摘要
目前使用最广泛和成熟的压水堆包壳材料是Zircaloy-2和Zircaloy-4。然而随着核动力反应堆技术朝着提高燃料燃耗和降低燃料循环成本、提高反应堆热效率和提高安全可靠性的方向发展,对关键核心部件燃料元件包壳材料锆合金的性能提出了更高的要求,包壳耐腐蚀性能、吸氢性能、力学性能及辐照尺寸稳定性等。总而言之,包壳材料是核反应堆重要的组成部分,最终包壳材料在核反应堆运行过程中性能的变化情况决定了反应堆的使用寿命及安全可靠性。因此,需要深入研究压水堆堆内行为的演变规律能为更优异综合性能的新锆合金设计、加工工艺优化等提供新的思路。本文综述了近年来国内外对目前压水堆锆合金包壳材料(Zircaloy-2和Zircaloy-4)的研究概况,即基于高温高压下包壳材料在核反应堆中受到冷却剂冲刷(析氢腐蚀和吸氧腐蚀)和辐照蠕变,分析和总结了对包壳材料性能退降的原因。此外,展望了未来研究的方向。
The most widely used and proven pressurized water reactor cladding materials are Zircaloy-2 and Zircaloy-4 until now.With the development of nuclear power reactor technology in the direction of improving fuel consumption and reducing fuel cycle cost,improving reactor thermal efficiency and improving safety and reliability,higher requirements are placed on the performance of zirconium alloys,which are key component fuel element cladding materials,including the properties of corrosion resistance,hydrogen absorption,mechanics and irradiation dimensional stability.In summary,the cladding material is an important component of the nuclear reactor.The perfor-mance of the final cladding material during the operation of the nuclear reactor determines the service life and safety reliability of the reactor.Therefore,it is necessary to study in depth the evolution of the behavior of the PWR reactor to provide new ideas for the design and processing optimization of new zirconium alloys with better comprehensive performance.In this paper,the research progress of the performance degradation of zirconium alloy cladding materials(Zircaloy-2 and Zircaloy-4)in PWR at home and abroad is reviewed.This is based on cladding materials eroded by coolant(hydrogen separation and oxidation)and irradiation creep in nuclear reactor at high temperature and pressure.The reason and mechanism of property degradation of cladding materials are analyzed and summarized.Finally,the future research direction is also forecasted.
出处
《材料科学》
CAS
2019年第9期861-871,共11页
Material Sciences
基金
国家自然科学基金资助项目(51601185)
国防基础科研计划资助(JCKY2017201C016)
国家重点研发计划资助项目(2016YFB07001)
中国先进核电标准体系研究(第二阶段,2017ZX06004001)。
