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Contour analysis of fusion reactor plasma performance

W.A. Houlberg, S.E. Attenberger, L.M. Hively1982年被引用 88Nuclear FusionIF 3出版社

A method of analysing plasma performance over large regions of density and temperature space with time-dependent multi-dimensional transport codes is presented. Contour plots of global steady-state plasma parameters are generated and then used to show: the relationships between driven and ignited operation; regions of thermal stability; the effects of the shift of the magnetic axis with increasing beta on beam penetration and thermal conduction losses from toroidal field ripple; and optimal neutral beam heating during start-up in tokamak reactor applications.

日本語訳

大域的定常プラズマパラメータの等高線プロットを生成し、それを用いて以下のことを示す、時間依存多次元輸送コードによる密度・温度空間の大領域にわたるプラズマ性能解析法を提示する。すなわち、駆動運転と点火運転の関係、熱的安定性の領域、ベータ値の増大に伴う磁気軸のシフトがビーム侵入及びトロイダル磁場リップルによる熱伝導損失に及ぼす影響、そしてトカマク炉応用における立ち上げ時の最適な中性粒子ビーム加熱である。

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