Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in SCTF core-I forced feed tests

Iwamura, Takamichi; not registered; Sudo, Yukio; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; not registered; Murao, Yoshio

no abstracts in English

Language	:	English
Report No.	:	JAERI-M 91-093
Pages	:	89 Pages
Publication Year/Month	:	1991/06
Patent information	:
PDF	:	JAERI-M-91-093.pdf:1.87MB
Paper URL	:	https://doi.org/10.11484/jaeri-m-91-093
Keywords	:	Reactor Safety; Reflood; SCTF; LOCA; Quench; Heat Transfer; PWR; Two Phase Flow; Two-dimensional
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:
Other institute's report number	:

Acecsses	:	- Accesses
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Registration No. : M19910093
JAEA Abstracts No. : 190421

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