To solve the power exhaust handling challenge, meanwhile maintaining acceptable divertor target erosion, the snowflake divertor (SFD) is proposed on HL-2M tokamak. In this work, simulations are carried out by using scrape-off layer plasma simulation code SOLPS-ITER to understand the advantages of SFD on plasma detachment, with emphasis on effects of the magnetic configuration on the neutral and impurity particles transport. Two magnetic configurations, i.e. the standard divertor (SD) and SFD, are chosen for comparison. By increasing the upstream plasma density, the simulation reveals the outer target of SFD reaches plasma detachment at much lower density than that of SD. The reason lays to that SFD can enhance the accumulation of neutral particles and carbon impurity in divertor region, thus increase divertor power radiation and divertor impurity screening capabilities. The target shape combined with the magnetic configuration also plays important role in neutral and impurity accumulation and transport. Further analysis of the roles of deuterium and lower charge-state carbon on the power radiation in divertor region is presented. Finally, the performance of SFD on the divertor plasma with the increasing input power is also simulated and discussed, which is informative for the future fusion device.

为了解决动力排气处理难题，同时保持可接受的滤清器目标侵蚀，在HL-2M托卡马克上提出了雪花滤清器（SFD）。在这项工作中，通过使用刮除层等离子体模拟代码SOLPS-ITER进行模拟，以了解SFD在等离子体分离方面的优势，重点是磁结构对中性和杂质颗粒传输的影响。选择两种磁性配置，即标准分流器（SD）和SFD，进行比较。通过增加上游等离子体密度，模拟显示SFD的外部目标以比SD更低的密度达到等离子体脱离。原因在于SFD可以增强偏滤器区域中性粒子和碳杂质的积累，因此增加了偏滤器功率辐射和偏滤器杂质筛选能力。目标形状与磁性结构的结合在中性和杂质的积累和运输中也起着重要的作用。进一步分析了氘和低电荷态碳对偏滤区功率辐射的作用。最后，随着输入功率的增加，SFD在偏滤器等离子体上的性能也得到了仿真和讨论，这为未来的聚变设备提供了有益的信息。