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Reconnection heating experiments and simulations for torus plasma merging start-up

Y. Ono, S. Inoue, H. Tanabe, C.Z. Cheng, H. Hara, R. Horiuchi2019年被引用 15Nuclear FusionIF 3出版社

A series of merging experiments, TS-3 (TS-3U), TS-4, MAST and ST-40, made clear the promising characteristics of reconnection heating during merging formation of a high-beta spherical tokamak (ST), spheromak and field-reversed configuration (FRC). We developed the MW-class (<30 MW in TS-3U) ion heating using magnetic reconnection of torus plasma merging. Both the merging experiments and particle-in-cell (PIC) simulations (and also partly solar observation) agree on, (i) ion heating of the reconnection in its downstream, (ii) negative potential formation in the downstream for accelerating ions and (iii) low dependence of ion heating on the guide (toroidal) field Bg. An important finding is that the reconnection heating energy depends on the reconnecting magnetic field Brec but has little dependence on Bg in the tokamak operation region with the safety factor at the magnetic axis q0  >  2. The plasmoid/current sheet ejection promotes ion heating in the high-q region, weakening the Bg dependence of ion heating. Since the reconnection accelerated ions up to 70% of the Alfven speed of Brec, the ion temperature Ti increment (and the reconnection heating energy) scales with Brec squared under the constant plasma density. This promising reconnection heating does not depend on plasma size, as long as the reconnection time is shorter than the plasma confinement time. This scaling law extended over 1.2 keV suggests that the merging start-up may realize the burning plasma temperature Ti  >  10 keV by increasing Brec. The merging/reconnection heating can explore a new direct route to burning plasma regimes without using any additional heating, such as neutral beam injection (NBI). This scaling leads us to new reconnection heating experiments for direct access to burning plasma regimes: ST-40 at Tokamak Energy and TS-3U at the University of Tokyo.

日本語訳

一連の合体実験であるTS-3(TS-3U)、TS-4、MAST、ST-40により、高ベータ球状トカマク(ST)、スフェロマック、逆転磁場配位(FRC)の合体形成時におけるリコネクション加熱の有望な特性が明らかになった。我々は、トーラスプラズマ合体を用いた磁気リコネクションによるMW級(TS-3Uでは30MW未満)のイオン加熱を開発した。合体実験と粒子セル(PIC)シミュレーション(および一部の太陽観測)は、以下の点で一致している:(i)下流領域におけるリコネクションのイオン加熱、(ii)下流領域におけるイオン加速のための負の電位形成、(iii)ガイド(トロイダル)磁場Bgに対するイオン加熱の低依存性。重要な発見は、安全係数が磁気軸上でq0 > 2であるトカマク運転領域において、リコネクション加熱エネルギーがリコネクション磁場Brecに依存するが、Bgにはほとんど依存しないことである。プラズモイド/電流シート放出は高q領域でのイオン加熱を促進し、Bg依存性を弱める。リコネクションによりイオンはBrecのアルフヴェン速度の70%まで加速されるため、イオン温度増分Ti(およびリコネクション加熱エネルギー)は、一定のプラズマ密度の下でBrecの2乗に比例する。この有望なリコネクション加熱は、リコネクション時間がプラズマ閉じ込め時間より短い限り、プラズマサイズに依存しない。このスケーリング則は1.2keVを超えて拡張され、Brecを増加させることで合体開始法が燃焼プラズマ温度Ti > 10keVを実現し得ることを示唆している。合体/リコネクション加熱は、中性粒子ビーム入射(NBI)などの追加加熱を用いずに燃焼プラズマ領域へ直接到達する新たな経路を切り開く可能性がある。このスケーリング則は、Tokamak Energy社のST-40および東京大学のTS-3Uにおける、燃焼プラズマ領域への直接到達を目指した新たなリコネクション加熱実験へと導く。

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