核级FeCrAl包壳材料研究进展

摘要：日本福岛核电站泄漏事故暴露了锆合金易与水蒸气反应造成爆炸的缺陷，又将人们的视线拉回了各项性能较为均衡的FeCrAl合金。FeCrAl合金较锆合金具有更好的耐腐蚀性能，更能满足核反应堆高温水蒸气环境下的工作条件。为进一步保障核反应堆安全性，各国学者对FeCrAl合金的性能进行了大量研究。基于此，综述了FeCrAl合金腐蚀机制及其在高温蒸汽和高温水环境中的腐蚀行为；探讨了合金元素（稀土、Ti、Zr、Nb和Mo）、变形和热处理对合金力学性能的影响；总结了FeCrAl合金辐照性能和焊接性能的研究进展。最后指出了核级FeCrAl合金在研究中存在的不足及未来重点发展方向，为今后其他学者在该领域的研究提供参考。

Research progress of nuclear FeCrAl cladding materials

Abstract： The leakage accident at the Fukushima nuclear power plant in Japan exposed the defect that zirconium alloy easily reacts with water vapor to cause an explosion, and distracting people's attention back to the FeCrAl alloy, which has relatively balanced properties. FeCrAl alloy has better corrosion resistance than zirconium alloy, and can better meet the working conditions of nuclear reactor under high temperature water vapor environment. In order to further ensure the safety of nuclear reactors, scholars from various countries had conducted a lot of research on the performance of FeCrAl alloy. For that reason, the corrosion mechanism of FeCrAl alloy and its corrosion behavior in high temperature steam and high temperature water environment were reviewed, and the effect of alloying elements (rare earth, Ti, Zr, Nb, and Mo), deformation and heat treatment system on the mechanical properties of the alloy was discussed; the research progress of the radiation and welding performance of FeCrAl alloy was summarized. The deficiencies in the research of nuclear grade FeCrAl alloys and the key development directions in the future were pointed out, which would provide references for other scholars in the field of research in the future.