EAST中性束注入下快离子输运行为的研究  

Study on the transport behavior of fast ions under neutral beam injection heating in EAST

作　　者：肖敏 吴斌[1] 钟国强 胡立群 王进芳 郝保龙 黄娟 周瑞杰 李凯 XIAO Min;WU Bin;ZHONG Guoqiang;HU Liqun;WANG Jinfang;HAO Baolong;HUANG Juan;ZHOU Ruijie;LI Kai(Institute of Plasma Physics,Chinese Academy of Sciences,Hefei 230031,China;University of Chinese Academy of Sciences,Beijing 100049,China)

机构地区：[1]中国科学院等离子体物理研究所,合肥230031 [2]中国科学院大学,北京100049

出　　处：《核技术》2020年第6期95-102,共8页Nuclear Techniques

基　　金：国家重点研发计划项目(No.2017YFE0300503);国家自然科学基金(No.11605241、No.11875290、No.11975276)资助。

摘　　要：利用等离子体输运分析程序TRANSP和粒子导心轨道模拟程序ORBIT,结合聚变中子和等离子体储能诊断数据,对EAST(Experimental Advanced Superconducting Tokamak)托卡马克中性束注入加热时不同等离子体电流和纵场强度下的快离子输运行为进行了研究。实验和模拟结果表明:中性束反向束注入时的快离子初始轨道损失功率大于中性束同向束;中性束4条束线产生快离子初始轨道损失区域主要集中在装置中平面以下第一壁以及偏滤器区域;在EAST目前的运行参数范围内,提高等离子体电流和纵场强度,可以使等离子体中快离子的漂移轨道宽度和拉莫尔回旋半径缩小,更有利于快离子的约束,从而提高中性束的加热效率,增加聚变中子产额和等离子体储能。[Background] In order to realize a magnetically confined plasma self-sustaining fusion reaction, fast ions need to be confined in the magnetic field for a long time for them to collide sufficiently, heat the main plasma,and drive the plasma current. [Purpose] This study aims to explore the fast ions transport behavior of experimental advanced superconducting Tokamak(EAST) neutral beam injection(NBI) heating under different plasma currents and toroidal magnetic field. [Methods] The plasma transport analysis code TRANSP and particle-guided center orbit simulation code ORBIT were combined with fusion neutron and plasma stored energy diagnostic data to study the transport behavior of fast ions. Experimental data under different plasma current and toroidal magnetic field intensity were compared with the simulation results. [Results] Experimental and simulation results show that the prompt loss power of fast ions from the neutral beam injection(NBI) counter-beam is higher than that from the NBI co-beam.Under the effect of the clockwise plasma current and the counterclockwise toroidal magnetic field, the loss areas of fast ions prompt loss from the four beam lines of NBI are mainly concentrated in the first wall below midplane and divertor area of the device. Within the current operating parameters of EAST, increasing the plasma current and toroidal magnetic field can reduce the drift orbit width and the larmor radius of fast ions in the plasma, which is much better for the confinement of the fast ions. [Conclusions] Increasing the plasma current and toroidal magnetic field can improve the heating efficiency of the NBI, especially for the counter-beam, which can increase the fusion neutron yield and stored energy of plasma.

关 键 词：快离子行为 聚变中子 初始轨道损失 中性束注入 EAST 

分 类 号：TL61[核科学技术—核技术及应用] TL65