Upgrade of the magnetic diagnostic system for restart of HT-6M operation

The HT-6M tokamak at the Thailand Institute of Nuclear Technology has been restarted.In order to ensure the smooth breakdown of plasma and obtain plasma discharge parameters,optimization of the poloidal field coils and upgrade of the magnetic diagnostics are described in this article.A perfect null field(stray field in the main chamber<10 G)is obtained using an ohmic heating field.To obtain important information about the plasma,an external magnetic diagnostics system is designed and calibrated,including a Rogowski coil(measuring plasma current),a magnetic probe(measuring external field),diamagnetic loops(measuringβ_(p))and so on.In order to realize high-frequency signal measurement and transmission,a series of frequency responses with the magnetic probe and transmission line are tested.Later,to verify the null field,a fitting code is developed to reconstruct the stray field in the vacuum chamber based on magnetic probe measurements and flux loops.The results show that the error is within 1.5%.This indicates the accuracy of the magnetic measurement system and ensures the preparation for the breakdown of plasma.

Comparison of different noble gas injections by massive gas injection on plasma disruption mitigation on Experimental Advanced Superconducting Tokamak

Massive gas injection(MGI)is a traditional plasma disruption mitigation method.This 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 insignificant.However,both pre-TQ and CQ durations decreased considerably with the increase in gas injection amount.The effect of atomic mass on pre-TQ and CQ durations showed the opposite trend.The observed trend could help in controlling CQ duration in a reasonable area.Moreover,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 disruption.These results provided essential data support for plasma disruption mitigation on EAST and future fusion devices.