锆合金辐照蠕变和生长的宏介观模型研究进展

锆合金作为核反应堆堆芯的主要结构材料之一，在服役过程中会发生辐照蠕变和生长行为，严重影响其使用可靠性。预测锆合金的辐照蠕变和生长是保障反应堆安全运行的关键。本文聚焦于两类锆合金构件，包括压水堆用锆合金包壳管及重水堆用Zr-2.5Nb压力管，分别从宏介观尺度详细综述了其辐照变形预测模型。针对适用于包壳管的宏观经验模型及介观力学模型，分别描述了两类模型的特征，重点介绍了介观力学模型的研究现状及最新进展，并对其未来的发展方向提出建议；针对适用于压力管的宏观经验模型，包括加拿大CANDU压力管辐照变形计算方程(简称C6方程)及秦山重水堆压力管辐照变形计算方程(简称秦山方程)，分别描述了两类方程的具体形式，并介绍了C6方程国产化的进展。

Research Progress in Macro-mesoscopic Model of Irradiation Creep and Growth of Zirconium Alloy

Zirconium alloys are extensively used for structural components in nuclear reactors. Under reactor operating conditions, irradiation creep and growth of zirconium alloys severely affect its reliability. Predicting the irradiation creep and growth behavior of zirconium alloys is crucial for the safe operation of the reactor. The predictive models of irradiation deformation for zirconium alloys from the macro-mesoscopic scale were reviewed, mainly focusing on two types of zirconium alloy components, including cladding tubes for pressurized water reactors and Zr-2.5Nb pressure tubes for heavy water reactors. For the cladding tube, the characteristics of the macro empirical model and the mesoscopic mechanics model were described, with an emphasis on the research status and the latest progress of the mesoscopic mechanics model, as well as putting forwards the suggestions for its future development. For the pressure tubes, the specific forms of macro-empirical models were described, including the prediction equation for Canadian CANDU pressure tube (C6 equation) and Qinshan CANDU pressure tube (Qinshan equation), and the progress of the localization of C6 equation was also introduced.