Core radial power profile effect on system and core cooling behavior during reflood phase of PWR-LOCA with CCTF data

not registered; not registered; Murao, Yoshio

no abstracts in English

Language	:	English
Journal	:	Journal of Nuclear Science and Technology
Volume	:	22
Number	:	7
Pages	:	p.538 - 550
Publication Year/Month	:	1985/00
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Paper URL	:	https://doi.org/10.3327/jnst.22.538
DOI for research data	:
Keywords	:	Reactor Safety; PWR Type Reactors; Loss of Coolant; Reflood; Two-phase Flow; Thermohyraulics; CCTF; Radial Core Profile
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Accesses	:	- Accesses
Web of Science® Times Cited Count	:	Times Cited Count： If you would like to get the latest times cited, please access the Web of Science®. http://www.webofknowledge.com/wos
InCites™	:	Percentile:80.38 Category:Nuclear Science & Technology
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Registration No. : A19844409
JAEA Abstracts No. :
Paper Submission No. : 7394

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