摘要
为保障核电厂运行的安全性与可靠性,需准确模拟和评估燃料棒在典型工况下的热工力学行为及其关键安全参数的不确定性影响。本研究开发了燃料棒性能分析程序BEARs,并基于高斯积分法构建了四阶多项式混沌代理模型,在典型稳态工况下计算了燃料棒中心线温度、芯块表面温度、包壳内表面温度、芯块-包壳间隙距离和气腔压力等关键安全参数。采用敏感性及不确定性分析方法,选取燃料棒线功率缩放因子、燃料热导率缩放因子、包壳热导率缩放因子等12个不确定性输入参数,评估关键安全参数的概率分布。代理模型有效降低了时间计算成本,预测均值误差小于1%,标准差误差小于4%。分析表明,在反应堆升功率初期,燃料热导率缩放因子、燃料棒线功率缩放因子及燃料热膨胀缩放因子是影响燃料棒安全性能的主要不确定性因素。本研究可为燃料设计优化及安全评估提供参考。
To ensure the safety and reliability of nuclear power plant operations,it is essential to accurately simulate and evaluate the thermomechanical behavior of fuel rods under typical conditions,as well as to quantify the uncertainties in key safety parameters.In this study,a fuel rod performance analysis code BEARs was developed,and a fourth-order polynomial chaos surrogate model was constructed based on the Gaussian integration method.Under typical steady-state conditions,key safety parameters such as fuel rod centerline temperature,pellet surface temperature,cladding inner surface temperature,pellet-cladding gap distance,and plenum pressure were computed.Using sensitivity and uncertainty analysis methods,12 uncertain input parameters—such as fuel rod linear power scaling factor,fuel thermal conductivity scaling factor,and cladding thermal conductivity scaling factor—were selected to evaluate the probability distributions of key safety parameters.The surrogate model effectively reduced computational time costs,with mean prediction errors below 1%and standard deviation errors below 4%.The results indicate that the fuel thermal conductivity scaling factor,fuel rod linear power scaling factor,and fuel thermal expansion scaling factor are the dominant uncertainties impacting fuel rod safety performance during the initial reactor power ramp.This study provides insights for fuel design optimization and safety assessment.
作者
涂兴东
熊骄阳
郭张鹏
王升飞
卓卫乾
Tu Xingdong;Xiong Jiaoyang;Guo Zhangpeng;Wang Shengfei;Zhuo Weiqian(School of Nuclear Science and Engineering,North China Electric Power University,Beijing,102413,China;State Key Laboratory of Advanced Nuclear Energy Technology,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
北大核心
2025年第S2期75-83,共9页
Nuclear Power Engineering
基金
国家自然科学基金(12275084)。
关键词
燃料棒性能分析
多物理场耦合
敏感性分析
不确定性分析
Fuel rod performance analysis
Multiphysics coupling
Sensitivity analysis
Uncertainty analysis
