FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Characterization of disruption mitigation via massive gas injection on MAST

A J Thornton, K J Gibson, J R Harrison, M Lehnen, R Martin, A Kirk, the MAST Team2012年Plasma Physics and Controlled FusionIF 2.2出版社

Disruptions are of significant concern to future devices, due to the large amount of energy released during the rapid quenching of the plasma. Disruption mitigation has been performed on MAST, to study the effect on heat loads and disruption time scales in a spherical tokamak. Massive gas injection is performed using a disruption mitigation valve capable of injecting between 0.6 and 1.5 × 1022 particles, corresponding to 10–150 times the plasma inventory. Noble gases are used for mitigation studies, specifically helium, argon, neon and a mixture of 10% argon and helium. The effect of mitigation is studied using a comparison between mitigated discharges and reference unmitigated disruptions.Mitigation has been seen to be effective at reducing peak divertor power loads, with reductions of up to 60% in the divertor power load being observed. The decrease in divertor power load is reflected by an increase in radiated power, mainly as a result of line radiation from the injected impurities. The largest reduction in the divertor power loads are seen for the impurities with Z > 4. The energy load to the divertor has been reduced by between 30–40% of the total stored plasma energy in ohmic, L mode and H mode discharges. Mitigation also affects the current quench times, accelerating the quench of the plasma with increasing injection quantity, with saturation observed at the highest injected quantities.

日本語訳

ディスラプションは、プラズマの急速なクエンチ中に放出される大量のエネルギーにより、将来の装置にとって重大な懸念事項である。MASTにおいてディスラプション緩和が実施され、球状トカマクにおける熱負荷とディスラプション時間スケールへの影響が調べられた。大量ガス入射は、プラズマ蓄積量の10〜150倍に相当する0.6〜1.5×10²²個の粒子を注入可能なディスラプション緩和弁を用いて実施される。緩和研究には希ガスが使用され、具体的にはヘリウム、アルゴン、ネオン、および10%アルゴンとヘリウムの混合ガスが用いられる。緩和の効果は、緩和を施した放電と参照となる未緩和ディスラプションとの比較を用いて研究される。緩和はピークダイバータ熱負荷の低減に効果的であることが確認されており、ダイバータ熱負荷において最大60%の低減が観測されている。ダイバータ熱負荷の減少は、主として注入された不純物からの線放射の結果としての放射パワーの増加に反映される。ダイバータ熱負荷の最大の低減は、Z > 4の不純物において見られる。ダイバータへのエネルギー負荷は、オーミック放電、Lモード放電、Hモード放電において、プラズマ蓄積エネルギーの30〜40%の範囲で低減されている。緩和はまた電流クエンチ時間にも影響を及ぼし、注入量の増加に伴ってプラズマのクエンチが加速され、最も高い注入量では飽和が観測される。

装置

mast高精度(タイトル一致)

wiki

Plasma disruptionMASTDisruption mitigationMassive gas injection
この論文にはまだAI要約がありません。

関連論文

Disruption mitigation with high-pressure helium gas injection on EAST tokamak

2018Nuclear Fusion

Disruption mitigation by massive gas injection in JET

2011Nuclear Fusion

Disruption mitigation by injection of small quantities of noble gas in ASDEX Upgrade

2017Plasma Physics and Controlled Fusion

Gas jet disruption mitigation studies on Alcator C-Mod and DIII-D

2007Nuclear Fusion

Experimental study of disruption mitigation using massive injection of noble gases on Tore Supra

2010Nuclear Fusion

Real-time data-driven disruption prediction and its mitigation of MA-plasma experiments in KSTAR with a lower carbon divertor

2025Nuclear Fusion

Assimilation of impurities during massive gas injection in ASDEX Upgrade

2015Nuclear Fusion

Shattered pellet injection experiments at JET in support of the ITER disruption mitigation system design

2022Nuclear Fusion

Mitigation of disruptions by fast helium gas puffs

2001Nuclear Fusion

Disruption runaway electron generation and mitigation in the Spherical Tokamak for Energy Production (STEP)

2024Nuclear Fusion