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

Heat loads on plasma facing components during disruptions on JET

G. Arnoux, A. Loarte, V. Riccardo, W. Fundamenski, A. Huber, JET-EFDA contributors2009年被引用 34Nuclear FusionIF 3出版社

For the first time, fast measurements of heat loads on the main chamber plasma facing components (about 1 ms time resolution) during disruptions are taken on JET. The timescale of energy deposition during the thermal quench is estimated and compared with the timescale of the core plasma collapse measured with soft x-ray diagnostic. The energy deposition time is 3–8 times longer than the plasma energy collapse during density limit disruptions or radiative limit disruptions. This factor is rather in the range 1.5–4 for vertical displacement events. The heat load profiles measured during the thermal quench show substantial broadening of the power footprint on the upper dump plate. The scrape-off layer power width is increased by a factor of 3 for the density limit disruptions. The far scrape-off layer is characterized by a steeper gradient which could be explained by shadowing of the dump plate by other main chamber plasma facing components such as the outer limiter.

日本語訳

JETにおいて、ディスラプション中の主チャンバー・プラズマ対向機器への熱負荷の高速計測(約1 msの時間分解能)が初めて実施された。熱クエンチ中のエネルギー堆積の時間スケールを推定し、軟X線計測で測定されたコアプラズマ崩壊の時間スケールと比較した。エネルギー堆積時間は、密度限界ディスラプションまたは放射限界ディスラプション中は、プラズマエネルギー崩壊よりも3~8倍長い。この係数は、垂直変位事象ではむしろ1.5~4の範囲である。熱クエンチ中に測定された熱負荷分布は、上部ダンププレート上のパワーフットプリントの大幅な広がりを示している。スクレイプオフ層のパワー幅は、密度限界ディスラプションでは3倍に増加する。遠方スクレイプオフ層はより急峻な勾配によって特徴づけられ、これは外側リミッターなどの他の主チャンバー・プラズマ対向機器によるダンププレートの遮蔽(シャドーイング)によって説明できる可能性がある。

装置

jet高精度(タイトル一致)

wiki

JETPlasma disruptionPlasma-facing componentHeat load
この論文にはまだAI要約がありません。

関連論文

Timescale and magnitude of plasma thermal energy loss before and during disruptions in JET

2005Nuclear Fusion

Application of powerful quasi-steady-state plasma accelerators for simulation of ITER transient heat loads on divertor surfaces

2007Plasma Physics and Controlled Fusion

Scaling of energy confinement with minor radius, current and density in Doublet III Ohmically heated plasmas

1982Nuclear Fusion

JET results and the prospects for fusion

1989Fusion Engineering and Design

Response of plasma-facing materials to high transient heat loads in a tokamak

1998Fusion Engineering and Design

Disruption heat loads on the JET MkIIGB divertor

2002Plasma Physics and Controlled Fusion

Ignition and reactor application of deuterium based fuel cycles in field reversed configurations

1989Nuclear Fusion

Heating of a large CTR-tokamak by neutral-beam injection

1974Nuclear Fusion

Heat pulse analysis in JET limiter and X-point plasmas

1990Nuclear Fusion

Influence of a magnetic field on plasma energy transfer to material surfaces in edge-localized mode simulation experiments with QSPA-M

2019Nuclear Fusion