长脉冲托卡马克上中性粒子对第一壁材料腐蚀的研究

在磁约束聚变研究中，第一壁材料的腐蚀直接关系到材料的寿命、等离子体性能以及氚滞留等关键问题，是未来聚变堆的核心问题之一，其中由电荷交换产生的不受磁场约束的高能中性粒子对第一壁腐蚀的大小和机理尚不清楚，直接影响到全超导偏滤器托卡马克ITER的相关预测和设计。由于EAST与ITER具有极大的相似性，本申请拟在EAST上建立有效测量中性粒子能量和通量的诊断，并在装置不同位置开展中性粒子对材料的腐蚀实验，同时结合等离子体流体程序SOLPS和材料腐蚀程序ERO对EAST上的实验结果进行模拟，通过实验与模拟的比较力图阐明偏滤器托卡马克中不同位置和等离子体条件下电荷交换产生中性粒子的分布情况及其对第一壁腐蚀的影响规律。在此基础上模拟预测ITER装置上中性粒子对第一壁材料的腐蚀与沉积，为ITER和未来的聚变堆的设计与运行提供科学基础与积累经验。

In the magnetic confinement fusion research, the erosion of first wall materials which is directly related to the vital issues such as the material lifetime, plasma performance and tritium retention, is one of the key problems in the future fusion reactors. It is not clear about the magnitude and mechanism of first wall erosion by energetic charge exchange neutrals which is not confined by the magnetic field. This has direct impact on the related prediction and design for the fully superconducting divertor tokamak ITER. Because of the great similarity between EAST and ITER, this application proposes to build up the valid diagnostics on EAST to measure the energy and flux of neutral particles, and to carry out experiments on material erosion by neutral particles at different locations of the device. The experimental results on EAST will be simulated together by plasma fluid code SOLPS and material erosion code ERO. It seeks to clarify the distribution of charge exchange neutral particles at different locations and in various plasma conditions and the laws of its impact on the first wall erosion in divertor tokamaks via the comparison of experimental and simulation results. On the basis of this, the erosion and deposition of first wall materials by neutrals in ITER will be predicted by simulations. This research can provide scientific basis and experience accumulation for the design and operation of ITER and future fusion reactors.