An integrated modeling workflow using OMFIT is constructed to evaluate the effects of tungsten (W) impurity on China Fusion Engineering Test Reactor (CFETR) performance. Self-consistent modeling of W core density profile, accounting for both turbulent and neoclassical transport contributions, is performed based on the steady-state scenario of CFETR phase I (Wan et al 2016 IAEA; Wan et al 2017 Nucl. Fusion57 102009). It is found that the fusion performance degrades mildly with increasing W concentration. The main challenge arises in the sustainment of H-mode operation with significant W radiation. Assuming that the power threshold of H–L back transition is approximately the same as that of L–H transition, the W fraction at the plasma boundary is not allowed to exceed to stay in H-mode for CFETR phase I according to the scaling law proposed by Takizuka et al (2004 Plasma Phys. Control Fusion46 A227–33). In addition, the tolerance of W concentration decreases with increasing pedestal density through a trade-off study of pedestal density and temperature. A future step is to connect the core simulation to W wall erosion modeling.
利用OFIT构建了一个集成建模工作流，以评估钨（W）杂质对中国聚变工程测试堆（CFETR）性能的影响。基于CFETR第一阶段稳态情景（Wan等，2016年IAEA；Wan等，2017年Nucl. Fusion 57 102009），对W芯部密度分布进行了自洽建模，同时考虑了湍流和新经典输运贡献。研究发现，随着W浓度的增加，聚变性能略有下降。主要挑战在于在显著W辐射条件下维持H模运行。假设H–L回跃的功率阈值与L–H跃迁大致相同，根据Takizuka等人提出的定标律（2004年Plasma Phys. Control Fusion 46 A227–33），CFETR第一阶段等离子体边界处的W份额不允许超过该值以保持H模。此外，通过台座密度与温度的权衡研究，W浓度的容限随台座密度增加而降低。未来的工作是将芯部模拟与W壁侵蚀建模相连接。