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 abstracts in English

Language	:	Japanese
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Meeting title	:	日本原子力学会九州支部第38回研究発表講演会
Held date	:	2019/12
Location (city)	:	福岡
Location (country)	:	日本
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Keywords	:	VHTRC; 高温ガス炉臨界実験装置; MVP3; 黒鉛減速体系; 熱中性子束分布評価
Research Facility	:	VHTRC(高温ガス炉臨界実験装置)
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Article of JAEA R&D Review	:
Cooperating Institute	:	九州大学

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Registration No. : BB20191518
JAEA Abstracts No. :
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