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Report No.

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.



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