Group Constants Generation of the Pseudo Fission Products for Fast Reactor Burnup Calculations

Journal Article · Tue May 24 04:00:00 EDT 2005 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.1945063· OSTI ID:20722613

Gil, Choong-Sup; Kim, Do Heon; Chang, Jonghwa ^[1]

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1. Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusung-gu, Taejon (Korea, Republic of)

The pseudo fission products for the burnup calculations of the liquid metal fast reactor were generated. The cross-section data and fission product yield data of ENDF/B-VI were used for the pseudo fission product data of U-235, U-238, Pu-239, Pu-240, Pu-241, and Pu-242. The pseudo fission product data can be used with the KAFAX-F22 or -E66, which are the MATXS-format libraries for analyses of the liquid metal fast reactor at KAERI and were distributed through the OECD/NEA. The 80-group MATXS-format libraries of the 172 fission products were generated and the burnup chains for generation of the pseudo fission products were prepared.

• OSTI ID: 20722613
• Journal Information: AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 769; ISSN 0094-243X; ISSN APCPCS
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BURNUP
FISSION
FISSION PRODUCTS
FLUORINE 22
GROUP CONSTANTS
KAERI
LMFBR TYPE REACTORS
NEA
NUCLEAR DATA COLLECTIONS
NUCLEAR FUELS
NUCLEAR REACTION YIELD
PLUTONIUM
PLUTONIUM 239
PLUTONIUM 240
PLUTONIUM 241
PLUTONIUM 242
URANIUM
URANIUM 235
URANIUM 238