日本原子能机构大功率回旋管研制进展

K. Sakamoto, A. Kasugai, K. Kajiwara, K. Takahashi, N. Kobayashi, Y. Oda
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引用次数: 7

摘要

国际热核实验反应堆(ITER)的电子回旋加速器加热和电流驱动(EC H&CD)系统需要1 MW 170 GHz长脉冲回旋管作为电源。在日本原子能机构(JAEA)的ITER回旋加速器开发过程中,在微波相关脉冲持续时间(800 s)下实现了1mw 170 GHz的稳定振荡,这是ITER等离子体燃烧时间的两倍。通过对振荡过程中硬自激区振荡参数的精确优化,采用降压集热器的效率可达55%。功率平衡是用量热法测量的,即从窗口输出功率为1020 kW,到集热器的功率沉积为742 kW,从减压窗输出的杂散辐射为24 kW。进入回旋管内部元件的总欧姆损耗功率为63千瓦。空腔处的功耗符合设计值。在长脉冲模式下获得的最大效率为~60%。回旋管自2006年3月开始工作,无大故障,输出能量约150gj。实验结果满足ITER的要求。由于ITER等离子体中心的最大环面场为5.3 T,预计频率为170 GHz,因此估计回旋管在低环面场下的频率可调性是有用的。仿真结果表明,在te27,6模式下的~137 GHz振荡与170 GHz/ te31,8模式振荡具有相似的性能。两种模式都能穿透厚度为1.853 mm的金刚石窗。三极管磁控管注射枪(MIG)在两种工作参数下都能产生低速发散的旋转电子束。为了实现对聚变等离子体的快速频率控制,研制了一种带超导扫线线圈的无氦磁体。室温孔径为240mm,中心为7t。使用市售的标准直流电源,在7 T时以0.4 T/10秒的速度进行了磁场扫描。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Progress of high power gyrotron development in JAEA
A 1 MW 170 GHz long pulse gyrotron is required for a power source of the electron cyclotron heating and current drive (EC H&CD) system on ITER (International Thermonuclear Experimental Reactor). In the ITER gyrotron development of JAEA (Japan Atomic Energy Agency), a stable 1 MW 170 GHz oscillation has been achieved at CW-relevant pulse duration (800 s), which is a twice of burning time of ITER plasma. The efficiency was 55% with the depressed collector with the precise optimization of the oscillation parameters in the hard self-excitation region during the oscillation. The power balance is measured calorimetrically, i.e., output power from the window is 1020 kW, power deposition to the collector is 742 kW, and a stray radiation output from the relief windows is 24 kW. Total ohmic-loss power into the inner components of the gyrotron is 63 kW. The power dissipation at the cavity agreed with the design value. The attained maximum efficiency in the long pulse mode is ~60%. The gyrotron has been working since March 2006 without major trouble, and records ~150 GJ of the output energy. The results satisfy the ITER requirement. As the frequency of 170 GHz is expected for the maximum toroidal field of 5.3 T at the plasma center of ITER, it is useful to estimate a frequency tunability of the gyrotron for the operation at lower toroidal filed. A simulation indicates that a similar performance is obtained at ~137 GHz oscillation at TE27,6 mode with the 170 GHz/TE31,8 mode oscillation. Both modes penetrate the diamond window of 1.853 mm in thickness. The triode magnetron injection gun (MIG) generates the rotational electron beam of low velocity divergence for both operation parameters. As for a fast frequency control, which will be useful for profile control in the fusion plasma, a He-free magnet with an additional super conducting sweeping coil was developed. A diameter of a room temperature bore is 240 mm, and the 7 T at the center. Using a commercially available standard DC power supplies, the magnetic field sweeping was demonstrated with a speed of 0.4 T/10 sec at 7 T.
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