Assessment of TRAC-PF1/MOD1 code for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with a radial power distribution

Onuki, Akira; not registered; Murao, Yoshio

no abstracts in English

Language	:	English
Report No.	:	JAERI-M 93-139
Pages	:	85 Pages
Publication Year/Month	:	1993/07
Patent information	:
PDF	:	JAERI-M-93-139.pdf:1.79MB
Paper URL	:	https://doi.org/10.11484/jaeri-m-93-139
Keywords	:	Reactor Safety; Heat Transfer; Void Fraction; Two-phase Flow; Reflood; Film Boiling; Numerical Simulation; TRAC Code
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:
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Acecsses	:	- Accesses
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Registration No. : M19930139
JAEA Abstracts No. : 210571

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