中子辐照对Cr涂层锆合金力学性能的影响  

Influence of Neutron Irradiation on Mechanical Properties of Cr-coated Zirconium Alloy

作　　者：吴亚贞[1] 席航[1] 李国云[1] 刘晓松[1] 张海生[1] 孙凯[1] 宁知恩 方忠强[1] 刘莎莎 Wu Yazhen;Xi Hang;Li Guoyun;Liu Xiaosong;Zhang Haisheng;Sun Kai;Ning Zhien;Fang Zhongqiang;Liu Shasha(Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院,成都610213

出　　处：《核动力工程》2023年第2期116-121,共6页Nuclear Power Engineering

基　　金：国防科工局核能开发项目(K301007015)。

摘　　要：为研究中子辐照对Cr涂层锆合金力学性能的影响,获得Cr涂层锆合金的辐照性能数据,本文针对多弧离子镀技术制备的Cr涂层锆合金开展了中子辐照考验,通过拉伸试验过程实时观测试样力学行为变化并对试验后断口微观形貌进行分析,研究了辐照后Cr涂层锆合金的力学性能以及涂层与基体的结合能力。结果表明:中子辐照导致Cr涂层锆合金的抗拉强度和屈服强度升高,断后伸长率下降,表现出与商用锆合金相似的辐照强化效应。同时Cr涂层与无涂层锆合金相比,其屈服强度和抗拉强度升高但塑性变形能力降低。另一方面,Cr涂层在拉伸变形量较大时产生环向裂纹,但未从基体表面剥落,中子辐照未对涂层结合强度产生明显的影响,受力过程中涂层仍保持了完整性。In order to study the influence of neutron irradiation on the mechanical properties of Cr-coated zirconium alloy,a neutron irradiation test is carried out in this paper for the Cr-coated zirconium alloy prepared by multi-arc ion plating technology.The mechanical properties were conducted by in situ tensile tests and the coating adhesion was analyzed by micron morphology characterization.Results show that Cr coating zircaloy has a similar irradiation effect with commercial zircaloy cladding.Compared with uncoated zircaloy,Cr coating shows that the yield strength and tensile strength increased but percentage elongation after fracture decreased.The Cr coating shows cracks till a large tensile strain without peeling off before rupture.The Cr coating exhibits good mechanical properties and excellent adhesion with Zircaloy Tubes.

关 键 词：耐事故燃料包壳 Cr涂层 力学性能 中子辐照 

分 类 号：TL34[核科学技术—核技术及应用]