反应堆核热耦合松耦合数值仿真研究综述

A Review of Numerical Simulation Research of Neutronic-Thermal Loosely Coupling in Reactor

在反应堆运行过程中,包含多个性质不同却相互联系的物理现象,涉及反应堆物理、热工水力、材料、系统控制等专业。本文主要探讨堆芯反应堆物理与热工水力间的相互作用,且主要关注对反应堆安全运行具有重要意义的耦合现象,对核热耦合的松耦合数值仿真研究进展进行广泛综述。本文先简要介绍核热耦合的原理方法和主流数值仿真程序,随后依据仿真程序自身特点进行科学分类,最后着重研究四类松耦合数值仿真方法现阶段的实际应用情况,给出了典型算例,并分析其计算效果及实用价值。

In the process of reactor operation,there are many physical phenomena with different properties but interrelated with each other,involving reactor physics,thermal hydraulics,materials,system control and other disciplines.This paper mainly discusses the interaction between reactor physics and thermal hydraulics,and the coupling phenomenon which has great significance to the safe operation to the reactor.This paper briefly introduces the principles and methods of neutronic-thermal coupling and mainstream numerical simulation programs,then makes scientific classifications according to the characteristics of the simulation programs.Finally,it focuses on the practical application of the four types of loosely coupled numerical simulation methods at the present stage,which gives a typical example,and analyzes its calculation effect and practical value.