Nuclear fusion plasma-facing materials (PFM) will suffer from irradiation, leading to significant changes in the material properties. This study investigates the impact of displacement damage on the deuterium retention near room temperature.

ITER grade tungsten, Eurofer-97, and HiperFer 17Cr5 steel samples are irradiated with a tandem accelerator with ~3 MeV protons at currents of 100–600 nA on 250–550 µm spots at 320±10 K. In total 33 spots from 0 to 0.9 displacements per atom (DPA) at 0–4 µm depth are irradiated on 5 samples. After irradiation, the samples are exposed to D₂ plasmas with a peak ion-flux of 2.1 × 10²¹ D/m²s for 4 h at <420 K in PSI-2. Lastly, D retention is measured via ³He nuclear reaction analysis with a spot size of 200 µm up to 4.5 µm depth.

The long-term D retention in both W and steel increases with DPA with a saturation starting around 0.2 DPA. Retention in W increased by a factor 12 with up to 3.2 at.% D, while in steel increases up to 180 times with up to 0.08 at.% D were observed. The results highlight the importance of using steels also in PFMs. Compatibility of the results with heavy ion irradiations boosts the confidence in inter-comparability between different ion types, but also between ions and neutrons.

面向核聚变等离子体的材料（PFM）会受到辐射的影响，从而导致材料性能发生重大变化。这项研究调查了位移损伤对室温附近氘保留的影响。

用具有〜3 MeV质子串联加速器的ITER级钨，Eurofer-97和HiperFer 17Cr5钢样品以100±600 nA的电流在320±10 K的250-550 µm点上辐照。从0到0，共33点。在5个样品上辐照0–4 µm深度的0.9个位移/原子（DPA）。辐照后，样品在PSI-2中以<420 K的峰值离子通量通过2.1×10 ²¹ D /m²s的D ₂等离子体暴露4小时。最后，通过³ He核反应分析，以200 µm到4.5 µm深度的斑点尺寸测量D保留。

W和钢中的长期D保留量随DPA的增加而增加，饱和度从0.2 DPA开始。W的保留率提高了12倍，D高达3.2 at。％，而钢的保留率提高了180倍，D高达0.08 at。％。结果强调了在PFM中也使用钢材的重要性。结果与重离子辐照的兼容性提高了不同离子类型之间以及离子与中子之间相互可比性的信心。