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	Code development and safety analyses for Pb-Bi-cooled direct contact boiling water fast reactor (PBWFR)
	Tian, Y. H.; Su, G. H.; Wang, J.; Tian, W. X.; Qiu, S. Z.
刊名	PROGRESS IN NUCLEAR ENERGY
	2013
卷号	68期号:[db:dc_citation_issue]页码:177-187
关键词	Fast reactor Direct contact Lead-bismuth eutectic Natural circulation Safety
ISSN号	0149-1970
DOI	[db:dc_identifier_doi]
URL标识	查看原文
WOS记录号	[DB:DC_IDENTIFIER_WOSID]
内容类型	期刊论文
URI标识	http://www.corc.org.cn/handle/1471x/4444258
专题	西安交通大学
推荐引用方式 GB/T 7714	Tian, Y. H.,Su, G. H.,Wang, J.,et al. Code development and safety analyses for Pb-Bi-cooled direct contact boiling water fast reactor (PBWFR)[J]. PROGRESS IN NUCLEAR ENERGY,2013,68([db:dc_citation_issue]):177-187.
APA	Tian, Y. H.,Su, G. H.,Wang, J.,Tian, W. X.,&Qiu, S. Z..(2013).Code development and safety analyses for Pb-Bi-cooled direct contact boiling water fast reactor (PBWFR).PROGRESS IN NUCLEAR ENERGY,68([db:dc_citation_issue]),177-187.
MLA	Tian, Y. H.,et al."Code development and safety analyses for Pb-Bi-cooled direct contact boiling water fast reactor (PBWFR)".PROGRESS IN NUCLEAR ENERGY 68.[db:dc_citation_issue](2013):177-187.

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