Studies of material migration and deposition after the 2017 experimental campaign in EAST

• DOI: 10.1016/j.nme.2021.101103
• Publication Date: 2021-12-14T07:45:10Z
• Authors: Rong Yan; Jiao Peng; Changjun Li; Guoliang Xu; Rui Ding; Wei Zheng; Binfu Gao; Dahuan Zhu; Baoguo Wang; Lei Mu; Junling Chen; Fujun Gou; Yuwei You; Zongbiao Ye; Kun Zhang; Xiongyuan Si
• Keywords: Deposition; Fusion power

Plasma-wall interaction is one of the key issues in tokamaks, as material erosion and deposition will strongly influence lifetime plasma facing materials, fuel retention performance. Material migration have been firstly analyzed after 2017 experimental campaign EAST with tungsten (W) upper divertor, molybdenum inner wall graphite lower divertor. It found that deposited elements on plasma-facing materials (PFMs) mainly consisted Li, C, O, W Mo etc, which was from conditioning sputtering PFMs. More than 90 wt% deposits were lithium carbonate hydroxide due to routine EAST. Quantitative characterization element density tile divertor showed increased when closer consistent decreasing normalized poloidal magnetic flux. The composition PFMs along direction has measured by handheld X-ray fluorescence (XRF). concentration less 0.2 most PFM surface. Double peaks near at midplane observed TZM surface high-field side, can be explained higher redeposition location or a smaller Besides, more redeposited outer strike points compared dome region.