Study of deuterium retention on lithiated tungsten exposed to high-flux deuterium plasma using laser-induced breakdown spectroscopy |
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| Affiliation: | 1. Key Laboratory of Materials Modification by Laser, Ion and Electron Beams, Chinese Ministry of Education, School of Physics and Optical Electronic Technology, Dalian University of Technology, Dalian 116024, PR China;2. FOM Institute DIFFER, Dutch Institute for Fundamental Energy Research, Association EURATOM-FOM, Trilateral Euregio Cluster, P.O. Box 1207, 3430 BE Nieuwegein, The Netherlands;1. Faculty of Engineering and Resource Science, Akita University, 1-1, Tegatagakuen-cho, Akita 010-8502, Japan;2. Fusion Research and Development Directorate, Japan Atomic Energy Agency, 2-166, Omotedate, Obuchi, Rokkasho, Kamikita, Aomori 039-3212, Japan;1. Korea Atomic Energy Research Institute, Republic of Korea;2. National Fusion Research Institute, Republic of Korea;1. Open Joint-Stock Company “N.A. Dollezhall Research and Development Institute of Power Engineering”, (OJSC “NIKIET”), 107140, Malaya Krasnoselskaya 2/8, Moscow, Russian Federation;2. D.V. Efremov Scientific Research Institute of Electrophysical Apparatus, 196641 St. Petersburg, Russian Federation;1. Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;2. National Fusion Research Institute, Daejeon, Republic of Korea |
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| Abstract: | 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 (LIBS). 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. |
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| Keywords: | Laser-induced breakdown spectroscopy Lithiated tungsten Deuterium retention Blistering on tungsten Lithium re-deposition |
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