Reactor pressure vessel design of the high temperature engineering test reactor

Tachibana, Yukio ; Nakagawa, Shigeaki ; Iyoku, Tatsuo

no abstracts in English

Language	:	English
Journal	:	Nuclear Engineering and Design
Volume	:	233
Number	:	1-3
Pages	:	p.103 - 112
Publication Year/Month	:	2004/10
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Paper URL	:	https://doi.org/10.1016/j.nucengdes.2004.07.015
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	HTGR; HTTR; Reactor Pressure Vessel; 2 1/4Cr-1Mo Steel; Embrittlement; In-service Inspection
Research Facility	:	HTTR(高温工学試験研究炉)
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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:9.81 Category:Nuclear Science & Technology
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Registration No. : A20040181
JAEA Abstracts No. : 330181
Paper Submission No. : 21583

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