High entropy alloys (HEAs) have been considered for applications in nuclear reactors due to their promising mechanical properties, corrosion and radiation resistance. It has been suggested that sluggish diffusion kinetics and lattice distortion of HEAs can enhance the annihilation of irradiation-induced defects, giving rise to a higher degree of tolerance to irradiation damage. In order to understand the irradiation effects in HEAs and to demonstrate their potential advantages over conventional austenitic stainless steels (SS), we performed in-situ ion irradiation experiments with 1 MeV krypton at 300 °C on two HEAs and a 316H SS under an identical irradiation condition. The irradiation introduced a high density of dislocation loops in all materials, and the microstructural evolution as a function of dose was similar for HEAs and 316H SS. Nanoindentation tests showed that the degree of irradiation hardening was also comparable between them. The similar microstructural evolution and irradiation hardening behavior between the HEAs and 316H indicate that, at low temperatures (≤300 °C), the irradiation damage of fcc alloys is not sensitive to compositional variation and configurational entropy.

高熵合金（HEA）由于其有希望的机械性能，耐腐蚀性和抗辐射性已被考虑用于核反应堆。已经提出，HEA的缓慢扩散动力学和晶格畸变可以增强辐射诱发的缺陷的an灭，从而提高了对辐射损伤的耐受性。为了了解HEA中的辐照效应并证明其相对于传统奥氏体不锈钢（SS）的潜在优势，我们进行了现场测试在相同的辐射条件下，在两个HEA和316H SS上，在300°C下用1 MeV rypto进行离子辐射实验。辐照在所有材料中引入了高密度的位错环，HEA和316H SS的微观结构随剂量的变化是相似的。纳米压痕测试表明，辐射硬化程度在它们之间也相当。HEA和316H之间相似的显微组织演变和辐照硬化行为表明，在低温（≤300°C）下，fcc合金的辐照损伤对成分变化和构型熵不敏感。