EAST共振磁扰动线圈作用下边界粒子再循环三维特性的研究

The mitigation of the heat load on divertor plates is essential for the aim of the steady-state high-power long-pulse operation on ITER. The resonant magnetic perturbation (RMP) coils can induce edge magnetic topology distortion in tokamaks, which under certain condition can achieve the splitting of divertor strike point and eventually open new channels for divertor power exhaust. The project, based on the EAST tokamak which has fully superconducting coils with divertor plasma configurations similar to ITER, aims at the international front of divertor physics study and focuses on the urgent necessity for the steady-state operation of EAST and ITER. By utilizing the infra-red camera, divertor Langmuir probe arrays at different toroidal locations, and optics diagnostics, along with other key diagnostics and simulation, to study on the boundary recycling process under the Three-Dimensional effect under RMP Modulation on the EAST to acquire the physical mechanism. These researches are of significant importance for the effective reduction of steady-state divertor heat flux while maintaining the steady-state operations for high-performance plasmas.

ITER未来运行目标是高功率长脉冲稳态等离子体，实现该目标的必要条件之一：是有效降低流向偏滤器靶板较高热负荷。共振磁扰动线圈(RMP)可引起托卡马克边界三维磁拓扑结构的改变，在一定条件下可实现打击点撕裂进而打开新的热与粒子排除通道。本项目研究依托于EAST装置，其拥有与ITER类似的全超导非圆截面的实验装置，紧紧围绕EAST与未来ITER高功率长脉冲稳态运行的迫切需要，基于红外相机、具有环向多阵列的偏滤器探针、光谱诊断等关键诊断系统并结合理论模拟，通过研究EAST上RMP调制等离子体发生三维效应时边界再循环过程来分析其内在物理机制。该研究对于有效降低偏滤器稳态峰值热流，进而维持高性能等离子体的稳态运行具有重要意义。

共振磁扰动线圈(RMP)所产生的扰动场可引起托卡马克边界三维磁拓扑结构的改变，在一定条件下可实现打击点撕裂，从而打开新的热流与粒子流排除通道，使得有效的降低流向偏滤器靶板较高热负荷，实现高功率长脉冲稳态等离子体运行模式。本项目研究依托于与ITER类似的全超导非圆截面的实验装置EAST，基于多项物理诊断，通过研究RMP调制等离子体发生三维效应时边界再循环过程，将实验和模拟相结合研究其内在的物理机制，该研究对于有效降低偏滤器稳态峰值热流，进而维持高性能等离子体的稳态运行具有重要意义。