核燃料包壳锆合金表面吸氢开裂行为的研究进展  

Review on Hydrogen Absorption Cracking Behavior of Zirconium Alloy Surface of Nuclear Fuel Cladding

作　　者：石刘洋 邱长军[1] 刘豪 SHI Liuyang;QIU Changjun;LIU Hao(School of Mechanical Engineering,University of South China,Hengyang 421001,China)

机构地区：[1]南华大学机械工程学院,湖南衡阳421001

出　　处：《机械工程师》2022年第3期47-48,51,共3页Mechanical Engineer

基　　金：衡阳市产学研结合专项(2019jhzx062)。

摘　　要：锆(Zr)及其合金因其在高压/高温水环境中的力学和化学性能、高剂量中子辐射下的结构稳定性和中子透明度,而被广泛用于核燃料包壳材料及其他核反应堆的重要结构材料。福岛核事故后,锆合金的腐蚀和吸氢行为成为耐事故核燃料包壳材料的重点研究方向之一。文中概述了锆合金氢化物的形成,并综述了3个因素对氢在锆合金中固溶度的影响,以及锆合金中氢化物的最新研究进展。最后指出了当前研究中所遇到的一些问题,展望了锆合金吸氢开裂的发展方向。Zirconium(Zr)and its alloys are extensively used in nuclear fuel cladding materials and other important structural materials because of their combination of mechanical and chemical properties in high pressure/high temperature aqueous environment,structural stability under high doses of neutron radiation,and neutron transparency.After the Fukushima nuclear accident,the corrosion and hydrogen absorption behavior of zirconium alloys became one of the key research directions for accident-resistant nuclear fuel cladding materials.The formation of zirconium alloy hydrides is summarized.Secondly,the influence of three factors on the solid solubility of hydrogen in zirconium alloys,and the latest research progress of hydrides in zirconium alloys are reviewed.Finally,some problems encountered in the current research are pointed out,and the development direction of hydrogen absorption cracking of zirconium alloy is prospected.

关 键 词：锆合金 吸氢开裂 吸氢机制 极限固溶度 改善方法 

分 类 号：TG174.4[金属学及工艺—金属表面处理]