-253, 99-Es-253

  ORIGIN: ENDF/B-VI.5 and some JENDL-3.2 and ENDL-84 data

  WEIGHTING SPECTRUM: Maxwellian + 1/E + fission spectrum
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The library was generated for the analyses of neutron and gamma shielding. The library includes 176 nuclides based on ENDF/B-VI.5 and has a format of MATXS processed by the NJOY97 code. It can be used to calculate the problem dependant group constants with the TRANSX code for neutron and gamma transport.

4. METHODS

The data were generated at 300 ~ 2100 Kelvin degrees and at 6~8 background cross sections for the self shielding considerations. The infinite diluted data of H-1, H-2, C and Li are included at the temperatures of the thermal scattering law data. The scattering matrices were expanded to P5~P7 of Legendre polynomial. The weighting function used for group averaged neutron cross sections from the pointwise data is "Maxwellian + 1/E + fission spectrum". The library has been validated through the shielding benchmarks such as PCA-REPLICA, NESDIP2, Winfrith Iron, Winfrith Iron88, Winfrith Graphite experiments, etc.

8. RELATED OR AUXILIARY PROGRAMS

- BBC : Program to convert MATXS libraries between formatted and binary modes, index libraries and maintain libraries by inserting, deleting, and extracting individual materials. Available at RSICC or NEA
- TRANSX : Code system to produce neutron, photon, and particle transport tables for discrete-ordinates and diffusion codes from cross sections in MATXS format. Available at RSICC or NEA

10. REFERENCES

- C-S. Gil, J-D. Kim, and J. Chang, "Analysis of Pressure Vessel Surveillance Dosimetry Inserted into Korean PWR", Reactor Dosimetry Radiation Metrology and Assessment, 101-107 page, (Feb 2001).
- C-S. Gil, J-D. Kim, and YO. Lee, "Development and Validation of a Library for Shielding Analysis", '98 Korea Nuclear Society Fall Meeting, (Oct. 1998). (Korean)
- C-S. Gil et al., "Establishment of Nuclear Data System", KAERI Report, KAERI/RR-2121/2000, (Apr. 2001). (Korean)

11. HARDWARE REQUIREMENTS:  - Memory space : 420 MB

15. NAME AND ESTABLISHMENT OF AUTHORS

Choong-Sup Gil
Nuclear Data Evaluation Laboratory
Korea Atomic Energy Research Institute
P.O. Box 105, Yusung
Taejon
Korea

index-E6 Index format MATXS file
KASHIL-E6 MATXS data library
kafax-E6_abs   Abstract
rep_kafaxE6   Description of content and method