Criticality analysis of uranium fueled thermal spectrum cores of Kyoto Univ. Critical Assembly using JENDL-3.3, ENDF/B-VI.8 and JEFF3.1 libraries

Conference · Sat Jul 01 00:00:00 EDT 2006

OSTI ID:22039737

Unesaki, H; Misawa, T; Ichihara, C; Nakamura, H; Shiroya, S; Nakajima, K ^[1]

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1. Research Reactor Inst., Kyoto Univ., Asashiro-Nishi 2, Kumatori-cho, Sennan-gun, Osaka 590-0494 (Japan)

This paper provides the results of criticality analysis of uranium fueled, polyethylene-moderated/reflected thermal spectrum cores performed at the solid moderated cores of Kyoto Univ. Critical Assembly. A wide variety of neutron spectra as well as different effective uranium enrichment have been realized in the experiments. The analyses have been performed by continuous energy Monte Carlo code MVP using cross section data based on JENDL-3.3, ENDF/B-VI.8 and JEFF3.1 libraries. All libraries gave the C/E values within {+-}0.5% to unity for most cases. Enrichment dependence and spectrum index dependence of the C/E values have been observed. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22039737
• Resource Relation: Conference: PHYSOR-2006: American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, Vancouver, BC (Canada), 10-14 Sep 2006; Other Information: Country of input: France; 4 refs.
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CRITICALITY
CROSS SECTIONS
KUCA REACTOR
M CODES
MONTE CARLO METHOD
NEUTRON SPECTRA
NUCLEAR DATA COLLECTIONS
POLYETHYLENES
REACTOR CORES
THERMAL NEUTRONS