Although tungsten is considered as one of the primary candidates for plasma-facing material (PFM) in future fusion reactors, blistering induced by plasma irradiation adversely affects fusion reactors. To overcome blistering, in this study, we proposed an approach to reduce the blistering by releasing hydrogen or helium (H/He) through the grooved surfaces of PFM. In order to verify the feasibility of this approach and the effectiveness of the transverse release of H/He, the deep grooves as the channel simulants on the tungsten surface were fabricated with different spacing using focused ion beam (FIB). The result of helium irradiation shows that the presence of grooved surfaces can reduce blisters and inhibit the rapid growth of He blisters. In addition, the blistering reduced significantly with decreasing groove spacing, especially when the groove spacing is less than 2 µm. In addition, He-induced blistering shows obvious crystal orientation dependence, and the (001) surface shows the most serious radiation damage.

尽管钨被认为是未来聚变反应堆中面向等离子材料（PFM）的主要候选材料之一，但等离子辐射引起的起泡会对聚变反应堆产生不利影响。为了克服起泡现象，在本研究中，我们提出了一种通过PFM沟槽表面释放氢或氦（H / He）来减少起泡现象的方法。为了验证该方法的可行性和横向释放H / He的有效性，使用聚焦离子束（FIB）在不同间距下制作了深槽作为钨表面上的通道模拟物。氦气辐照的结果表明，开槽表面的存在可以减少水泡并抑制He水泡的快速生长。另外，随着凹槽间距的减小，起泡现象也明显减少，特别是当凹槽间距小于2 µm时。此外，He引起的起泡显示出明显的晶体取向依赖性，（001）表面显示出最严重的辐射损伤。