プラズマ・核融合学会誌
Print ISSN : 0918-7928
79 巻, 4 号
選択された号の論文の17件中1~17を表示しています
Rapid Communications
解説
  • 鈴木 敬三
    2003 年 79 巻 4 号 p. 326-335
    発行日: 2003年
    公開日: 2005/09/28
    ジャーナル フリー
    Comparison of luminosity-modulation switching principles in matrix displays showed that an AC-PDP (alternating-current plasma display panel) can produce 30 to 50-inch diagonal displays of superior motionpicture quality and of a low price. Comparison with a process plasma and a thermonuclear fusion plasma showed that an AC-PDP plasma in each cell has extremely low degrees of ionization, uniformity, and steadiness. The mechanism of VUV (vacuum ultraviolet) production in an AC-PDP was theoretically studied, and ways to increase VUV production efficiency were discussed. It was then shown that the development of a vertical discharge AC-PDP of low driving voltage is expected and that precise and dynamic control and measurement of the non-uniform and non-steady discharge-radiation process will become even more important in the future development of new AC-PDP technologies.
  • 高瀬 雄一
    2003 年 79 巻 4 号 p. 336-344
    発行日: 2003年
    公開日: 2005/09/28
    ジャーナル フリー
    Research on spherical tokamak (ST) plasmas is progressing rapidly. Recent results from the mega-ampere class ST devices, MAST and NSTX, are herein reviewed. A toroidal beta of up to 35% and a normalized beta of over 6 were achieved on NSTX. The highest betas are obtained with low internal inductance and a flat pressure profile, exceeding the no-wall stability limit by up to20%. Diamagnetic plasmas with a noninductive current fraction of 60% and a self-driven current fraction of 40% have been obtained. Ion thermal diffusivity is consistent with neoclassical transport, where as electron thermal diffusivity is anomalous. A strong toroidal flow (20-30% of Alfven velocity) is observed. H-mode is routinely observed in both MAST and NSTX. Energy confinement is consistent with the ITER 98y2 ELMy H-mode scaling, but the H-mode transition threshold power is about 50% higher than the ITER scaling. The divertor heat load is highly asymmetric, the outboard side being higher than the inboard side, typically by an order of magnitude. Up to 0.5 MA of plasma current has been obtained using the merging-compression technique, and further increase was demonstrated by ramping up the vertical field on MAST. Up to 0.4 MA of toroidal current has been obtained by coaxial helicity injection on NSTX. Noninductive current drive techniques using the neutral beam, high harmonic fast wave, and electron Bernstein wave are being developed.
小特集 「高分解能プラズマX線計測の最前線」
講座 「プラズマ利用ミリ波・サブミリ波帯パルス電磁波放射入門」
研究論文
  • Satoshi ITOH, Eriko JOTAKI, Kazuo NAKAMURA, Mizuki SAKAMOTO, Kazuaki H ...
    2003 年 79 巻 4 号 p. 413-419
    発行日: 2003年
    公開日: 2005/09/28
    ジャーナル フリー
    The operation of tokamak devices is based on the principle of the transformer, so it has been considered that pulse operation of such devices is inevitable. But the superconducting high-field tokamak TRIAM-1M has been demonstrated continuous operation for last 15 years and succeeded in sustaining 3 hours of constant operation in 2001. Fusion reactors of the future will use the center solenoid (CS) coil only in the ramp-up phase of the plasma current. If the coil is removed from the tokamak device, the device can be simplified and its cost will be decreased. In TRIAM-1M experiments, a perfect CS-free ramp-up was demonstrated and succeeded in sustaining the plasma current longer than 30 s. In this paper, the operation scenario, especially plasma position control, and the results of the analysis of plasma control are described.
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