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论文类型： 期刊论文

发表时间： 2014-10-01

发表刊物： 11th International Symposium on Fusion Nuclear Technology (ISFNT)

收录刊物： SCIE、EI、CPCI-S

卷号： 89

期号： 7-8

页面范围： 949-954

ISSN号： 0920-3796

关键字： Laser-induced breakdown spectroscopy; Lithiated tungsten; Deuterium retention; Blistering on tungsten; Lithium re-deposition

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 in long-pulse tokamaks like EAST. The investigation of lithiated tungsten is important for understanding the lithium conditioning effects for EAST, where tungsten will be used as a plasma-facing material. In this paper, a few important issues of lithiated tungsten interacting with high-flux deuterium plasma have been studied, such as the effect of lithiation on deuterium retention, the profile of elemental distribution, and the chemical state of lithiated tungsten. Deuterium retention inside both pure and lithiated tungsten has been investigated for the first time in the linear plasma simulator Magnum-PSI by in-situ laser induced breakdown spectroscopy (LIES). The results indicate that, after deuterium plasma exposure, deuterium retention could be saturated in the lithiation layer, and the lithium in the lithiated layer is chemically bound with deuterium. Moreover, the lithiation can inhibit the blistering on the tungsten surface. These results can be valuable for the application of LIBS as a diagnostic technique for plasma-facing components of tokamaks. (c) 2014 Elsevier B.V. All rights reserved.