EAST上基于平衡中性束注入方法的L模等离子体自发扭矩分布实验研究  

Experimental study of intrinsic torque distribution of L-mode plasma based on balanced neutral beam injection on EAST

作　　者：袁泓 尹相辉 吕波 金仡飞 Bae Cheonho 张洪明 符佳 刘海庆 赵海林 臧庆 王福地 向东[1] YUAN Hong;YIN Xianghui;LYU Bo;JIN Yifei;BAE Cheonho;ZHANG Hongming;FU Jia;LIU Haiqing;ZHAO Hailin;ZANG Qing;WANG Fudi;XIANG Dong(School of Nuclear Science and Technology,University of South China,Hengyang 421001,China;Institute of Plasma Physics,Hefei Institutes of Physical Science,Chinese Academy of Sciences,Hefei 230031,China;School of Electrical Engineering,University of South China,Hengyang 421001,China;Science Island Branch,Graduate School of University of Science and Technology of China,Hefei 230026,China;Enn Science and Technology Development Co.,Ltd.,Langfang 065001,China)

机构地区：[1]南华大学核科学技术学院,衡阳421001 [2]中国科学院合肥物质科学研究院等离子体物理研究所,合肥230031 [3]南华大学电气工程学院,衡阳421001 [4]中国科学技术大学研究生科学岛分院,合肥230026 [5]新奥科技发展有限公司,廊坊065001

出　　处：《物理学报》2025年第9期241-249,共9页Acta Physica Sinica

基　　金：国家自然科学基金(批准号:12175278,U23A2077);湖南省教育厅重点项目和青年项目(批准号:21B0439);磁约束聚变安徽省实验室开放基金(批准号:2023AMF03005)资助的课题。

摘　　要：等离子体旋转及其剪切是影响聚变装置的关键参数之一,等离子体旋转的驱动和控制对未来聚变堆的稳定运行和约束改善都具有很大意义.目前靠外部动量注入的方式不足以在满足Q大于5的同时抑制电阻壁模不稳定性.因此,有必要对不依赖外部动量注入的等离子体自发旋转展开实验研究.为了更好地预测未来聚变装置中自发旋转速度的大小,本文在东方超环托卡马克(EAST)上开展了残余应力与无量纲参数的定标研究,利用平衡中性束的方法进行了多次自发扭矩的实验测量,为未来托卡马克装置中等离子体自发旋转的预测提供实验依据.实验定标结果表明,芯部残余应力与ρ*^(-1.80±1.26)相关,而边界残余应力的定标则显示出对ρ*^(1.26±0.63)的依赖性,这表明随着装置尺寸的增大,未来托卡马克聚变堆中芯部的残余应力可能会增大,而边界残余应力则减小.芯部与边界残余应力的定标结果差异表明,在边界区域刮削层区残余应力的产生过程中,有E×B流剪切以外的对称性破坏机制起主导作用.在自发扭矩与ν*的定标之间发现芯部自发扭矩依赖于ν*^(0.21±0.18).结合芯部自发扭矩与归一化旋转半径、归一化碰撞率的定标结果,得到芯部自发扭矩的定标律为ρ*^(-1.39±0.71)ν*^(0.11±0.10).使用ITER氘-氚混合运行方案中的等离子体参数预测得到芯部自发扭矩大小为(1.0±6.3)N·m,远小于之前DIII-D预测结果.Plasma rotation and its shear are key parameters influencing the performance of fusion devices.The prediction and control of plasma rotation velocity are of great significance for improving the stable operation and confinement of future fusion reactors.External momentum injection methods are insufficient to suppress resistive wall mode instability while achieving Q greater than 5 in international thermonuclear experimental reactor(ITER).Therefore,it is necessary to conduct experimental research on intrinsic plasma rotation that does not rely on external momentum injection.To better predict the magnitude of intrinsic rotation velocity in future fusion devices,we conduct an experimental study on the scaling of residual stress and dimensionless parameters on EAST.Using the balanced neutral beam,multiple measurements of intrinsic torque are performed,providing experimental basis for predicting the intrinsic rotation in future tokamak devices.The scaling results indicate that the core residual stress is dependent onρ*^(-1.80±1.26).while the scaling of edge residual stress shows an opposite trend withρ*^(1.26±0.63).This suggests that as the device size increases,the core residual stress in future large devices can increase,while the edge residual stress can decrease.The difference in scaling results between the core and edge residual stress indicates that in the edge region,the symmetrybreaking mechanism other than E×B flow shear dominates the generation of residual stress in the scrape-off layer.A relationship is found between intrinsic torque andν*.revealing that the core intrinsic torque depends onν*^(0.21±0.18)Combining the scaling results of core intrinsic torque with the gyroradius and normalized collisionality,the scaling law for core intrinsic torque is obtained to beρ*^(-1.39±0.71)ν*^(0.11±0.10)Using plasma parameters of ITER operation scenario 1,the core intrinsic torque in future ITER plasma is predicted to be (1.0±6.3)N·m,which is much smaller than the predicted magnitude at DIII-D.

关 键 词：托卡马克 动量输运 残余应力 定标律 

分 类 号：O53[理学—等离子体物理]