Material testing for plasma facing components (PFCs) in future fusion devices reveals important damage mechanisms that impact lifetime and performance. During operation, PFCs in the divertor region will be subjected to high particle fluxes and heat loads. Tungsten (W) is currently the leading candidate material for divertor PFCs, due to its high melting point, high thermal conductivity, and low tritium retention. Laboratory experiments have effectively characterized mechanisms of damage on W due to different forms of radiation. However, understanding how different species of incident plasma particles interact with one another to affect the resultant strength of the material remains in development.

In this study, W samples were exposed to simultaneous ELM-like heat loading and high-flux He⁺ and D⁺ ion irradiation at different ELM intensities to further elucidate the complex synergistic effects inherent in a fusion environment. ELM-like heat loading was replicated using a 1064 nm Nd:YAG pulsed millisecond laser at different energy densities. Exposures produced a shale-like microstructure with or without concurrent He⁺ and D⁺ ion irradiation. However, adding D⁺ to a simultaneous laser + He⁺ irradiation reduced pore formation and inhibited early-stage nanostructure formation. Changes in surface morphology with the addition of D⁺ could be attributed to super-saturation in the near-surface layer. While the addition of He⁺ and D⁺ clearly increased W erosion, the laser energy density did not have as clear of an effect. Increasing the ELM intensity reduced the number of pores, but increased the pore size. Future studies need to explore whether near-surface D impacts pore formation and total He desorption. Continued research on the combined effect of high-flux particle irradiation and transient heat loading will help refine predictions of material performance for ITER and beyond.

在未来的聚变设备中对面向等离子体的组件（PFC）进行的材料测试揭示了影响寿命和性能的重要损坏机制。在运行过程中，偏滤器区域中的PFC将承受较高的颗粒通量和热负荷。钨（W）由于其高熔点，高导热性和低retention保留性，目前是偏滤器PFC的主要候选材料。实验室实验已有效地表征了由于不同形式的辐射而对W造成损害的机理。然而，了解不同种类的入射等离子体颗粒如何相互作用以影响材料的合成强度仍在发展中。

在这项研究中，W样品在不同的ELM强度下同时受到类似ELM的热负荷和高通量He ⁺和D ⁺离子辐照，以进一步阐明聚变环境中固有的复杂协同效应。使用1064 nm Nd：YAG脉冲毫秒激光以不同的能量密度复制了类似ELM的热负荷。暴露会产生页岩状的微观结构，同时伴有或不伴有He ⁺和D ⁺离子辐照。但是，在同时进行的激光+ He ⁺辐射中添加D ⁺可以减少孔的形成并抑制早期纳米结构的形成。添加D ^+后表面形态的变化可以归因于近表层的过饱和。虽然添加He ⁺和D ⁺明显增加了W腐蚀，但激光能量密度没有明显的影响。ELM强度的增加减少了孔的数量，但增加了孔径。未来的研究需要探索近地表D是否会影响孔隙形成和总He解吸。继续研究高通量粒子辐照和瞬态热负荷的综合作用，将有助于完善对ITER及以后的材料性能的预测。