首页|Characteristics of the SOL ion-to-electron temperature ratio on the J-TEXT tokamak with different plasma configurations
Characteristics of the SOL ion-to-electron temperature ratio on the J-TEXT tokamak with different plasma configurations
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Accurate measurement of the average plasma parameters in the edge region,including the temperature and density of electrons and ions,is critical for understanding the characteristics of the scrape-off layer(SOL)and divertor plasma transport in magnetically confined fusion research.On the J-TEXT tokamak,a multi-channel retarding field analyzer(RFA)probe has been developed to study average plasma parameters in the edge region under various poloidal divertor and island divertor configurations.The edge radial profile of the ion-to-electron temperature ratio,τi/e,has been determined,which gradually decreases as the SOL ion self-collisionality,v*SOL,increases.This is broadly consistent with what has been observed previously from various tokamak experiments.However,the comparison of experimental results under different configurations shows that in the poloidal divertor configuration,even under the same v*SOL,τi/e in the SOL region becomes smaller as the distance from the X-point to the target plate increases.In the island divertor configuration,ri/e near the O-point is higher than that near the X-point at the same v*SOL,and both are higher than those in the limiter configuration.These results suggest that the magnetic configuration plays a critical role in the energy distributions between electrons and ions at the plasma boundary.
ion temperatureisland divertorpoloidal divertorretarding field analyzer(RFA)probe
李存凯、梁云峰、江中和、周松、华建坤、阳杰、杨庆虎、Alexander KNIEPS、Philipp DREWS、徐鑫、毛飞越、谢伟、杨雨桐、郭金龙、李杨波、任正康、陈志鹏、王能超、the J-TEXT Team
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International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics,State Key Laboratory of Advanced Electromagnetic Engineering and Technology,School of Electrical and Electronic Engineering,Huazhong University of Science and Technology,Wuhan 430074,People's Republic of China
Forschungszentrum Jülich GmbH,Institut für Energie-und Klimaforschung—Plasmaphysik,Partner of the Trilateral Euregio Cluster(TEC),Jülich 52425,Germany
National Magnetic Confinement Fusion Energy Research and Development Program of ChinaNational Natural Science Foundation ofChina
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