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反应堆多物理场耦合计算中的不确定性研究概述
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Abstract:
核反应堆是一个由粒子场、温度场、流体场、应力场等多个物理过程相互紧密耦合的系统，先进核反应堆数值模拟需要解决多尺度、大规模、多物理场耦合问题。近年来，随着计算机技术和现代数值仿真技术的进步，使得通过多物理场、多尺度等耦合框架实现对反应堆综合性能的大规模数值模拟成为可能，数值反应堆乃至反应堆数字孪生系统成为数值模拟的总体目标。随着最佳估算加不确定性分析方法的推广，不确定性分析成为核反应堆设计和安全分析的重要组成部分。相比起针对单一程序或单一物理场的不确定性分析，对于多物理场耦合计算的不确定性分析则更为复杂，除了各个物理场模拟本身的不确定性外，还必须考虑程序耦合过程中引入的不确定性，该方面的研究尚不够深入。本文从单物理场计算程序的不确定性源及其分析方法出发，对目前已开展的耦合程序计算不确定性分析相关工作进行了总结和阐述，并对多物理场耦合计算中的混合不确定性研究进行了初步分析。
Nuclear reactor is a system which is closely coupled with many physical processes such as particle field, temperature field, flow field, and stress field. The numerical simulation of advanced nuclear reactor needs to solve the problems of multi-scale, large-scale and multi-physical field coupling. In recent years, with the progress of computer technology and modern numerical simulation technology, it is possible to realize large-scale numerical simulation of comprehensive reactor performance through multi-physical field and multi-scale coupling framework, numerical reactor and even reactor digital twin system become the overall target of numerical simulation. With the popularization of the method of best estimate plus uncertainty analysis, uncertainty analysis has become an important part of nuclear reactor design and safety analysis. Compared with the uncertainty analysis for a single code or a single physical field, the uncertainty analysis for the multi-physical field coupling calculation is more complex. In addition to the uncertainty of each physical field simulation itself, the uncertainty caused by the code coupling process must be considered, which has not been studied deeply enough. Based on the uncertainty sources and analysis methods of single physical field computing code, this paper summarizes and expounds the existing work on the uncertainty analysis of coupling codes, and makes a preliminary analysis on the mixed uncertainty research of multi-physics coupling calculation.
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