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Direct ion orbit loss near the plasma edge of a divertor tokamak in the presence of a radial electric field

K. Miyamoto1996年被引用 47Nuclear FusionIF 3出版社

The loss region in the initial velocity space of the direct orbit loss ions near the plasma edge of tokamaks with the divertor configuration is studied analytically. The results of this analysis are compared with the numerical results of the loss region in the JET case obtained by Chankin and McCracken (1993). The results agree with each other semiquantitatively in several cases involving the presence of a radial electric field. A measure of the direct ion orbit loss Gamma is calculated from the given loss region in the initial velocity space for JET, JT-60U and ITER. When the initial position of an ion is located in the outside torus (r>Rx, where Rx is the radius at the null X point), the dependence of Gamma on the radial electric field shows the existence of a local maximum and a local minimum in the negative region of the radial electric field

日本語訳

ダイバータ配位を有するトカマクのプラズマ端近傍における直接軌道損失イオンの初期速度空間における損失領域を解析的に研究した。この解析の結果を、ChankinとMcCracken(1993)によって得られたJETの場合の損失領域の数値結果と比較した。両者は、動径電場の存在を含むいくつかの場合において定性的に一致する。直接イオン軌道損失の指標であるGammaは、与えられた初期速度空間の損失領域からJET、JT-60U、ITERについて計算される。イオンの初期位置が外側トーラス(r>Rx、ここでRxはヌルX点における半径)に位置する場合、動径電場に対するGammaの依存性は、動径電場の負の領域において極大値と極小値の存在を示す。

装置

iter中精度(概要文一致)jet中精度(概要文一致)

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DivertorRadial electric field
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