Thirteen austenitic stainless steels, nickel-base alloys, and ferritic alloys were irradiated using 2 MeV protons at 360 °C to a damage level of 2.5 displacements per atom (dpa). Comprehensive microstructural characterization was performed for irradiation-induced features, including dislocation loops, voids, precipitates, and radiation induced segregation (RIS). Dislocation loops formed in all alloys except 14YWT, while voids were observed in alloys 316 L, 310, C22, and 14YWT. Irradiation-induced formation of γ′ precipitates was observed in alloys 316 L, 310, 800, and 690; the irradiation-enhanced, long-range ordered Ni₂Cr phase (Pt₂Mo-type) was observed in alloys 690, C22, 625, 625Plus, 625DA, and 725; and G-phase was observed in alloy T92. No irradiation-induced precipitates were observed in alloys X750, 718 or 14YWT. Precipitation of the γ′ phase can be understood through segregation and clustering of Si, Al, and Ti. Overall, austenitic stainless steels are generally susceptible to irradiation damage in the form of loops, voids, precipitates, and RIS. Ni-base alloys have this same type of dislocation loops and RIS behaviors but are more resistant to void swelling. Ferritic alloys showed better resistance to loop formation, void swelling and irradiation-induced precipitation. From the degree of irradiation-induced microstructural change, alloy T92 was identified as the most radiation resistant among these alloys.

在360°C下使用2 MeV质子辐照了13种奥氏体不锈钢，镍基合金和铁素体合金，损伤程度为每原子2.5位移（dpa）。对辐射诱导的特征进行了全面的微结构表征，包括位错环，空隙，沉淀和辐射诱导的偏析（RIS）。除14YWT以外的所有合金中都形成了位错环，而在316L，310，C22和14YWT合金中观察到了空隙。在合金316 L，310、800和690中观察到了辐射诱导的γ'沉淀的形成；增强辐射的远距离有序Ni ₂ Cr相（Pt ₂在690，C22、625、625Plus，625DA和725合金中观察到Mo型）; 在T92合金中观察到G相。在X750、718或14YWT合金中未观察到辐照引起的沉淀。可以通过Si，Al和Ti的聚集和聚集来理解γ'相的析出。总体而言，奥氏体不锈钢通常容易受到环，空隙，沉淀物和RIS形式的辐射损害。镍基合金具有相同类型的位错环和RIS行为，但更能抵抗空隙膨胀。铁素体合金表现出更好的抗回路形成，空隙膨胀和辐射诱导的沉淀的能力。从辐照引起的微观结构变化的程度来看，T92合金被认为是这些合金中最耐辐射的。