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Progress in development and application of lithium based components for Tokamak
Affiliation:1. JSC “Red Star”, Moscow, Russian Federation;2. SRC TRINITI, Troitsk, Moscow, Russian Federation;1. National Fusion Research Institute, Daejeon, Republic of Korea;2. Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;1. Karlsruhe Institute of Technology (KIT), Institute for Neutron Physics and Reactor Technology (INR), Germany;2. Karlsruhe Institute of Technology (KIT), Institute for Applied Materials (IAM-WPT), Germany;3. Indian Institute of Technology Madras (IITM), Department of Mechanical Engineering, India;1. CEA, DEN, Saclay, DM2S, SERMA, F-91191 Gif-sur-Yvette, France;2. Incka, 19-21 Rue du 8 mai 1945, F-94110 Arcueil, France;1. Korea Atomic Energy Research Institute, 989 Daeduck-daero, Yuseong-gu, Daejeon 305-353, Republic of Korea;2. National Fusion Research Institute, Gwahangno, Yuseong-gu, Daejeon 305-333, Republic of Korea
Abstract:Experiments with lithium plasma facing components (PFCs) show promising results for the operation of hot plasma facilities and the general improvement of plasma parameters. The design and development of new tokamak plasma facing material (PFM) based on lithium capillary porous systems (CPS) are described in this paper.The recent progress in the development of limiters with different kinds of CPS is relevant for protection of tokamak PFCs from damage under normal operation, ELMs and disruptions. New PFM eliminates the lithium flux into plasma, its pollution and lithium accumulation.Here we present an overview of the design and the experimental tests of the liquid lithium limiters. These limiters are based on CPS with hard matrix from stainless steel mesh, molybdenum and tungsten. Different types of limiter have been taken into account: the horizontal and vertical rail type limiters with passive and active cooling for investigation the possibility to provide the closed lithium circulation in tokamak chamber; the ring CPS-based limiter for investigation of lithium behavior in limiter scrape-off layer (SOL).Here we also present the preliminary results of the application of the cryogenic techniques for lithium removal from the chamber wall after operation in hot plasma.
Keywords:Liquid lithium  Plasma facing material  Plasma facing component  Lithium technology
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