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High power heating results on JT-60

M Akiba, H Aikawa, N Akaoka, H Akasaka, N Akino, T Akiyama, T Ando, K Annoh, T Aoyagi, T Arai1988年Plasma Physics and Controlled FusionIF 2.2出版社

From June to October 1987, JT-60 achieved fusion product (ne(0). tau E*.Ti(0)) of 6*1019 m-3.keV.s with hydrogen plasma at plasma current of 2.8 to 3.1 MA with neutral beam power of approximately 20 MW. The central electron density of 1.3*1020 m-3 was obtained at plasma current of 3 MA with 13 approximately 20 MW neutral beam power and the confinement time reached 0.14-0.18 s. An offset linear scaling law like the Shimomura-Odajima scaling on confinement time will be able to reproduce experimental data better than that of the Goldston type scaling. With low beam energy injection approximately 40 keV, confinement degradation was found. Many short periods (0.05 approximately 0.1 s) of H-mode phase were found in outside X-point divertor discharges with NB or NB+RF(LH or IC) heating power above 16 MW. However, improvement in energy confinement time was limited to 10 %. The ballooning/interchange stability analyses were also made for the outside X-point divertor equilibrium in connection with H0-phase capability. Heating powers of 9.5 MW and 1.9 MW were obtained by LHRF, ICRF injection, respectively. In combined LHRF and NB heating, the incremental energy confinement time of 0.064 s was obtained, which is the same level of that of NB heating only. In combined NB and on-axis ICRF heating of low ne discharge, an incremental energy confinement time of 0.21 s was obtained, which is three times as long as those of NB or ICRF heating only. High energy beam ions were accelerated by ICRF in the central region of the plasma.

日本語訳

1987年6月から10月にかけて、JT-60は、プラズマ電流2.8〜3.1 MA、中性粒子ビーム出力約20 MWの水素プラズマにおいて、核融合積(ne(0)・τE・Ti(0))6×10¹⁹ m⁻³・keV・sを達成した。中心電子密度1.3×10²⁰ m⁻³は、プラズマ電流3 MA、中性粒子ビーム出力約20 MWで得られ、閉じ込め時間は0.14〜0.18 sに達した。閉じ込め時間に関するシオモダ・オジマ則のようなオフセット線形スケーリング則は、ゴールドストン型スケーリング則よりも実験データを良好に再現できることがわかった。低ビームエネルギー注入(約40 keV)では、閉じ込め劣化が観測された。外部X点ダイバータ放電において、NBまたはNB+RF(LHまたはIC)加熱出力16 MW以上で、Hモード位相の短い期間(0.05〜0.1 s)が多数観測された。しかしながら、エネルギー閉じ込め時間の改善は10%に限られた。また、外部X点ダイバータ平衡に対するバルーニング/交換安定性解析も、Hモード位相の可能性との関連で実施された。LHRFおよびICRF注入により、それぞれ9.5 MWおよび1.9 MWの加熱出力が得られた。LHRFとNBの複合加熱では、増分エネルギー閉じ込め時間0.064 sが得られ、これはNB単独加熱の場合と同程度であった。低密度放電におけるNBとオン軸ICRFの複合加熱では、増分エネルギー閉じ込め時間0.21 sが得られ、これはNBまたはICRF単独加熱の場合の3倍に相当した。高エネルギー・ビームイオンは、プラズマ中心領域においてICRFによって加速された。

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