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Ion cyclotron range of frequencies heating and high-energy particle production in the Large Helical Device

T. Mutoh, R. Kumazawa, T. Seki, K. Saito, T. Watari, Y. Torii, N. Takeuchi, T. Yamamoto, F. Shimpo, G. Nomura2003年被引用 25Nuclear FusionIF 3出版社

Significant progress has been made with ion cyclotron range of frequencies (ICRF) heating in the Large Helical Device. This is mainly due to better confinement of the helically trapped particles and less accumulation of impurities in the region of the plasma core. During the past two years, ICRF heating power has been increased from 1.35 to 2.7 MW. Various wave-mode tests were carried out using minority-ion heating, second-harmonic heating, slow-wave heating and high-density fast-wave heating at the fundamental cyclotron frequency. This fundamental heating mode extended the plasma density range of effective ICRF heating to a value of 1×1020 m−3. This use of the heating mode was its first successful application in large fusion devices. Using the minority-ion mode gave the best performance, and the stored energy reached 240 kJ using ICRF alone. This was obtained for the inward-shifted magnetic axis configuration. The improvement associated with the axis-shift was common for both bulk plasma and highly accelerated particles. For the minority-ion mode, high-energy ions up to 500 keV were observed by concentrating the heating power near the plasma axis. The confinement properties of high-energy particles were studied for different magnetic axis configurations, using the power-modulation technique. It confirmed that with the inward-shifted configuration the confinement of high-energy particles was better than with the normal configuration. By increasing the distance of the plasma to the vessel wall to about 2 cm, the impurity influx was sufficiently reduced to allow sustainment of the plasma with ICRF heating alone for more than 2 min.

日本語訳

大型ヘリカル装置におけるイオンサイクロトロン周波数帯(ICRF)加熱に関して、顕著な進展が達成された。これは主に、ヘリカル閉じ込め粒子の閉じ込め改善と、プラズマコア領域における不純物蓄積の低減によるものである。過去2年間で、ICRF加熱パワーは1.35 MWから2.7 MWへと増大した。様々な波動モードの試験が、 minority-ion加熱、second-harmonic加熱、slow-wave加熱、およびfundamentalサイクロトロン周波数におけるhigh-density fast-wave加熱を用いて実施された。このfundamental加熱モードにより、効果的なICRF加熱が可能なプラズマ密度範囲は1×10²⁰ m⁻³まで拡大された。この加熱モードの使用は、大型核融合装置における初めての成功例となった。minority-ionモードを用いた場合に最も優れた性能が得られ、ICRFのみで蓄積エネルギーは240 kJに達した。これは、内側シフト磁気軸配位において達成された。軸シフトに伴う改善は、バルクプラズマと高エネルギー粒子の両方において共通して観測された。minority-ionモードでは、加熱パワーをプラズマ軸近傍に集中させることにより、500 keVまでの高エネルギーイオンが観測された。異なる磁気軸配位における高エネルギー粒子の閉じ込め特性が、パワー変調法を用いて研究された。その結果、内側シフト配位では、通常配位と比較して高エネルギー粒子の閉じ込めが優れていることが確認された。プラズマと真空容器壁との距離を約2 cm増大させることにより、不純物流入が十分に低減され、ICRF加熱のみで2分以上のプラズマ維持が可能となった。

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Ion cyclotron heatingHelical device
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