辐照对堆用锆合金腐蚀行为的影响  

EFFECTS OF IRRADIATION IN NUCLEAR REACTORS ON CORROSION BEHAVIOR OF ZIRCALOYS

作　　者：白新德[1] 王社管[1] 何敬浩[1] 陈鹤鸣[1] 范毓殿[1] 

机构地区：[1]清华大学材料科学与工程系

出　　处：《核科学与工程》1996年第3期243-249,255,共8页Nuclear Science and Engineering

基　　金：国家"八.五"攻关课题

摘　　要：综述了堆用锆合金辐照腐蚀研究的进展，包括概况、机理和模型，在ＰＷＲ运行环境下，辐照确实增强了锆合金的腐蚀，其增强因子大于２－３倍。为了降低运行成本而提高卸料燃耗和提高运行温度，使得辐照腐蚀加剧；从不同侧面提出了辐照增强腐蚀的机理和模型，包括不同射线与材料的相互作用机理，氧化膜中缺陷的形成，组织结构的变化，电导的变化和脆化，金属的辐照损伤，中间相的辐照分解，水的辐照分解和辐照对反应活化能的影响等；近年来关于中间相在不同射线下辐照分解的研究较为活跃，其进展结果为从机理上建立辐照损伤参量与辐照腐蚀性能参量的关系提供了依据。The research results of the irradiation corrosion of zircaloys in nuclear reactors, including the general survey, the mechanism and models, are described. The authors POint out especially: 1 ) under the PWR operation environment, irradiation enhances the corrosion of zircaloys with a enhancement factor not less than 2 - 3. Recently, the effort to increase the fuel burnup rate and operation temperature in PWR entails a much more serious irradiation corrosion of zircaloys; 2 ) many authors have proPOsed some kinds of irradiation enhancement corrosion mechanism and models, including the interaction between zircaloys and different irradiation particles, formation of the defects, phase transformation, change of eletronic conductivity and brittlization in oxide films of zircaloys irradiation damage in zircaloys, decomposition of precipitates in it, decomPOsition of water, and the contribution of irradiation to the reaction free energy, etc., but, hitherto, there is not a satisfactory systematic theory and model;3)there appears an intensive study for the decomPOsition of precipitates under different irradiation particles, and the research results are valuable to build the most imPOrtant relationship, on mechanism level, between the irrdiation parameters and those of the corrosion properties.

关 键 词：辐照腐蚀 锆合金 中间相 反应堆 

分 类 号：TL375[核科学技术—核技术及应用]