抗辐照材料研究进展

Progress of Irradiation-Resistance Materials

摘要:

用于核反应堆的新候选材料研发是一项重要任务。由于反应堆环境恶劣，堆芯材料在高温下应具有良好的综合性能，如良好的强度、延展性、耐腐蚀性能和耐辐照性能等。此外，还应考虑低中子吸收横截面和中子活化。典型的空间核反应堆核心材料的选择主要由工作温度决定。随着反应堆设计工作温度的升高，一般以316不锈钢、镍基高温合金、氧化物分散强化（ODS）钢、铌合金、难熔金属和SiC陶瓷的顺序来选择设计堆芯材料。此外，高熵合金已经引起核领域的广泛关注。本文综述了以上不同材料体系在辐照过程中的力学性能演变，为进一步提升抗辐照性能提供研究指导。

Abstract:

Developing novel materials for nuclear reactors is a crucial research task. Due to the harsh conditions in the reactors, core materials must possess exceptional high-temperature properties, including high strength, ductility, corrosion resistance, and irradiation resistance. Additionally, the low neutron absorption cross-section and the neutron activation are also important considerations. It is widely acknowledged that the choice of core material for a typical space nuclear reactor is primarily determined by the operation temperature. Generally, with increasing the designed operation temperature of reactor, 316 stainless steel, nickel-based superalloys, oxide-dispersion-strengthened (ODS) steel, refractory metals, and SiC ceramics are preferred in order. Besides, the high entropy alloys attract extensive attention for nuclear applications. This review summaries the evolution of mechanical properties of different material systems during irradiation process, providing guidance for the further research in irradiation resistance.