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NEA-1815 ZZ-KAFAX-E70.

ZZ KAFAX-E70, 150 and 12 Groups Cross Section Library in MATXS Format based on ENDF/B-VII.0 for Fast Reactors

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1. NAME OR DESIGNATION:  ZZ-KAFAX-E70.
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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-E70 NEA-1815/01 Tested 02-FEB-2009

Machines used:

Package ID Orig. computer Test computer
NEA-1815/01 Many Computers PC Windows
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3. DESCRIPTION

  
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  FORMAT: MATXS, 144 nuclides processed with NJOY99.245
  
  NUMBER OF GROUPS: 150 neutron-, 12 photon-groups
  
  144 NUCLIDES: H-1, H-2, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat, N-14 , N-15 , O-16 , F-19 , Na-23, Mg-24, Mg-25, Mg-26, Al-27, Si-28, Si-29, Si-30, P-31 , Cl-35, Cl-37, Ar-40, K-39 , K-40 , K-41 , Ca-40, Ca-42, Ca-43, Ca-44, Ca-46, Ca-48, Ti-46, Ti-47, Ti-48, Ti-49, Ti-50, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Ga-69, Ga-71, Y-89, Zr-90, Zr-91, Zr-92, Zr-93, Zr-94, Zr-95, Zr-96, Nb-93, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-99, Mo-100, Ag-107, Ag-109, Cd-106, Cd-108, Cd-110, Cd-111, Cd-112, Cd-113, Cd-114, Cd-115m, Cd-116, Sn-112, Sn-113, Sn-114, Sn-115, Sn-116, Sn-117, Sn-118, Sn-119, Sn-120, Sn-122, Sn-123, Sn-124, Sn-125, Sn-126, Eu-151, Eu-153, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, W-182, W-183, W-184, W-186, Re-185, Re-187, Au-197, Pb-206, Pb-207, Pb-208, Bi-209, Th-232, Pa-233, U-233, U-234, U-235, U-236, U-238, Np-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242, Am-242m, Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246
  
  ORIGIN: ENDF/B-VII.0
  
  WEIGHTING SPECTRUM: 300, 600, 900, 1200 k
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The ZZ-KAFAX-E70 is a MATXS-format, 150-group neutron and 12-group photon cross section library for fast reactors based on ENDF/B-VII.0. This library was originally generated for the KALIMER (Korea Advanced LIquid MEtal Reactor) core analyses. It includes 144 nuclide data processed with the NJOY99.245 code patched with NEA020. The library can be used to generate the problem-dependent group constants for neutron and/or photon transport calculations through the DANTSYS, DOORS, or PARTISN code systems.
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4. METHODS

The KAFAX-E70 was generated at 300, 600, 900, and 1200 K. It contains the self-shielded cross sections for 5 to 10 background cross sections depending on the nuclides. The neutron group structure consists of one-eighth lethargy widths in almost all the energy ranges, except between 1 and 10 keV in which one-sixteenth lethargy widths were used. (Table 2) The LANL 12-group structure (IGG=3) provided in the NJOY code was selected as a photon group structure. In the NJOY processing, an equilibrium core flux of the KALIMER-150 core was used as a weighting function. The background cross sections for a self-shielding were also selected from those of the calculations. The library has been validated through the fast benchmark experiments taken from the CSEWG benchmark specifications and BFS critical assemblies.
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8. RELATED OR AUXILIARY PROGRAMS

DANTSYS 3.0 (CCC-0547): One-, Two-, and Three-Dimensional, Multigroup, Discrete Ordinate Transport Code System

DOORS-3.2 (CCC-0650): One-, Two-, and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System

PARTISN 4.00 (CCC-0707): Time-Dependent, Parallel Neutral Particle Transport Code System

TRANSX 2.15 (PSR-0317): Code System to Produce Neutron, Photon, and Particle Transport Tables for Discrete-Ordinates and Diffusion Codes from Cross Sections in MATXS Format
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9. STATUS
Package ID Status date Status
NEA-1815/01 02-FEB-2009 Tested at NEADB
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10. REFERENCES

- C.-S Gil: ZZ-KAFAX-F22, 80 and 24 Groups Cross-Section Library in MATXS Format Based on JEF-2.2 for Fast Reactors, NEA-1650, OECD/NEA Data Bank, Issy-les-Moulineaux, France (2002).
- D.H. Kim and C.-S. Gil: Benchmark Calculations for Fast Reactors using JEFF-3.1, ENDF/B-VII and JENDL-3.3, JEFDOC-1108, JEFF/EFF/EAF Meetings, OECD/NEA, Issy-les-Moulineaux, France (2005).
- D.H. Kim, C.-S. Gil, and Y.-O. Lee: Validation Tests of the Multigroup Cross Section Libraries for Fast Reactors, PHYSOR-2006, ANS Topical Meeting on Reactor Physics, Vancouver, BC, Canada (2006).
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11. HARDWARE REQUIREMENTS:  Hard disk space of 223 MB is required.
NEA-1815/01
Tested at the NEA Data Bank on a PC with 3GHz INTEL Pentium 4 RAM 1Gb, WINDOWS XP Professional SP3, Compaq Version 6.6 (Update A).
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS

Do Heon Kim
Nuclear Data Evaluation Lab.
Korea Atomic Energy Research Institute
P.O. Box 105, Yuseong, Daejeon, 305-600, Rep. of Korea
  
Choong-Sup Gil
Nuclear Data Evaluation Lab.
Korea Atomic Energy Research Institute
P.O. Box 105, Yuseong, Daejeon, 305-600, Rep. of Korea
  
Young-Ouk Lee
Nuclear Data Evaluation Lab.
Korea Atomic Energy Research Institute
P.O. Box 105, Yuseong, Daejeon, 305-600, Rep. of Korea
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16. MATERIAL AVAILABLE
NEA-1815/01
KAFAX-E70: MATXS-format library
INDEX-E70: Index file for KAFAX-E70
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17. CATEGORIES
  • Z. Data.

Keywords: ENDF/B-VII.0, Kalimer, MATXS, fast reactors.