Author:
Zhou Hai-Shan,Xu Yu-Ping,Sun Ning-Bo,Zhang Ying-Chun,Oya Yasuhisa,Zhao Ming-Zhong,Mao Hong-Min,Ding Fang,Liu Feng,Luo Guang-Nan
Funder
National Magnetic Confinement Fusion Science Program of China
National Natural Science Foundation of China
Technological Development Grant of Hefei Science Center of CAS
Scientific Research Grant of Hefei Science Center of CAS
Korea Research Council of Fundamental Science and Technology (KRCF)
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference18 articles.
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3. Progress of ITER full tungsten divertor technology qualification in Japan;Ezato;Fusion Eng. Des.,2015
4. PSI issues at plasma facing surfaces of blankets in fusion reactors;Ueda;J. Nucl. Mater.,2003
5. Exposure of vacuum plasma spraying tungsten to PISCES and DIII-D plasmas;Zhou;Fusion Eng. Des.,2011
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