Journal Article

FZJ-2017-05339

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Baseline high heat flux and plasma facing materials for fusion

Ueda, Y. (Corresponding author) ; Schmid, K. ; Balden, M. ; Coenen, J. W.FZJ* ; Loewenhoff, T.FZJ* ; Ito, A. ; Hasegawa, A. ; Hardie, C. ; Porton, M. ; Gilbert, M.

2017
IAEA Vienna

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Please use a persistent id in citations: doi:10.1088/1741-4326/aa6b60

Abstract: 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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Contributing Institute(s):

1. Plasmaphysik (IEK-4)
2. Werkstoffstruktur und -eigenschaften (IEK-2)

Research Program(s):

1. 174 - Plasma-Wall-Interaction (POF3-174) (POF3-174)

Appears in the scientific report 2017

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Database coverage:
Current Contents - Physical, Chemical and Earth Sciences ; Ebsco Academic Search ; IF < 5 ; JCR ; National-Konsortium ; Nationallizenz ; SCOPUS ; Science Citation Index ; Science Citation Index Expanded ; Thomson Reuters Master Journal List ; Web of Science Core Collection

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