Deuterium Retention in SiC-Coated Graphite Tiles of EAST

Fuel retention and recycling in plasma facing materials is a crucial issue for fusion devices, especially for the long pulse discharge devices. In this work, the deuterium retention and the surface erosion of SiC-coated graphite tiles exposed to EAST plasmas have been studied by post-mortem analyses...

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Published inPlasma science & technology Vol. 16; no. 3; pp. 193 - 196
Main Author 赵利平 王万景 周海山 吴婧 谢春意 李强 杨钟时 罗广南
Format Journal Article
LanguageEnglish
Published 01.03.2014
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Summary:Fuel retention and recycling in plasma facing materials is a crucial issue for fusion devices, especially for the long pulse discharge devices. In this work, the deuterium retention and the surface erosion of SiC-coated graphite tiles exposed to EAST plasmas have been studied by post-mortem analyses, i.e., thermal desorption spectroscopy (TDS), secondary ion mass spec- troscopy (SIMS) and scanning electron microscopy (SEM). The results show that the sample cut from the high field side (HF) tile has been intensely eroded due to deuterium bombardment on plasma facing surfaces in the initial phase of discharges and trapped highest amount of deuterium. Lower deuterium retention has been found in the inner divertor sample, which is presumably due to the particular exposure history in the 2010 spring campaign.
Bibliography:ZHAO Liping, WANG Wanjing, ZHOU Haishan, WU Jing ,XIE Chunyi , LI Qiang ,YANG Zhongshi,LUO Guangnan (1Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China 2Research Center of Laser Fusion, China Academy of Engineering Physics, Mianyang 621000, China)
deuterium retention, post-mortem analyses, SiC-coated graphite tiles, EAST
Fuel retention and recycling in plasma facing materials is a crucial issue for fusion devices, especially for the long pulse discharge devices. In this work, the deuterium retention and the surface erosion of SiC-coated graphite tiles exposed to EAST plasmas have been studied by post-mortem analyses, i.e., thermal desorption spectroscopy (TDS), secondary ion mass spec- troscopy (SIMS) and scanning electron microscopy (SEM). The results show that the sample cut from the high field side (HF) tile has been intensely eroded due to deuterium bombardment on plasma facing surfaces in the initial phase of discharges and trapped highest amount of deuterium. Lower deuterium retention has been found in the inner divertor sample, which is presumably due to the particular exposure history in the 2010 spring campaign.
34-1187/TL
ISSN:1009-0630
DOI:10.1088/1009-0630/16/3/04