Computer Programs
NEA-1649 ZZ-KASHIL-E6.
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NEA-1649 ZZ-KASHIL-E6.

ZZ KASHIL-E6, 175 N, 42 Gamma Groups Cross Sections in MATXS Format Based on ENDF/B-VI.5 for Shielding Applications

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-KASHIL-E6.
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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-KASHIL-E6 NEA-1649/01 Tested 18-JAN-2002

Machines used:

Package ID Orig. computer Test computer
NEA-1649/01 Many Computers Many Computers
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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.
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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.
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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
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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
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9. STATUS
Package ID Status date Status
NEA-1649/01 18-JAN-2002 Tested at NEADB
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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)
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11. HARDWARE REQUIREMENTS:  - Memory space : 420 MB
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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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
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16. MATERIAL AVAILABLE
NEA-1649/01
index-E6 Index format MATXS file
KASHIL-E6 MATXS data library
kafax-E6_abs   Abstract
rep_kafaxE6   Description of content and method
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17. CATEGORIES
  • Z. Data.

Keywords: ENDF/B, cross sections, data library, shielding.