U-10Mo合金燃料的辐照脆化和强度退化机理研究
批准号:
12102094
项目类别:
青年科学基金项目(C类)
资助金额:
30.0 万元
负责人:
简晓彬
依托单位:
学科分类:
极端条件下材料与结构力学
结题年份:
2024
批准年份:
2021
项目状态:
已结题
项目参与者:
简晓彬
中文摘要
U-10Mo/Al单片式燃料元件具有铀密度高、辐照性能稳定等优点,在研究试验堆中具有良好的应用前景。辐照条件下,U-10Mo合金会产生裂变气体,形成气泡,演化为多孔结构。气孔演化会影响材料辐照蠕变和裂变气体肿胀行为,引发材料辐照脆化和强度退化,进而影响燃料元件堆内安全运行。本研究拟针对U-10Mo合金,建立裂变气体肿胀模型和内聚力模型,发展辐照-降温-卸载后四点弯曲断裂行为计算方法,编写定义材料三维本构关系的子程序;对不同辐照条件下U-10Mo合金四点弯曲试样断裂过程进行数值模拟计算,结合实验结果,验证模型、算法和程序的正确性;分析加载历史对U-10Mo合金宏观弯曲强度的影响,揭示辐照脆化和强度退化机理;进一步分析高燃耗下燃料元件堆内失效行为,解释辐照实验现象。本研究可为分析燃料元件辐照热-力耦合行为和评估元件结构完整性提供理论模型和计算手段,支撑燃料元件及其组件的设计和应用。
英文摘要
U-10Mo/Al monolithic fuel plate has promising applications in research and test reactor due to the advantages of high uranium density and stable irradiation performance. Fission gas atoms will be produced during irradiation and form fission gas bubbles, which leads to a porous structure of U-10Mo alloy. Fission gas swelling and irradiation-induced creep behaviors are affected by the evolution of fission gas bubble, which causes the radiation embrittlement and strength degradation. As a result, the safety operation of fuel plates may be affected in irradiation. In this study, fission gas swelling model and a cohesive zone model are established for U-10Mo alloy. The calculation method for fracture behavior of four-point bending testing after irradiation-cooling-unloading is developed. The user-defined subroutines are programmed to define the three-dimensional constitutive relationship of materials. The four-point bending fracture behaviors of U-10Mo alloy are simulated under different irradiation conditions. Comparing simulation results with experimental data, the effectiveness of the models, algorithms and programs is validated. The influence of loading history on the macroscale bending strength is investigated. The mechanisms of radiation embrittlement and strength degradation are revealed. The irradiation-induced failure behavior of fuel plate in high burnup is further analyzed to explain the experimental phenomena. This study can provide theoretical model and calculation method for analyzing the irradiation-induced thermal-mechanical coupling behavior and evaluating structural integrity of fuel plates, and supports the design and application of U-10Mo/Al monolithic fuel plates and their assemblies.
本项目考虑了裂变气体原子行为、晶粒亚晶化效应,含孔U-10Mo合金骨架热膨胀、裂变固体肿胀、辐照蠕变行为,建立了U-10Mo合金辐照等效体积膨胀应变模型,预测了裂变气体肿胀演化规律,和文献试验结果吻合很好,揭示了核燃料辐照蠕变变形为主导的裂变气泡生长机制;完善考虑了辐照-降温过程中各材料的热-力学行为,建立了三维大变形增量本构关系、应力更新算法和一致刚度模量,发展了U-10Mo/Al单片式燃料元件辐照-降温过程热-力耦合行为分析方法,获得了燃料芯体孔隙率、孔压、辐照蠕变等物理量结果,孔隙率结果与文献试验结果吻合很好;建立了含Zr合金防扩散层的四点弯曲试样有限元模型,发展了U-10Mo燃料芯体四点弯曲试验数值计算方法,获得了四点弯曲载荷-位移曲线,与试验结果吻合很好,识别了辐照后U-10Mo合金的宏观等效弹性常数和贫Mo区宏观强度;基于辐照-降温过程中孔隙率结果,以及含孔材料宏观等效杨氏模量模型,识别了辐照后U-10Mo合金骨架材料杨氏模量结果,拟合得到了骨架杨氏模量与裂变密度之间的关系,揭示了U-10Mo骨架材料刚度退化为主导的宏观性能退化机理。基于连续介质损伤理论,发展了考虑塑性功的U-10Mo合金损伤本构关系,建立了考虑微观空洞影响的RVE 模型和拉伸试验有限元计算模型,识别了辐照前U-10Mo合金应力-应变曲线,分析了含孔区域骨架材料对RVE模型宏观应力-应变的影响,揭示了含孔材料骨架强度退化和脆化为主导机制的U-10Mo合金辐照脆化和强度退化机理。基于四点弯曲试验模拟获得的U-10Mo合金贫Mo区宏观强度结果,结合含孔RVE细观模型拉伸试验模拟,识别了辐照后U-10Mo合金骨架材料强度,并建立了其与裂变密度之间的关系。分析了骨架强度和U-10Mo合金辐照蠕变变形之间的相关性。
国内基金
海外基金