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	Thermal-hydraulic analysis code development for sodium heated once-through steam generator
	Xu, Rongshuan; Zhang, Dalin; Tian, Wenxi; Qiu, Suizheng; Su, G.H.
刊名	Annals of Nuclear Energy
	2019
卷号	127页码:385-394
关键词	China experiment fast reactor Computer codes Generate electricity Once through steam generator Sodium cooled fast reactors (SFR) Thermal hydraulic modeling Thermal hydraulic parameters Thermal-hydraulic analysis
ISSN号	0306-4549
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/2828481
专题	西安交通大学
推荐引用方式 GB/T 7714	Xu, Rongshuan,Zhang, Dalin,Tian, Wenxi,et al. Thermal-hydraulic analysis code development for sodium heated once-through steam generator[J]. Annals of Nuclear Energy,2019,127:385-394.
APA	Xu, Rongshuan,Zhang, Dalin,Tian, Wenxi,Qiu, Suizheng,&Su, G.H..(2019).Thermal-hydraulic analysis code development for sodium heated once-through steam generator.Annals of Nuclear Energy,127,385-394.
MLA	Xu, Rongshuan,et al."Thermal-hydraulic analysis code development for sodium heated once-through steam generator".Annals of Nuclear Energy 127(2019):385-394.

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