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Chinese Physics B 2023年第7期32卷 42-48页

作者：赵胜波庄会东元京升张德皓黎立曾龙陈大龙毛松涛黄明左桂忠胡建生 Institute of Plasma Physics Hefei Institutes of Physical ScienceChinese Academy of SciencesHefei 230031China University of Science and Technology of China Hefei 230026China Department of Engineering Physics Tsinghua UniversityBeijing 100084China

Massive gas injection(MGI)is a traditional plasma disruption mitigation *** method directly injected massive gas into the pre-disruption plasma and had been developed on the Experimental Advanced Superconducting Tokamak(EAST).Different noble gas injection experiments,including He,Ne,and Ar,were performed to compare the mitigation effect of plasma disruption by evaluating the key parameters such as flight time,pre-thermal quench(pre-TQ),and current quench(CQ).The flight time was shorter for low atomic number(Z)gas,and the decrease in flight time by increasing the amount of gas was ***,both pre-TQ and CQ durations decreased considerably with the increase in gas injection *** effect of atomic mass on pre-TQ and CQ durations showed the opposite *** observed trend could help in controlling CQ duration in a reasonable ***,the analysis of radiation distribution with different impurity injections indicated that low Z impurity could reduce the asymmetry of radiation,which is valuable in mitigating plasma *** results provided essential data support for plasma disruption mitigation on EAST and future fusion devices.

关键词： disruption mitigation massive gas injection(MGI) Experimental Advanced Superconducting Tokamak(EAST)

Development of a Fast Valve for disruption mitigation and its Preliminary Application to EAST and HT-7

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Plasma Science and Technology 2013年第8期15卷 745-749页

作者：庄会东张晓东 Institute of Plasma Physics Chinese Academy of Sciences

In large tokamaks, disruption of high current plasma would damage plasma facing component surfaces （PFCs） or other inner components due to high heat load, electromagnetic force load and runaway electrons. It would also influence the subsequent plasma discharge due to production of impurities during disruptions. So the avoidance and mitigation of disruptions is essential for the next generation of tokamaks, such as ITER. Massive gas injection （MGI） is a promising method of disruption mitigation. A new fast valve has been developed successfully on EAST. The valve can be opened in 0.5 ms, and the duration of open state is largely dependent on the gas pressure and capacitor voltage. The throughput of the valve can be adjusted from 0 mbar·L to 700 mbar·L by changing the capacitor voltage and gas pressure. The response time and throughput of the fast valve can meet the requirement of disruption mitigation on EAST. In the last round campaign of EAST and HT-7 in 2010, the fast valve has operated successfully. He and Ar was used for the disruption mitigation on HT-7. By injecting the proper amount of gas, the current quench rate could be slowed down, and the impurities radiation would be greatly improved. In elongated plasmas of EAST discharges, the experimental data is opposite to that which is expected.

关键词： EAST disruption mitigation MGI fast valve

Research on High Pressure Gas Injection As a Method of Fueling, disruption mitigation and Plasma Termination for Future Tokamak Reactors

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Plasma Science and Technology 2005年第5期7卷 3057-3061页

作者：宋云涛 S.Nishio Institute of Plasma Physics Chinese Academy of Sciences Department of Fusion Plasma Research of Japan Atomic Energy Research InstituteNaka-machi Naka-gun Ibaraki-ken 311-0193 Japan

High-pressure gas injection has proved to be an effective disruption mitigation tech- nique in DIII-D tokamak experiments. If the method can be applied in future tokamak reactors not only for disruption mitigation but also for plasma termination and fueling, it will have an attractive advantage over the pellet and liquid injection from the viewpoint of economy and engineering design. In order to investigate the feasibility of this option, a study has been carried out with relevant parameters for conveying tubes of different geometrical sizes and for different gases. These parameters include pressure drop, lagger time after the valve＇s opening, gas diffusion in an ultra-high vacuum condition, and particle number contour.

关键词： tokamak reactor disruption mitigation fueling gas injection

Overview of runaway current suppression and dissipation on J-TEXT tokamak

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Plasma Science and Technology 2022年第12期24卷 115-125页

作者：陈忠勇林志芳严伟黄都伟魏禹农李由蔡念恒胡捷丁永华梁云峰江中和 J-TEXT Team International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics State Key Laboratory of Advanced Electromagnetic Engineering and TechnologySchool of Electrical and Electronic EngineeringHuazhong University of Science and TechnologyWuhan 430074People's Republic of China School of Electrical Engineering&Automation Jiangsu Normal UniversityXuzhou 221116People's Republic of China

The main works on disruption mitigation including suppression and mitigation of runaway current on the J-TEXT tokamak are summarized in this *** strategies for the mitigation of runaway electron(RE) beams are applied in *** first strategy enables the REs to be completely suppressed by means of supersonic molecular beam injection and resonant magnetic perturbation which can enhance RE loss,magnetic energy transfer which can reduce the electric field,and secondary massive gas injection(MGI) which can increase the collisional *** the second strategy,the runaway current is allowed to form but should be dissipated or soft landed within *** is observed that the runaway current can be significantly dissipated by MGI,and the dissipation rate increases with the injected impurity particle number and eventually stabilizes at 28 MA s^(-1).The dissipation rate of the runaway current can be up to 3 MA s^(-1)by ohmic *** pellet injection has been chosen as the main disruption mitigation method,which has the capability of injecting material deeper into the plasma for higher density assimilation when compared to ***,simulation works show that the RE seeds in the plasma are strongly influenced under different phases and sizes of 2/1 mode locked islands during thermal *** robust runaway suppression and runaway current dissipation provide an important insight on the disruption mitigation for future large tokamaks.

关键词： tokamak disruption mitigation runaway electron runaway current