Overview of confinement and MHD stability in the Large Helical Device
Overview of confinement and MHD stability in the Large Helical Device
复制标题
大型螺旋装置中的约束和 MHD 稳定性概述
DOI：
10.1088/0029-5515/45/10/s21
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发表时间：
2005
期刊：
影响因子：
3.3
通讯作者：
Y. Yoshimura
中科院分区：
文献类型：
--
作者：
O. Motojima;K. Ida;K. Watanabe;Y. Nagayama;A. Komori;T. Morisaki;B. Peterson;Y. Takeiri;K. Ohkubo;K. Tanaka;T. Shimozuma;S. Inagaki;T. Kobuchi;S. Sakakibara;J. Miyazawa;H. Yamada;N. Ohyabu;K. Narihara;K. Nishimura;M. Yoshinuma;S. Morita;T. Akiyama;N. Ashikawa;C. Beidler;M. Emoto;T. Fujita;T. Fukuda;H. Funaba;P. Goncharov;M. Goto;T. Ido;K. Ikeda;A. Isayama;M. Isobe;H. Igami;K. Ishii;K. Itoh;O. Kaneko;K. Kawahata;H. Kawazome;S. Kubo;R. Kumazawa;S. Masuzaki;K. Matsuoka;T. Minami;S. Murakami;S. Muto;T. Mutoh;Y. Nakamura;H. Nakanishi;Y. Narushima;M. Nishiura;A. Nishizawa;N. Noda;T. Notake;H. Nozato;S. Ohdachi;Y. Oka;S. Okajima;M. Osakabe;T. Ozaki;A. Sagara;T. Saida;K. Saito;M. Sakamoto;R. Sakamoto;Y. Sakamoto;M. Sasao;K. Sato;M. Sato;T. Seki;M. Shoji;S. Sudo;N. Takeuchi;H. Takenaga;N. Tamura;K. Toi;T. Tokuzawa;Y. Torii;K. Tsumori;T. Uda;A. Wakasa;T. Watari;I. Yamada;S. Yamamoto;K. Yamazaki;M. Yokoyama;Y. Yoshimura
大螺旋装置是一种长径为3.5- 4.1m、短径为0.6m、环向磁场为0.5 ~ 3 T的L = 2、M = 10连续螺旋线圈的日光管装置，是稳态热核聚变反应堆环向磁约束系统的候选装置。通过功率为13 MW的中性束注入和功率为2 MW的电子回旋加热（ECH），在各种等离子体参数下扩展等离子体操作制度方面取得了重大进展。在无碰撞状态下，电子和离子温度达到10 keV，最大电子密度、体均β值和储存能量分别为2.4 × 1020 m−3、4.1%和1.3 MJ。在过去的两年中，磁流体动力学的稳定性提供访问的高β制度和愈合的磁岛相比，在托卡马克的新古典撕裂模式进行了深入的研究。局部岛偏滤器实验也已进行控制的边缘等离子体约束改善的目的。对于输运研究，对具有内部输运屏障和磁岛的等离子体进行了瞬态输运分析。高离子温度等离子体通过向等离子体中添加杂质来获得，以即使在非常低的密度下也保持离子的功率沉积相当高。通过注入72 kW的ECH功率，等离子体持续了756 s，没有严重的杂质或再循环问题。
The Large Helical Device is a heliotron device with L = 2 and M = 10 continuous helical coils with a major radius of 3.5–4.1 m, a minor radius of 0.6 m and a toroidal field of 0.5–3 T, which is a candidate among toroidal magnetic confinement systems for a steady state thermonuclear fusion reactor. There has been significant progress in extending the plasma operational regime in various plasma parameters by neutral beam injection with a power of 13 MW and electron cyclotron heating (ECH) with a power of 2 MW. The electron and ion temperatures have reached up to 10 keV in the collisionless regime, and the maximum electron density, the volume averaged beta value and stored energy are 2.4 × 1020 m−3, 4.1% and 1.3 MJ, respectively. In the last two years, intensive studies of the magnetohydrodynamics stability providing access to the high beta regime and of healing of the magnetic island in comparison with the neoclassical tearing mode in tokamaks have been conducted. Local island divertor experiments have also been performed to control the edge plasma aimed at confinement improvement. As for transport study, transient transport analysis was executed for a plasma with an internal transport barrier and a magnetic island. The high ion temperature plasma was obtained by adding impurities to the plasma to keep the power deposition to the ions reasonably high even at a very low density. By injecting 72 kW of ECH power, the plasma was sustained for 756 s without serious problems of impurities or recycling.
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影响因子：
3.3
作者：
Shimada, M.;Campbell, D. J.;Sipps, A. C. C.
通讯作者：
Sipps, A. C. C.
影响因子：
2.2
作者：
S. Sudo;N. Tamura;K. Khlopenkov;S. Muto;H. Funaba;I. Viniar;V. Sergeev;Kuninori Sato;K. Ida;K. Kawahata;A. Komori;K. Matsuoka;K. Narihara;S. Okamura;N. Ohyabu;K. Tanaka;O. Motojima
通讯作者：
S. Sudo;N. Tamura;K. Khlopenkov;S. Muto;H. Funaba;I. Viniar;V. Sergeev;Kuninori Sato;K. Ida;K. Kawahata;A. Komori;K. Matsuoka;K. Narihara;S. Okamura;N. Ohyabu;K. Tanaka;O. Motojima
DOI：
--
发表时间：
2004
期刊：
Fusion Science & Technology Vol.46・No.1
影响因子：
--
作者：
O.Motojima;H.Yamada;A.Komori;K.Y.Watanabe;et al.
通讯作者：
et al.
大型螺旋装置与JT-60U等离子体中电子内部传输势垒的比较
DOI：
--
发表时间：
2004
期刊：
Plasma Phys.Control.Fusion 46
影响因子：
--
作者：
K.Ida;et al.
通讯作者：
et al.
紧凑螺旋系统中的等离子体约束物理研究
DOI：
--
发表时间：
2006
期刊：
Journal of the Korean Physical Society 49
影响因子：
--
作者：
S.Okamura;et. al.
通讯作者：
et. al.