Plasma and Fusion Research
Volume 9, 3405041 (2014)
Regular Articles
- The Graduate University for Advanced Studies, Toki, Gifu 509-5292, Japan
- 1)
- National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292, Japan
- 2)
- RIAM, Kyushu University, Kasuga, Fukuoka 816-8580, Japan
Abstract
First wall particle flux measurements in the QUEST spherical tokamak have been conducted, using a permeation probe that employs a first wall candidate ferritic steel alloy F82H as the membrane and also SUS304 as a comparative reference membrane. Permeation measurements have been done during the conditioning steady-state discharges heated with 2.45 GHz and 8.2 GHz ECR. Diffusion and recombination coefficients measured in a laboratory-scale plasma device: VEHICLE-1 are used to interpret the results from the permeation probe measurements in QUEST. These permeation membranes have been analyzed with XPS to evaluate the effects of surface impurities.
Keywords
plasma-driven permeation, QUEST, reduced activation ferritic steel, stainless steel, first wall, hydrogen plasma
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This paper may be cited as follows:
Haishan ZHOU, Yoshi HIROOKA, Hideki ZUSHI, Arseniy KUZMIN and the QUEST group, Plasma Fusion Res. 9, 3405041 (2014).