钨
材料科学
熔点
聚变能
热流密度
热导率
焊剂(冶金)
等离子体
铜
粒子(生态学)
冶金
核物理学
热力学
传热
复合材料
物理
地质学
海洋学
作者
Y. Ueda,K. Schmid,M. Balden,J.W. Coenen,Th. Loewenhoff,Atsushi Ito,Akira Hasegawa,Chris Hardie,M. Porton,Mark R. Gilbert
出处
期刊:Nuclear Fusion
[IOP Publishing]
日期:2017-06-09
卷期号:57 (9): 092006-092006
被引量:165
标识
DOI:10.1088/1741-4326/aa6b60
摘要
In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing materials (PFMs) and coolant tube materials, respectively, mainly due to high thermal conductivity and, in the case of tungsten, its high melting point. In this paper, recent understandings and future issues on responses of tungsten and Cu alloys to fusion environments (high particle flux (including T and He), high heat flux, and high neutron doses) are reviewed. This review paper includes; Tritium retention in tungsten (K. Schmid and M. Balden), Impact of stationary and transient heat loads on tungsten (J.W. Coenen and Th. Loewenhoff), Helium effects on surface morphology of tungsten (Y. Ueda and A. Ito), Neutron radiation effects in tungsten (A. Hasegawa), and Copper and copper alloys development for high heat flux components (C. Hardie, M. Porton, and M. Gilbert).
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