反应堆严重事故分析程序研发进展

Development of Reactor Severe Accident Analysis Code

压水堆严重事故是一个多组分、多相态、多物理场的复杂耦合过程,开发压水堆严重事故一体化分析程序可为我国核电厂严重事故预防缓解策略制定及安全审评提供技术支持。本文介绍反应堆严重事故分析程序研发的进展情况,包括压水堆严重事故一体化分析程序中堆芯早期行为及反应堆系统热工水力分析模块、压力容器内堆芯熔化晚期熔融物行为分析模块和安全壳内严重事故进程分析模块的开发进展,搭建科研云平台系统,为有序、高效且具有延续性的研究奠定基础,提供保障。

The severe accident of a Pressurized Water Reactor(PWR)is a complex coupling process of multicomponent,multi-phase and multi-physical fields.The development of integrated analysis code for PWR severe accident can provide technical support for the formulation of accident prevention and mitigation strategies and safety review of nuclear power plants.This paper introduces the progress of the research and development project of the nuclear reactor severe accident analysis code,including modules of early core behavior and thermal-hydraulic analysis,late core behavior and severe accident process in containment.The scientific research cloud platform has been built,which enables the team to develop code in an orderly,efficient and continuous manner,which could ensure the smooth implementation of the project.