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Engineering aspects of the fusion engineering test facility based on mirror confinement (FEF)

Y. Kohzaki, T. Kawabe, K. Yoshikawa, R. Kumawzawa, T. Watanabe1989年Fusion Engineering and DesignIF 1.7出版社

AbstractAn engineering feasibility study on the mirror-based fusion plasma neutron source as a fusion engineering test facility (FEF) has been carried out. The engineering issues and conditions to meet the requirement are presented.The radius and length of the plasma are about 10 cm and about 4 m, respectively. The wall loading of 14 MeV neutrons is about 1–2 MW/m2, and the required electric power is about 100–150 MW.The critical issues are as follows: (i) the heat lead to the first wall of the central cell and plug cell, which depends strongly on charge exchange neutrals. Methods to reduce the charge exchange in the plug cell are discussed. (ii) The blistering on the Faraday shield and the guard limiter of the ICRF antenna due to the bombardment of the alpha particles is the second critical issue. Some optimization has been considered.

日本語訳

ミラーベースの核融合プラズマ中性子源を核融合工学試験施設(FEF)として用いるための工学的実現可能性調査が実施された。要求を満たすための工学的課題と条件が提示されている。プラズマの半径は約10 cm、長さは約4 mである。14 MeV中性子の壁負荷は約1~2 MW/m²であり、必要とされる電力は約100~150 MWである。重要な課題は以下の通りである:(i) 中央セルおよびプラグセルの第一壁への熱負荷は、電荷交換中性子に強く依存する。プラグセルにおける電荷交換を低減する方法が議論されている。(ii) ICRFアンテナのファラデーシールドおよびガードリミッタの、アルファ粒子の衝撃によるブリスターリングが2番目の重要な課題である。いくつかの最適化が検討されている。

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