ウエダ　ヨシオ   Ueda Yoshio   上田　良夫    所属   追手門学院大学  理工学部 電気電子工学科    職種   教授
言語種別	英語
発行・発表の年月	2017/06/09
形態種別	論文
査読	査読あり
標題	Baseline high heat flux and plasma facing materials for fusion
執筆形態	共著・編著（代表編著を除く）
掲載誌名	Nuclear Fusion
出版社・発行元	Institute of Physics Publishing
巻・号・頁	57(9)
担当区分	筆頭著者
国際共著	国際共著
著者・共著者	Y. Ueda,K. Schmid,M. Balden,J. W. Coenen,Th Loewenhoff,A. Ito,A. Hasegawa,C. Hardie,M. Porton,M. Gilbert
概要	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).
DOI	10.1088/1741-4326/aa6b60
ISSN	1741-4326/1741-4326