Evaluation report on SCTF core-II test S2-08; Effect of core inlet subcooling on thermal-hydraulic behavior including two-dimensional behavior in pressure vessel during reflood in PWR-LOCA

Onuki, Akira; Iwamura, Takamichi; Abe, Yutaka; not registered; Murao, Yoshio

no abstracts in English

Language	:	English
Report No.	:	JAERI-M 90-236
Pages	:	76 Pages
Publication Year/Month	:	1991/01
Patent information	:
PDF	:	JAERI-M-90-236.pdf:1.52MB
Paper URL	:	https://doi.org/10.11484/jaeri-m-90-236
Keywords	:	Reactor Safety; PWR; LOCA; Reflood; SCTF; Subcooling; Heat Transfer; Void Fraction; Quench
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:
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Registration No. : M19900236
JAEA Abstracts No. : 190147

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