核反应堆热工水力多尺度耦合模拟初步研究

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Preliminary Research on Nuclear Reactor Thermal-Hydraulic Multi-scale Coupled Simulation

1. Department of Engineering Physics, Tsinghua University, Beijing, 100084, China;
2. National Key Laboratory of Reactor System Design Technology, Nuclear power institute of China, Chengdu, 610041, China

摘要: 近年来,核反应堆安全分析越来越多地强调分析的精细化和真实性,国际上提出了热工水力多尺度耦合模拟研究。该方法包括系统、部件和局部3个尺度,通过一定的耦合方法将3者有机地结合到一起。采用类似的思路,本文提出了基于RELAP5、COBRA4和CFX的多尺度耦合程序框架,完成了程序开发的前期工作,并通过2个简化问题的测试计算,对耦合程序进行了阶段性的验证。
- 多尺度耦合 /
- 耦合方法 /
- RELAP5/COBRA4/CFX
Abstract: Recently,the nuclear safety analysis more and more emphasize on the fine and realistic analy-sis. Thus thermal-hydraulic multi-scale coupled simulation approach,including the system,component and local scales,has been proposed in some countries. And the three scales can be coupled together effectively through one coupling method. Based on the similar idea,this paper makes a multi-scale coupling framework of RELAP5,COBRA4 and CFX. Verification of current coupled code has been carried out by testing calcula-tion of two simplified problems.
- Multi-scale simulation /
- Coupling method /
- RELAP5/COBRA4/CFX