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Poloidal flux linkage requirements for the International Thermonuclear Experimental Reactor

S.C. Jardin, C.E. Kessel, N. Pomphrey1994年被引用 20Nuclear FusionIF 3出版社

Two computational models have been applied to calculate the poloidal flux linkage requirements for the current ramp-up and for the flat-top phase of the proposed International Thermonuclear Experimental Reactor (ITER). For the current ramp-up phase, the TSC code has been used to simulate the entire current ramp-up period as described in the TAC-3 Report. The time of the simulation has been extended to cover the full current penetration time, that is, until the loop voltage is a constant throughout the plasma. Sensitivity studies have been performed with respect to current ramp-up time, impurity concentration and to the time of onset of auxiliary heating. A steady state plasma equilibrium code has been used that has the constant loop voltage constraint built in to survey the dependence of the steady state loop voltage on the density and temperature profiles. This calculation takes into account the plasma bootstrap current contribution, including non-circular and collisional corrections. The results can be displayed as contours of the loop voltage on a POPCON-like diagram

日本語訳

2つの計算モデルが、提案された国際熱核融合実験炉(ITER)の電流立ち上げ時およびフラットトップ相におけるポロイダル磁束鎖交要件を計算するために適用されてきた。電流立ち上げ相については、TSCコードを用いて、TAC-3レポートに記載されている電流立ち上げ期間全体をシミュレートしてきた。シミュレーションの時間は、完全な電流浸透時間をカバーするように延長された。すなわち、ループ電圧がプラズマ全体で一定になるまでである。感度研究は、電流立ち上げ時間、不純物濃度、および補助加熱の開始時間に関して実施された。定常ループ電圧の密度および温度分布への依存性を調査するために、一定ループ電圧制約が組み込まれた定常状態プラズマ平衡コードが使用された。この計算は、非円形および衝突補正を含むプラズマのブートストラップ電流の寄与を考慮している。結果は、POPCON類似図上にループ電圧の等高線として表示できる。

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