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High power ICRF heating experiments on the JIPP T-IIU tokamak

Y. Ogawa, K. Masai, T. Watari, R. Akiyama, R. Ando, J. Fujita, Y. Hamada, S. Hirokura, K. Ida, K. Kadota1989年被引用 8Nuclear FusionIF 3出版社

In the JIPP T-IIU tokamak, a high power ICRF heating experiment has been conducted, up to an extremely high power density (∼2 MW·m−3), with a total RF power of PRF = 2 MW. Great attention has initially been paid to the problem of impurities, and it has been found that (a) the adoption of low Z materials for the limiter, (b) in situ carbon coating (i.e. carbonization) and (c) adequate gas puffing synchronized to the RF pulse are very effective in suppressing radiation loss. With these methods, a remarkable reduction in metal impurities (especially in iron impurity) has been achieved; the total radiation loss has been reduced to less than 30-40% of the input power. In these reduced radiation loss plasmas, the characteristics of ICRF heated plasmas have been studied intensively. With an increase in the ICRF heating power, a deterioration of the energy confinement time has been observed, indicating quantitative agreement with the Kaye-Goldston L-mode scaling. It is shown that the so-called profile consistency, which is the leading feature in neutral beam heated plasmas, also holds in ICRF heated plasma. It has been observed that the electron temperature profile only responds to the safety factor q(a) and does not change when the deposition profile is controlled by tailoring the k1 spectrum.

日本語訳

JIPP T-IIUトカマクにおいて、極めて高いパワー密度(∼2 MW·m−3)に達する高パワーICRF加熱実験が、全RFパワーPRF = 2 MWで実施された。当初、不純物の問題に大きな注意が払われ、(a)リミッタへの低Z材料の採用、(b)その場炭素被覆(すなわちカーボナイゼーション)、(c)RFパルスに同期した適切なガスパフが、放射損失の抑制に非常に効果的であることが見出された。これらの方法により、金属不純物(特に鉄不純物)の顕著な低減が達成された。全放射損失は入力パワーの30〜40%未満に低減された。これらの放射損失低減プラズマにおいて、ICRF加熱プラズマの特性が集中的に研究された。ICRF加熱パワーの増加に伴い、エネルギー閉じ込め時間の劣化が観測され、Kaye-Goldston Lモードスケーリングと定量的に一致することが示された。いわゆるプロファイル一貫性は、中性粒子ビーム加熱プラズマにおける主要な特徴であるが、ICRF加熱プラズマでも成り立つことが示された。電子温度プロファイルは、安全係数q(a)にのみ応答し、k1スペクトルを調整して堆積プロファイルを制御しても変化しないことが観測された。

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