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NEA-1650 ZZ-KAFAX-F22.

ZZ KAFAX-F22, 80 and 24 Groups Cross-Section Library in MATXS Format Based on JEF-2.2 for Fast Reactors

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1. NAME OR DESIGNATION:  ZZ-KAFAX-F22.
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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-KAFAX-F22 NEA-1650/01 Tested 18-JAN-2002

Machines used:

Package ID Orig. computer Test computer
NEA-1650/01 Many Computers Many Computers
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3. DESCRIPTION

  FORMAT: MATXS

  NUMBER OF GROUPS: 80 neutron-, 24 photon-groups

  97 NUCLIDES: 1-H-1, 1-H-2, 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, 9-F-19, 11-Na-23, 12-Mg-nat., 13-Al-27, 14-Si-nat., 15-P-31, 17-Cl-nat., 18-Ar-40, 19-K-nat., 20-Ca-nat., 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-nat., 31-Ga-nat., 39-Y-89, 40-Zr-nat., 41-Nb-93, 42-Mo-nat., 47-Ag-107, 47-Ag-109, 48-Cd-nat., 50-Sn-nat., 63-Eu-151, 63-Eu-153, 64-Gd-152, 64-Gd-154, 64-Gd-155, 64-Gd-156, 64-Gd-157, 64-Gd-158, 64-Gd-160, 73-Ta-181, 74-W-182, 74-W-183, 74-W-184, 74-W-186, 75-Re-185, 75-Re-187, 79-Au-197, 82-Pb-nat., 83-Bi-209, 90-Th-232, 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, 94-Pu-238, 94-Pu-239, 94-Pu-240, 94-Pu-241, 94-Pu-242, 95-Am-241, 95-Am-242, 95-Am-242m, 95-Am-243, 96-Cm-242, 96-Cm-243, 96-Cm-244, 96-Cm-245, 96-Cm-246, 96-Cm-247, 96-Cm-248, 98-Cf-252

  ORIGIN: JEF-2.2

  WEIGHTING SPECTRUM: Thermal + 1/E + fast reactor + fusion
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The library is focused on the fast reactor analyses. It has 80 and 24 energy group structures for neutron and photon, respectively. It includes 97 nuclide data based on JEF-2.2 and has a format of MATXS processed by the NJOY94 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 ~ 2500 Kelvin degrees and at 4~7 background cross sections for the self shielding considerations. The weighting function used for group averaged neutron cross sections from the pointwise data is " thermal + 1/E + fast reactor + fusion". The library has been validated through the CSEWG benchmark analyses such as VERA-11A, ZPR-3-12, SNEAK-7B, ZPPR-2, ZPR-6-7, etc.
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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-1650/01 18-JAN-2002 Tested at NEADB
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10. REFERENCES

- J-D. Kim, C-S. Gil and J. Chang, "Comparison of BFS-73-1 Benchmark Test using JENDL-3.2, JEF-2.2 and ENDF/B-VI.3", 1998 Symposium on Nuclear Data, JAERI, (Nov. 1998).
- J-D. Kim, and C-S. Gil, "Development and Benchmark of Multi-group Library for Fast Reactor Using JEF-2.2", KAERI/TR-842/97 (Feb. 1997). (Korean)
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11. HARDWARE REQUIREMENTS:  - Memory space : 80 MB
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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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
Rep. of Korea
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16. MATERIAL AVAILABLE
NEA-1650/01
index-F22 Index format MATXS file
kafax-F22 MATXS data library
kafax-F22_abs   Abstract
rep_kafaxF22   Description of content and method
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17. CATEGORIES
  • Z. Data.

Keywords: cross sections, data library, fast reactors, joint evaluated file.