In-vessel thermal-hydraulics analyses of the ASTRID-600MWe reactor with STAR-CCM+ code to supply boundary conditions for mechanical evaluation

Onoda, Yuichi ; Chikazawa, Yoshitaka ; Nakamura, Hironori*; Barbier, D.*; Dirat, J.-F.*

no abstracts in English

Language	:	English
Journal	:	Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet)
Volume	:
Number	:
Pages	:	8 Pages
Publication Year/Month	:	2019/05
Meeting title	:	27th International Conference on Nuclear Engineering (ICONE-27)
Held date	:	2019/05
Location (city)	:	Tsukuba
Location (country)	:	Japan
Patent information	:
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DOI for research data	:
Keywords	:	ASTRID; CFD; Scram; Loss of Grid; thermal load
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	経済産業省

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Registration No. : BB20182021
JAEA Abstracts No. : 47001257
Paper Submission No. : 21893

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