容错事故燃料包壳用FeCrAl合金的研究进展EI北大核心CSCD

福岛事故后,人们迫切需要开发相应的燃料包壳材料以忍受严重事故发生时的极端工况,从而提高核电站的事故承受能力。尽管FeCrAl合金的宏观中子吸收截面要远远高于锆合金,但其在严重事故下良好的耐腐蚀性、优越的高温力学性能及抗辐照损伤能力,使其被列为事故容错燃料包壳的候选材料之一。然而,现有FeCrAl合金难以满足核电站用材料的要求,因此需对其进行优化,以获得更佳的性能。本文系统总结了近年来关于优化后FeCrAl合金的腐蚀行为、力学性能、辐照后的微观结构及力学性能变化、焊接性及加工性等方面的研究进展,分析了FeCrAl合金的高温腐蚀机理以及引起FeCrAl合金微观结构及力学性能变化的主要原因,提出了FeCrAl合金在高温腐蚀、焊接性以及加工性等过程中存在的主要问题以及未来的研究方向。

Research progress in FeCrAl alloys for accident-tolerant fuel cladding

After the Fukushima accident, there is an urgent need to develop fuel cladding materials to meet the performance requirements of materials under severe accident conditions, and therefore greatly improving the accident tolerance of nuclear power plants. Although the macroscopic thermal neutron absorption capture cross-section of the FeCrAl alloy is much higher than that of zirconium alloy, however, its good corrosion resistance, high temperature mechanical properties and radiation damage resistance in severe accident conditions make it become a candidate material of accident-tolerant fuel cladding. Currently, the performance of various industrial FeCrAl alloys can not meet the requirements of materials for nuclear power plants. Therefore, the FeCrAl alloy needs to be optimized in order to obtain a better performance. The research progress of corrosion behavior, mechanical properties, microstructural evolution and mechanical properties under irradiation, weldability and processability of FeCrAl alloys are summarized systematically. Meanwhile, the corrosion mechanism at high temperatures and the reasons for the change of microstructure and mechanical properties of FeCrAl alloy are analyzed. Besides, the main problems of FeCrAl alloy of high temperature corrosion behavior, weldability, workability and the future research directions are proposed.