Application of the JENDL-4.0 nuclear data set for the uncertainty analysis of the prototype FBR Monju

Konomura, Mamoru; Tamagno, P.*; Takeda, Toshikazu*; Van Rooijen, W. F. G.*

The presentation deals with uncertainty analysis on Monju fast reactor using the JENDL-4.0 nuclear data set and the ERANOS code. For this study, cross-sections library had to be produced for the ERANOS cell code ECCO and verified with the benchmarks MZA and MZB. Monju 2010 restart reactivity measurement was modeled using several libraries. Uncertainty analysis is performed and comparison is done with the former JENDL-3.3 evaluation.

Language	:	English
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Meeting title	:	日本原子力学会2012年春の年会
Held date	:	2012/03
Location (city)	:	福井
Location (country)	:	日本
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DOI for research data	:
Keywords	:	no keyword
Research Facility	:	もんじゅ(高速増殖炉原型炉)
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Registration No. : BB20112896
JAEA Abstracts No. :
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