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

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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.