In-vessel inspection of arc traces on the W7-X plasma facing components after the operation phase OP2.1

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
D. Hwangbo , C.P. Dhard , S. Kajita , D. Naujoks , Y. Gao , The W7-X Team
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Abstract

Updated distribution of arc traces across the interior walls after the operation phase 2.1 of Wendelstein 7-X (W7-X) is reported. A total of 105 new arc places were found, with 95% of them located around the stainless steel panels, diagnostic ports, and the glow discharge cleaning electrodes. Remaining 5% of the traces were found on carbon surfaces such as the graphite baffle and carbon fiber-reinforced composites divertor tiles, for the first time in W7-X. The arcing on the divertor tiles showed a retrograde motion, suggesting that the arcing must have occurred during the main plasma operations. A simple estimate of the mass loss due to arcing on the divertor area shows that 0.2-0.3 g of carbon was eroded during OP2.1. This amount turns out to be a significantly smaller amount compared to the estimated losses due to sputtering, 7.6 g/1800 s during OP1.2b (Brezinsek et al., 2021).
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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