Abstract Fusion reactors will require specially engineered structural materials that will simultaneously satisfy the harsh conditions, such as high thermomechanical stresses, high heat loads, and severe radiation damage, without compromising on safety considerations. The simulation of 14.7-MeV protons and 3.6-MeV α-particles irradiation processing using different fusion structural materials, such as graphite, titanium, zirconium, molybdenum, tantalum, and tungsten, was studied. The open-source three-dimensional computer simulation code SRIM (2013 version) was used to determine the protons and α-particles penetrability into the target material as well as the range dependence of the protons and α-particles energies. The protons and α-particles distribution range and their trajectories in the target materials were determined. The effect of the target materials’ atomic mass on the 14.7-MeV protons and 3.6-MeV α-particles penetration range was determined. Also, the phonons and ionization of the target materials induced by these irradiated particles were studied.

中文翻译：

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14.7-MeV 质子和 3.6-MeV α 粒子对聚变结构材料的影响

摘要 聚变反应堆需要经过特殊设计的结构材料，既能满足高热机械应力、高热负荷和严重辐射损伤等严酷条件，又不影响安全考虑。研究了使用石墨、钛、锆、钼、钽和钨等不同融合结构材料对 14.7-MeV 质子和 3.6-MeV α-粒子辐照处理的模拟。开源三维计算机模拟代码SRIM（2013版）用于确定质子和α粒子对目标材料的穿透性以及质子和α粒子能量的范围依赖性。确定了质子和 α 粒子的分布范围及其在目标材料中的轨迹。确定了目标材料的原子质量对 14.7-MeV 质子和 3.6-MeV α-粒子穿透范围的影响。此外，研究了由这些辐射粒子引起的目标材料的声子和电离。