Study of deuterium retention on lithiated tungsten exposed to high-flux deuterium plasma using laser-induced breakdown spectroscopy
作者： Cong Li , Xingwei Wu , Chenfei Zhang , Hongbin Ding , G. De Temmerman
DOI: 10.1016/J.FUSENGDES.2014.04.071
关键词:
摘要: Tungsten is under consideration for use as a plasma-facing material in the divertor region of ITER. Lithiation can significantly improve plasma performance long-pulse tokamaks like EAST. The investigation lithiated tungsten important understanding lithium conditioning effects EAST, where will be used material. In this paper, few issues interacting with high-flux deuterium have been studied, such effect lithiation on retention, profile elemental distribution, and chemical state tungsten. Deuterium retention inside both pure has investigated first time linear simulator Magnum-PSI by in-situ laser induced breakdown spectroscopy (LIBS). results indicate that, after exposure, could saturated layer, layer chemically bound deuterium. Moreover, inhibit blistering surface. These valuable application LIBS diagnostic technique components tokamaks.
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