超导偏滤器托卡马克中钨杂质产生及在边界等离子体中输运的实验和模拟研究

钨是目前最有希望在未来聚变堆中使用的面向等离子体材料，但是作为高原子序数材料，其最大的问题是钨杂质进入中心等离子体并且产生大量的辐射能量损失，严重损害聚变等离子体的品质，因此对于聚变装置中钨杂质产生及其输运的研究有着极其重要的意义。由于超导偏滤器托卡马克EAST与ITER具有极大的相似性，本项研究拟在EAST上建立钨杂质光谱，通过实验与模拟结合的方法得到EAST在不同等离子体条件下的反光子效率，并测量不同运行条件下偏滤器钨的腐蚀和钨杂质在边界等离子体中的输运情况，结合等离子体流体程序SOLPS5.0、材料腐蚀与沉积程序ERO以及杂质输运程序DIVIMP对EAST上的实验进行模拟，通过比较实验和模拟的结果，力图掌握EAST偏滤器上钨杂质的产生和在边界等离子体中输运的规律，并对ITER全钨偏滤器的腐蚀和杂质输运进行预测，为ITER和未来的聚变装置的设计与运行提供科学基础。

Tungsten is currently the most promising plasma facing material to be used in future fusion reactors. However, as high atomic number material, the most serious problem is that the tungsten impurities can move into the core plasma and induce high energy loss by radiation, which will do great damage to the quality of the fusion plasma. Therefore, studies of tungsten impurities generation and their transport in devices are of an extremely important significance . Because of the great similarity between superconducting divertor Tokamaks EAST and ITER, this research proposed to build up tungsten impurity spectroscopy on EAST. The inverse photon efficiency under different plasma conditions of EAST could be obtained by the combination of experiments and simulations. The erosion of divertor tungsten and transport of tungsten impurities in edge plasma will be measured under different operation conditions. The EAST experiments will be simulated by combined codes: plasma fluid code SOLPS5.0, materials erosion and deposition code ERO and impurity transport code DIVIMP. It seeks to grasp the laws of tungsten impurities generation from EAST divertor and their transport in edge plasma via the comparison of experimental and simulation results. The erosion of ITER full tungsten divertor and impurity transport will be predicted. This research can provide scientific basis for the design and operation of ITER and future fusion devices.