Modeling and analysis of thermal-hydraulic response of uranium-aluminum reactor fuel plates under transient heatup conditions

S.Navarro-Valenti*; S.H.Kim*; V.Georgevich*; R.P.Taleyarkhan*; Fuketa, Toyoshi; Soyama, Kazuhiko ; Ishijima, Kiyomi; Kodaira, Tsuneo

no abstracts in English

Language	:	English
Journal	:	NUREG/CP-0142 (Vol. 4)
Volume	:	0
Number	:
Pages	:	p.2957 - 2976
Publication Year/Month	:	1996/00
Meeting title	:	7th Int. Meeting on Nuclear Reactor Thermal-Hydraoulics; NURETH-7
Held date	:	1995/09
Location (city)	:	America
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DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	Thermal Hydraulics; Transient Boiling Heat Transfer; Reactor Safety; Uranium Silicide Fuel; Advanced Neutron Source; NSRR; HEATING Code
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Registration No. : B19941514
JAEA Abstracts No. : 240535
Paper Submission No. : 14009

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