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Oral presentation

Evaluation of detailed thermal neutron flux distribution in graphite-moderated reactor by Monte-Carlo code

Nakagawa, Naoki*; Fujimoto, Nozomu*; Ho, H. Q.; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo

no journal, , 

no abstracts in English

Oral presentation

Evaluation of analysis accuracy in graphite-moderated critical assembly by Monte-Carlo code

Nakagawa, Naoki*; Fujimoto, Nozomu*; Ho, H. Q.; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo

no journal, , 

no abstracts in English

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