Influence analysis of coupled neutronics and thermal-hydraulics on characteristics of supercritical water-cooled reactor system

被引:0
|
作者
Chen, Juan [1 ]
Zhou, Tao [1 ]
Luo, Feng [1 ]
Wang, Han-Ding [1 ]
Cheng, Wan-Xu [1 ]
机构
[1] Institute of Nuclear Thermal-Hydraulic Safety and Standardization, North China Electric Power University, Beijing 102206, China
关键词
Light water reactors;
D O I
10.7538/yzk.2013.47.05.0804
中图分类号
学科分类号
摘要
引用
收藏
页码:804 / 810
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