基于HFR的核动力装置非能动系统敏感性分析方法研究

敏感性分析应用于反应堆非能动系统热工水力过程的不确定性分析和可靠性分析，能够定量识别对系统热工水力行为具有重要影响的不确定性输入参数。基于混合随机均衡-傅里叶幅度敏感性测试（HFR）方法，以某型核动力装置非能动余热排出试验系统作为算例进行全局敏感性分析研究，仿真结果证明了HFR方法的可行性与正确性。敏感性分析给出了系统输入参数重要度随时间的变化规律以及系统稳定运行时输入参数的重要度排序，分析结果有助于指导系统的设计优化及运行管理。 

Research on Sensitivity Analysis of Passive System for Nuclear Power Plants Based on HFR

Sensitivity analysis is applied to uncertainty analysis and reliability evaluation of the thermal-hydraulic process for reactor passive system, which can quantitatively identify uncertainty input parameters that have important influence on system’s thermal-hydraulic behavior. Based on hybrid of random balance designs and Fourier amplitudes sensitivity test (HFR), the passive residual heat removal experimental system of a nuclear power plant is used as an example to carry out?the?global sensitivity analysis. The applicability and accuracy of HFR method are demonstrated by simulation results. The change rule of parameter importance with time and the parameter importance ranking when the system is running stably are given by sensitivity analysis, which help to guide passive system’s design optimization and operation management.