核用钢高温力学性能及本构模型综述  

REVIEW OF HIGH-TEMPERATURE MECHANICAL PROPERTIES AND CONSTITUTIVE MODEL OF NUCLEAR STEELS

作　　者：莫亚飞[1] 杜柔 马寒松 刘小明[2] MO Yafei;DU Rou;Ma Hansong;LIU Xiaoming(China Institute of Atomic Energy,Beijing 102413,China;Institute of Mechanics,Chinese Academy of Sciences,Beijing 100190,China)

机构地区：[1]中国原子能科学研究院,北京102413 [2]中国科学院力学研究所,北京100190

出　　处：《力学与实践》2022年第3期564-575,共12页Mechanics in Engineering

基　　金：国家自然科学基金(11772334,11890681,12022210,12032001,12125202)资助项目。

摘　　要：为发展适用于结构完整性评定的高温非弹本构模型,本文对316奥氏体不锈钢和9Cr-1Mo钢高温力学性能及非弹本构模型进行了综述。通过比较单轴拉伸、应变控制循环、蠕变以及塑变-蠕变交互性能,展示了两类核用钢高温力学行为的异同。其中,温度、加载速率、应力水平等对核用钢高温力学性能均有影响。另外,综合评价了用于描述核用钢高温力学性能的两类非弹本构模型,并对模型发展趋势进行了讨论。对核用钢高温力学性能综合准确描述有助于解决工程中核反应堆结构完整评价问题。To develop a high-temperature inelastic constitutive model suitable for structural integrity assessment, the high temperature mechanical properties of 316 austenitic stainless steel and 9Cr-1Mo steel are reviewed in this paper. By comparing the uniaxial tensile, strain-controlled cyclic, creep and plastic-creep interaction properties, the similarities and differences of the high-temperature mechanical behaviors of the two types of nuclear steels are demonstrated. Also, temperature, loading rate, stress level etc. have an influence on the above mentioned mechanical properties. In addition, two types of high-temperature constitutive models are comprehensively evaluated, and the development trend of models is discussed. The comprehensive description of the high-temperature mechanical properties of nuclear steel is helpful for the complete evaluation of nuclear reactor structure.

关 键 词：高温力学性能 316奥氏体不锈钢 9CR-1MO钢 非弹本构模型 

分 类 号：TB126[理学—工程力学]