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D III-D divertor target heat flux measurements during ohmic and neutral beam heating

D.N. Hill, T. Petrie, M. Ali Mahdavi, L. Lao, W. Howl1988年被引用 34Nuclear FusionIF 3出版社

Time resolved power deposition profiles on the D III-D divertor target plates have been measured for Ohmic and neutral beam injection heated plasmas using fast response infrared thermography (τ ≤ 150 μs). Giant Edge Localized Modes have been observed which punctuate quiescent periods of good H-mode confinement and deposit more than 5% of the stored energy of the core plasma on the divertor armour tiles on millisecond timescales. The heat pulse associated with these events arrives approximately 0.5 ms earlier on the outer leg of the divertor relative to the inner leg. The measured power deposition profiles are displaced relative to the separatrix intercepts on the target plates, and the peak heat fluxes are a function of core plasma density.

日本語訳

DIII-Dダイバータ標的板上の電力堆積プロファイルは、高速応答赤外線サーモグラフィ(τ ≤ 150 μs)を用いて、オーミック加熱および中性粒子ビーム入射加熱プラズマに対して時間分解測定が行われた。巨視的エッジ局在モード(ELM)が観測され、これは良好なHモード閉じ込めの静穏期を断続的に中断し、コアプラズマの蓄積エネルギーの5%以上をミリ秒時間スケールでダイバータアーマータイル上に堆積させる。これらの事象に伴う熱パルスは、内側脚部と比較して外側脚部に約0.5 ms早く到達する。測定された電力堆積プロファイルは、標的板上のセパラトリックス交点に対して変位しており、ピーク熱流束はコアプラズマ密度の関数である。

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DivertorNeutral beamNeutral beam injectionOhmic heatingDivertor target
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