Thermal and hydraulic tests of a standard fuel rod of HTTR with HENDEL

Takase, Kazuyuki; Hino, Ryutaro; not registered

no abstracts in English

Language	:	Japanese
Journal	:	Nihon Genshiryoku Gakkai-Shi
Volume	:	32
Number	:	11
Pages	:	p.1107 - 1110
Publication Year/Month	:	1990/11
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Paper URL	:	https://doi.org/10.3327/jaesj.32.1107 Read or search this article
DOI for research data	:
Keywords	:	Fluid Dynamics; Forced Convection; High Temperature Reactor; Helium Gas; Fuel Channel; Annular Passage; Fuel Rod; Friction Factor; Heat Transfer
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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:86.39 Category:Nuclear Science & Technology
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Registration No. : A19900261
JAEA Abstracts No. : 190070
Paper Submission No. : 10097

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