Research status and issues of tungsten plasma facing materials for ITER and beyond |
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| Affiliation: | 1. Graduate School of Engineering, Osaka University, 2-1 Yamadaoka, Suita, Osaka 565-0871, Japan;2. Forschungszentrum Jülich GmbH, EURATOM Association, Jülich D-52425, Germany;3. FOM Institute DIFFER, Association EURATOM-FOM, Trilateral Euregion Cluster, Postbus 1207, Nieuwegein3430BE, The Netherlands;4. Center for Energy Research, University of California in San Diego, 9500 Gilman Dr, La Jolla, CA 92093-0417, USA;5. CEA/DSM/IRFM, CEA Cadarache, Saint-Paul-lez-Durance, France;1. School of Physics and Optoelectronic Technology, Dalian University of Technology, Dalian 116024, People’s Republic of China;2. School of Physics and Materials Engineering, Dalian Nationalities University, Dalian 116600, People’s Republic of China;3. Fujian Key Laboratory for Plasma and Magnetic Resonance, Department of Electronic Science, Aeronautics, School of Physics and Mechanical & Electrical Engineering, Xiamen University, Xiamen, Fujian 361005, People’s Republic of China;1. Department of Physics, Beihang University, Beijing 100191, PR China;2. School of Material Engineering, Panzhihua University, Panzhihua 617000, PR China;3. State Key Laboratory of Nuclear Physics and Technology, Institute of Heavy Ion Physics, Peking University, Beijing 100871, PR China;1. NRC «Kurchatov Institute», Akademika Kurchatova pl., Moscow, Russia;2. SRC RF TRINITI, Moscow Region, Russia;3. Efremov Institute, St. Petersburg, Russia;4. Institution «Project Center ITER», Moscow, Russia;5. National Research Nuclear University MEPhI, Kashirskoe sh. 31, Moscow, Russia;1. Department of Material Science, Shimane University, Matsue, Shimane 690-8504, Japan;2. Center for Energy Research, University of California at San Diego, La Jolla, CA 92093-0417, USA;3. RIAM, Kyushu University, Kasuga, Fukuoka 816-8580, Japan;4. Graduate School of Engineering, Osaka University, 2-1 Yamadaoka, Suita 565-0871, Japan;5. National Institute for Fusion Science, Oroshi, Toki, Gifu 509-5292, Japan;1. Southwestern Institute of Physics, P.O. Box 432, Chengdu 610041, Sichuan, China;2. Central South University, Changsha 410083, China;3. Xiamen Honglu Tungsten & Molybdenum Industry Co., Ltd, Xiamen, China |
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| Abstract: | This review summarizes surface morphology changes of tungsten caused by heat and particle loadings from edge plasmas, and their effects on enhanced erosion and material lifetime in ITER and beyond. Pulsed heat loadings by transients (disruption and ELM) are the largest concerns due to surface melting, cracking, and dust formation. Hydrogen induced blistering is unlikely to be an issue of ITER. Helium bombardment would cause surface morphology changes such as W fuzz, He holes, and nanometric bubble layers, which could lead to enhanced erosion (e.g. unipolar arcing of W fuzz). Particle loadings could enhance pulsed heat effects (cracking and erosion) due to surface layer embrittlement by nanometric bubbles and solute atoms. But pulsed heat loadings alleviate surfaces morphology changes in some cases (He holes by ELM-like heat pulses). Effects of extremely high fluence (～1030 m?2), mixed materials, and neutron irradiation are important issues to be pursued for ITER and beyond. In addition, surface refurbishment to prolong material lifetime is also an important issue. |
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| Keywords: | Tungsten Plasma facing materials ITER He bubbles ELM-like heat pulse |
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