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	SARAX: A new code for fast reactor analysis part I: Methods
	Zheng, Youqi; Du, Xianan; Xu, Zhitao; Zhou, Shencheng; Liu, Yong; Wan, Chenghui; Xu, Longfei
刊名	Nuclear Engineering and Design
	2018
卷号	340页码:421-430
关键词	Computing technology Cross section generation Neutron diffusion Neutron transport Numerical benchmark Research and development Sensitivity and uncertainty analysis Transport calculation
ISSN号	0029-5493
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/2918634
专题	西安交通大学
推荐引用方式 GB/T 7714	Zheng, Youqi,Du, Xianan,Xu, Zhitao,et al. SARAX: A new code for fast reactor analysis part I: Methods[J]. Nuclear Engineering and Design,2018,340:421-430.
APA	Zheng, Youqi.,Du, Xianan.,Xu, Zhitao.,Zhou, Shencheng.,Liu, Yong.,...&Xu, Longfei.(2018).SARAX: A new code for fast reactor analysis part I: Methods.Nuclear Engineering and Design,340,421-430.
MLA	Zheng, Youqi,et al."SARAX: A new code for fast reactor analysis part I: Methods".Nuclear Engineering and Design 340(2018):421-430.

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