Author:
Zhong Yajuan,Zhang Junpeng,Lin Jun,Xu Liujun,Zhang Feng,Xu Hongxia,Chen Yu,Jiang Haitao,Li Ziwei,Zhu Zhiyong,Guo Quangui
Funder
Thorium Molten Salt Reactor Nuclear Energy System
Frontier Science Key Program of the Chinese Academy of Sciences
CAS Key Laboratory of Carbon Materials
National Natural Science Foundation of China
Natural Science Foundation of Shanghai
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference21 articles.
1. The molten salt reactor (MSR) in generation IV: overview and perspectives;Serp;Prog. Nucl. Energy,2014
2. Graphitic Matrix Materials for Spherical HTR Fuel Elements;Schulze,1982
3. Advances in High Temperature Gas Cooled Reactor Fuel Technology,2012
4. Anisotropy of coefficient of thermal expansion of nuclear graphite under compressive stresses;Zhou;Nucl. Eng. Des.,2011
Cited by
15 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献