Long pulse discharge is one of the important goals of HT-7 superconducting tokamak experiments. For ITER （International Thermonuclear Experimental Reactor） or a tokamak reactor, carrying out a steady operation is on...Long pulse discharge is one of the important goals of HT-7 superconducting tokamak experiments. For ITER （International Thermonuclear Experimental Reactor） or a tokamak reactor, carrying out a steady operation is one of the main techniques. For long pulse discharges on HT-7 the poloidal flux is used as the feedback signal to control the injected power of LHCD （Low Hybrid Current Drive） system. Experimental results are presented.展开更多
The main efforts of HT-7 superconducting tokamak are directed to quasi-steady state discharges and relevant physics. Significant progress has been realized in obtaining high-performance discharges under a quasi-steady...The main efforts of HT-7 superconducting tokamak are directed to quasi-steady state discharges and relevant physics. Significant progress has been realized in obtaining high-performance discharges under a quasi-steady state in HT-7. The long pulse discharges have been obtained with duration up to more than one minute. Wall recycling has been studied in the long duration discharges in HT-7. The recycling coefficient R of each plasma increases with time. The uncontrolled density increase is accompanied by hydrogen and the impurity influx originating mainly from the limiter surface and the parts of the inner vessel. The edge recycling after boronization will also be discussed in this paper.展开更多
Temperature measurement by IR （infrared） camera was performed oll HT-T tokamak. particularly during long pulse discharges, during which the temperature of the hot spots on the belt limiter exceeded 1000℃. The heat ...Temperature measurement by IR （infrared） camera was performed oll HT-T tokamak. particularly during long pulse discharges, during which the temperature of the hot spots on the belt limiter exceeded 1000℃. The heat load on the surface of the movable limiter could be obtained through ANSYS with the temperature measured by IR-camera. This work could be important for the temperature measurement and heat load study on the first wall of EAST device.展开更多
文摘Long pulse discharge is one of the important goals of HT-7 superconducting tokamak experiments. For ITER （International Thermonuclear Experimental Reactor） or a tokamak reactor, carrying out a steady operation is one of the main techniques. For long pulse discharges on HT-7 the poloidal flux is used as the feedback signal to control the injected power of LHCD （Low Hybrid Current Drive） system. Experimental results are presented.
基金The project supported by the Meg-science Engineering Project of the Chinese Academy of Sciences
文摘The main efforts of HT-7 superconducting tokamak are directed to quasi-steady state discharges and relevant physics. Significant progress has been realized in obtaining high-performance discharges under a quasi-steady state in HT-7. The long pulse discharges have been obtained with duration up to more than one minute. Wall recycling has been studied in the long duration discharges in HT-7. The recycling coefficient R of each plasma increases with time. The uncontrolled density increase is accompanied by hydrogen and the impurity influx originating mainly from the limiter surface and the parts of the inner vessel. The edge recycling after boronization will also be discussed in this paper.
基金National Natural Science Foundation of China(No.10305011)
文摘Temperature measurement by IR （infrared） camera was performed oll HT-T tokamak. particularly during long pulse discharges, during which the temperature of the hot spots on the belt limiter exceeded 1000℃. The heat load on the surface of the movable limiter could be obtained through ANSYS with the temperature measured by IR-camera. This work could be important for the temperature measurement and heat load study on the first wall of EAST device.
