水堆燃料元件性能分析及程序FROBA开发  

Analysis of Fuel Rod Behavior and Design of FROBA Code

作　　者：杨震[1] 苏光辉[1,2] 田文喜[1] 秋穗正[1,2] 

机构地区：[1]西安交通大学核科学与技术学院,陕西西安710049 [2]西安交通大学动力工程多相流国家重点实验室,陕西西安710049

出　　处：《原子能科学技术》2012年第5期590-595,共6页Atomic Energy Science and Technology

基　　金：863计划资助项目(2009AA050705);国家自然科学基金资助项目(10905045)

摘　　要：在详细分析芯块和包壳的辐照行为的基础上,开发了燃料元件性能分析程序FROBA,并对燃料元件的热工-机械-材料特性进行模拟分析,计算得到不同燃耗深度下燃料元件的温度、应变特性。通过与美国爱达荷国家实验室的软件计算结果进行对比,验证本工作开发程序的准确性。结果表明:在芯块和包壳接触前,芯块温度先上升,密实化消失后温度逐渐下降;接触后芯块温度会再次上升。The temperature and strain profile of pellet and cladding were studied by developing a thermomechanic coupling code FROBA,which was based on analyzing fuel rod behavior theoretically during irradiation.Based on the analysis of results under different operating conditions,a numerical method for calculating fuel rod behavior was obtained,which could be used for the analysis of fuel component under operational conditions of nuclear reactors.The reliability of the code was also proved by comparing the results derived from Idaho National Laboratory software.The results show that the fuel temperature rises before irradiation.Once the densification is complete,the fuel temperature drops.After the gap closure occurs,the temperature gradually rises again.

关 键 词：燃料元件 程序开发 数值计算方法 

分 类 号：TL349[核科学技术—核技术及应用]