Author:
Wang Haoran,Xu Liujun,Zhong Yajuan,Lin Jun,Tang Hui,Xu Hongxia,Zhang Feng,Yang Xu,Zhu Zhiyong
Funder
Gansu Provincial Natural Science Foundation
Chinese Academy of Sciences
Shanghai Municipal Natural Science Foundation
Subject
Materials Chemistry,Mechanics of Materials,General Materials Science
Reference23 articles.
1. The molten salt reactor (MSR) in generation IV: overview and perspectives;Serp;Biol. Sci.,2014
2. Nuclear Fuel for High Temperature Gas-cooled Reactors;Lindemer,1974
3. Graphitic Matrix Materials for Spherical HTR Fuel Elements;Schulze,1982
4. Advances in High Temperature Gas Cooled Reactor Fuel Technology,2012
5. Anisotropy of coefficient of thermal expansion of nuclear graphite under compressive stresses;Zhou;Nucl. Eng. Des.,2011