Published 2004
| Version v1
Miscellaneous
Generation of the pseudo fission products for burnup calculations of liquid metal fast reactor
Creators
- 1. Kyunghee University, Yongin (Korea, Republic of)
Description
The pseudo fission products for burnup calculations of 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 liquid metal fast reactor at KAERI. The 80 groups, MATXS-format libraries of the 172 fission products were generated and burnup chains for generation of the pseudo fission products were prepared
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [8 p.]
Conference
- Title
- 2004 spring meeting of the KNS
- Dates
- 27-28 May 2004
- Place
- Gyeongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 35100309
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; COMPUTER CALCULATIONS; CROSS SECTIONS; FISSION PRODUCTS; LIQUID METAL COOLED REACTORS; PLUTONIUM; URANIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; ISOTOPES; MATERIALS; METALS; RADIOACTIVE MATERIALS; REACTORS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 4 refs, 3 figs, 1 tab