Assessment of feasibility of helium ash exhaust and heat removal by pumped-limiter in tokamak fusion reactor.
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概要
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A detailed calculation of the behavior of fuel and He particles in tokamak reactor with pumped-limiter is performed by one-dimensional tokamak transport code. Energy of neutral particles flowing back from limiter chamber is calculated by two-dimensional Monte Carlo neutral code. Feasibility of He ash exhaust and heat removal by the pumped-limiter are analyzed. Following features of the pumped-limiter are clarified : <BR>(1) Electron temperature decays rapidly in radial direction in scrape-off layer, while density profile is broader than that of temperature. <BR>(2) Helium accumulation in main plasma can be kept at desired level by rather short limiter and moderate pumping system. <BR>(3) Minimum amount of tritium pumped out little depends on limiter length. <BR>(4) Although high temperature plasma in scrape-off layer could be realized by large pumping and ideal pellet injection, it is not sufficiently high to reduce the erosion of the limiter surface and the leading edge. <BR>In conclusion, He ash exhaust may be possible by the pumped-limiter, while the heat load and erosion will be so high that the pumped-limiter may not be applicable unless the boundary plasma is cooled by radiation or by some other means.
- 一般社団法人 日本原子力学会の論文
著者
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Sugihara Masayoshi
Division Of Large Tokamak Development Japan Atomic Energy Research Institute
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SAITO Seiji
Division of Large Tokamak Development, Japan Atomic Energy Research Institute
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SAITO Seiji
Division of Large Tokamak Development,Japan Atomic Energy Research Institute
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FUJISAWA Noboru
Division of Large Tokamak Development,Japan Atomic Energy Research Institute
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HITOKI Shigehisa
Division of Large Tokamak Development,Japan Atomic Energy Research Institute
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