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首页> 美国政府科技报告 >Impurity Control Test Facility (ICTF) For the Study of Fusion Reactor Plasma/Edge Materials Interactions
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Impurity Control Test Facility (ICTF) For the Study of Fusion Reactor Plasma/Edge Materials Interactions

机译：杂质控制测试设施（ICTF）用于聚变反应堆等离子体/边缘材料相互作用的研究

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A test facility for investigating many of the impurity control issues associated with the interactions of materials with the plasma edge is outlined. Analysis indicates that the plasma edge conditions expected in TFCX, INTOR, etc. can be readily produced at the end cells of an rf stabilized mirror, similar in some respects to the Phaedrus device at the University of Wisconsin. A steady-state, Impurity Control Test Facility (ICTF) based on such a mirror device is expected to produce a plasma with typical parameters of n/sub e/ approx. 3 x 10 exp 18 m exp -3 , T/sub e/ = 50 eV, and T/sub i/ = 100 eV at each end cell. A heat load of approx. 2 MW/m exp 2 over areas of approx. 1600 cm exp 2 could be produced at each end with 800 kW of ICRH power. These conditions would provide a unique capability for examining issues such as erosion/redeposition behavior, properties of redeposited materials, high recycling regimes, plasma edge operating limits for high-Z materials, and particle pumping efficiencies for limiter and divertor designs. (ERA citation 09:047106)

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