JT-60 operation results after its modification for higher plasma current with single null open divertor

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI:10.1109/FUSION.1991.218923

I. Kondo, H. Horiike, Y. Neyatani, M. Matsukawa, T. Ando, R. Yoshino, T. Arai, H. Ninomiya, M. Yamamoto, T. Koike, K. Kodama, K. Miyachi, M. Honda, H. Hiratsuka

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引用次数: 2

Abstract

The hardware performance of the JT-60U (JAERI Tokamak-60 Upgrade) tokamak machine was investigated in several aspects. The experimental operation has advanced to record D-D fusion power as high as 17 kW. The displacement of the toroidal field coil was measured, and the effect of reinforcement was confirmed. The dynamic displacement of the vessel was found to be a vibration with amplitude within 0.3 mm and relatively slow dumping. Regarding the first wall, the divertor suffered from the heat flow with the width of 4 to 5 cm that was close to the design value. The divertor armor was found to rise 500 degrees C at most for the neutral-beam heating of 20 MW for 2 s, and it is still operated with nitrogen gas circulation cooling. The power flow to the divertor is low due to large radiations of the main and divertor plasmas, while the purity of plasma was largely improved by introduction of glow discharge cleaning of 300 V*1 A.<>

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JT-60单空开导流器改造后的运行结果

从几个方面对JT-60U (JAERI托卡马克-60升级版)托卡马克机的硬件性能进行了研究。实验操作已经进展到记录高达17kw的D-D聚变功率。测量了环形磁场线圈的位移，并验证了加固的效果。船舶动位移为振幅在0.3 mm以内的振动和相对缓慢的倾移。对于第一壁，导流器遭受的热流宽度为4 ~ 5cm，接近设计值。在20兆瓦的中性光束加热2秒的情况下，导流器装甲被发现最多上升500摄氏度，并且它仍然在氮气循环冷却下运行。由于主等离子体和分流体的辐射较大，分流器的功率流较低，而等离子体的纯度通过引入300 V*1 a的辉光放电清洗而大大提高。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering

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