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	Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System
	Wei, Shiying; Wang, Chenglong; Su, Guanghui; Tian, Wenxi; Qiu, Suizheng
刊名	Hedongli Gongcheng/Nuclear Power Engineering
	2018
卷号	39页码:067-070
关键词	Cladding failures Coolant systems Direct contact boiling Lead-bismuth reactors Reactor systems Steady state and transients System safety Thermal hydraulics
ISSN号	0258-0926
URL标识	查看原文
内容类型	期刊论文
URI标识	http://www.corc.org.cn/handle/1471x/2906664
专题	西安交通大学
推荐引用方式 GB/T 7714	Wei, Shiying,Wang, Chenglong,Su, Guanghui,et al. Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System[J]. Hedongli Gongcheng/Nuclear Power Engineering,2018,39:067-070.
APA	Wei, Shiying,Wang, Chenglong,Su, Guanghui,Tian, Wenxi,&Qiu, Suizheng.(2018).Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System.Hedongli Gongcheng/Nuclear Power Engineering,39,067-070.
MLA	Wei, Shiying,et al."Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System".Hedongli Gongcheng/Nuclear Power Engineering 39(2018):067-070.

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