Development of burn-up calculation modules in the MOSRA system

Okumura, Keisuke ; Kojima, Kensuke; Okamoto, Tsutomu

As a part of the modular system for reactor analyses (MOSRA), three burn-up calculation modules are newly developed with use of the latest nuclear data JENDL-4.0. One is a burn-up calculation module (MOSRA-SRAC) based on a two-dimensional collision probability method with 200-group constants, the second one is a point burn-up calculation module (MOSRA-Bacon), and the last is MOSRA-SuperBacon which execute MOSRA-SRAC and MOSRA-Bacon alternately. The employed data and calculation methods are validated by intercomparison with calculated results and comparison with assay data of a spent nuclear fuel sample from LWR.

Language	:	Japanese
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Meeting title	:	日本原子力学会2012年秋の大会
Held date	:	2012/09
Location (city)	:	東広島
Location (country)	:	日本
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Keywords	:	no keyword
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Registration No. : BB20120815
JAEA Abstracts No. :
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