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作 者:徐国盛 贾国章 丁根凡 陶余强 孟令义 余林 王亮 刘建斌 Guosheng XU;Guozhang JIA;Genfan DING;Yuqiang TAO;Lingyi MENG;Lin YU;Liang WANG;Jianbin LIU(Institute of Plasma Physics,Hefei Institutes of Physical Science,Chinese Academy of Sciences,Hefei 230031,People's Republic of China;School of Physics and lectronic Information,Anhui Normal University,Wuhu 241000,People's Republic of China)
机构地区:[1]Institute of Plasma Physics,Hefei Institutes of Physical Science,Chinese Academy of Sciences,Hefei 230031,People's Republic of China [2]School of Physics and lectronic Information,Anhui Normal University,Wuhu 241000,People's Republic of China
出 处:《Plasma Science and Technology》2023年第10期60-67,共8页等离子体科学和技术(英文版)
基 金:funded by the National Magnetic Confinement Fusion Program of China(Nos.2019YFE03030000,2019YFE03080500 and 2022YFE03060004);National Natural Science Foundation of China(No.U19A20113)。
摘 要:A major challenge facing the steady-state operation of tokamak fusion reactors is to develop a viable divertor solution with order-of-magnitude increase in power handling capability as compared with present experience.A recently developed divertor concept for this end has been tested recently on EAST tokamak through combining the effects of a closed divertor corner and E×B drifts.The E×B drifts in the divertor move particles towards the outer divertor corner area in the scrape-off layer for B×▽B directed away from the divertor,which can significantly enhance the particle concentration there,facilitating divertor detachment.In recent EAST experiments,the effects have been demonstrated where the lowest electron temperature at the divertor plate is obtained with strike point located close to the corner in the horizontal target and with B×▽B away from the divertor.These experimental results are in reasonable agreement with SOLPS-ITER simulations including drift effects,suggesting that the new divertor concept potentially provides a promising divertor solution for long-pulse operations of future tokamak fusion reactors with much higher power fluxes.
关 键 词:divertor concept closed divertor corner E×B drifts SOLPS-ITER simulation EAST tokamak
分 类 号:TL6[核科学技术—核技术及应用]
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