Analysis of Transient Thermal-Hydraulic and Safety of Lead-Cooled Fast Reactor Based on Unified Coupling Framework

被引：0
|
作者：
Luo, Xiao [1 ]
Zhang, Xilin [2 ]
Chen, Hongli [1 ]
Wang, Shuai [1 ]
Guo, Chao [2 ]
Wang, Chi [3 ]
机构：
[1] University of Science and Technology of China, Hefei,230026, China
[2] Nuclear Power Institute of China, Chengdu,610213, China
[3] China Academic of Engineering Physics, Mianyang,621900, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2021年 / 42卷
关键词：
13;
D O I：
10.13832/j.jnpe.2021.S1.0011
中图分类号：
学科分类号：
摘要：
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页码：11 / 16
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