Computer Programs
NEA-1650 ZZ-KAFAX-F22.
last modified: 18-JAN-2002 | catalog | categories | new | search |

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. Rules for end-users 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.