Author:
CHEN 陈 Dalong 大龙,SHEN 沈 Biao 飊,SHI 石 Tonghui 同辉,GUO 郭 Bihao 笔豪,LI 李 Tingyu 婷玉,CHEN 陈 Lixing 力行,XUE 薛 Minmin 敏敏,CHU 楚 Nan 南
Abstract
Abstract
In EAST long-pulsed discharge (hundreds of seconds), electric magnetic diagnosis (EMD) is very important, since EMD not only monitors tokamak security status but also provides accurate measurement accuracy for reconstruction of the plasma boundary. To avoid current measurement drift, a fiber optic current sensor, based on the Faraday effect, is developed and used for poloidal and plasma current feedback control for the first time, relative current measurement accuracy is within 0.5%. To ensure plasma boundary control accuracy, a detailed set of magnetic measurement calibration methods is developed before the plasma discharge. The maximum relative error is less than 1%, the corresponding control accuracy is within 1 cm. To minimize integrator drift error, a long-pulse integrator test is essential, the corresponding drift error needs to be subtracted in plasma control system. Besides, the saddle coil and Mirnov coil not only help to detect MHD issues, but are also utilized for plasma disruption prediction during the long-pulse discharge.
Funder
National MCF Energy R&D Program of China
National Natural Science Foundation of China
Cited by
3 articles.
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