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Influence of the shape and magnitude of the discharge current pulse on plasma containment and heating in Tokamak-3

S.V. Mirnov1969年被引用 39Nuclear FusionIF 3出版社

The author systematizes the results of measurements of plasma energy and energy replacement time as a function of the shape and magnitude of the discharge current pulse. It has already been established that the maximum transverse energies E⊥ and energy replacement times τE in Tokamak-3 are reached 2-3 ms after the peak of the discharge current I. I n this paper, the author shows how E⊥(t) and τE(t) depend on the shape of the discharge current pulse and the duration of the discharge. An attempt is made to connect the observed relationships with the current density distribution. The internal (ℓi) and external (Lext = 2 ln(b/a)) self-inductance coefficients of the plasma column are measured and, on the basis of the results, an estimate is obtained of the shear averaged over the radius a. Hypotheses are advanced regarding the nature of the processes which determine the observed patterns of behaviour. One possible explanation is the presence of either dissipative helical instability (tearing mode) or overheat instability in the initial stage of the discharge and during the current rise.

日本語訳

著者は、放電電流パルスの形状と大きさの関数としてのプラズマエネルギーおよびエネルギー置換時間の測定結果を体系化する。トカマク3において、最大の横方向エネルギーE⊥およびエネルギー置換時間τEが、放電電流Iのピーク後2〜3msに達することはすでに確立されている。本論文では、著者はE⊥(t)およびτE(t)が放電電流パルスの形状と放電時間にどのように依存するかを示す。観測された関係を電流密度分布と結び付ける試みがなされる。プラズマ柱の内部自己インダクタンス係数(ℓi)および外部自己インダクタンス係数(Lext = 2 ln(b/a))が測定され、その結果に基づいて、半径aにわたって平均されたシアの推定値が得られる。観測された挙動パターンを決定する過程の性質に関する仮説が提示される。一つの可能な説明は、放電の初期段階および電流上昇中における、散逸性らせん不安定性(ティアリングモード)または過熱不安定性の存在である。

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