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Progress in the ITER physics basis, 4; Power and particle control

ITER物理基盤の進展,4; 熱・粒子制御

Loarte, A.*; Lipschultz, B.*; Kukushkin, A. S.*; Matthews, G. F.*; Stangeby, P. C.*; 朝倉 伸幸; Counsell, G. F.*; Federici, G.*; Kallenbach, A.*; Krieger, K.*; Mahdavi, A.*; Philipps, V.*; Reiter, D.*; Roth, J.*; Strachan, J.*; Whyte, D.*; Doerner, R.*; Eich, T.*; Fundamenski, W.*; Herrmann, A.*; Fenstermacher, M.*; Ghendrih, P.*; Groth, M.*; Kirschner, A.*; 木島 滋; LaBombard, B.*; Lang, P.*; Leonard, A. W.*; Monier-Garbet, P.*; Neu, R.*; Pacher, H.*; Pegourie, B.*; Pitts, R. A.*; 高村 秀一*; Terry, J.*; Tsitrone, E.*; ITPA Scrape-off Layer and Divertor Physics Topical Group*

Loarte, A.*; Lipschultz, B.*; Kukushkin, A. S.*; Matthews, G. F.*; Stangeby, P. C.*; Asakura, Nobuyuki; Counsell, G. F.*; Federici, G.*; Kallenbach, A.*; Krieger, K.*; Mahdavi, A.*; Philipps, V.*; Reiter, D.*; Roth, J.*; Strachan, J.*; Whyte, D.*; Doerner, R.*; Eich, T.*; Fundamenski, W.*; Herrmann, A.*; Fenstermacher, M.*; Ghendrih, P.*; Groth, M.*; Kirschner, A.*; Konoshima, Shigeru; LaBombard, B.*; Lang, P.*; Leonard, A. W.*; Monier-Garbet, P.*; Neu, R.*; Pacher, H.*; Pegourie, B.*; Pitts, R. A.*; Takamura, Shuichi*; Terry, J.*; Tsitrone, E.*; ITPA Scrape-off Layer and Divertor Physics Topical Group*

1999年にNuclear Fusion誌に出版されたITER物理基盤以来、ITERの設計及び運転に必要な周辺プラズマ及びプラズマ相互作用における現在のトカマク装置の研究成果がまとめられた。大きく進展した実験分野として、境界層及びダイバータにおける熱・粒子輸送,第一壁と周辺プラズマとの相互作用,ELM熱流の輸送と壁相互作用,非接触プラズマと中性粒子の輸送,高Z及び低Z材料の損耗と輸送及び堆積,トリチウムの対向材への吸着とその除去方法等が挙げられる。これらの進展と同時に、周辺プラズマ及びプラズマ材料相互作用のモデリングも大きく進展した。現状のデータをもとにITERにおいて期待されるダイバータ性能や対向材料の寿命などについて議論した。

Progress, since the ITER Physics Basis publication (1999), in understanding the processes that will determine the properties of the plasma edge and its interaction with material elements in ITER is described. Significant progress in experiment area: energy and particle transport, the interaction of plasmas with the main chamber material elements, ELM energy deposition on material elements and the transport mechanism, the physics of plasma detachment and neutral dynamics, the erosion of low and high Z materials, their transport to the core plasma and their migration at the plasma edge, retention of tritium in fusion devices and removal methods. This progress has been accompanied by the development of modelling tools for the physical processes at the edge plasma and plasma-materials interaction. The implications for the expected performance in ITER and the lifetime of the plasma facing materials are discussed.

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パーセンタイル:5.26

分野:Physics, Fluids & Plasmas

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