RELAP5堆芯功率计算模型的扩展

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Expanding of Reactor Power Calculation Model of RELAP5 Code

1. School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China;
2. School of Naval Architecture and Power, Naval University of Engineering, Wuhan, 430033, China;
3. Nuclear Power Institute of China, Chengdu, 610041, China

摘要: 为了更好地将反应堆热工水力最佳估算程序RELAP5应用于分析控制棒控制的反应堆堆芯的功率瞬变过程,堆芯功率计算模块除保留原程序中使用的点堆中子动力学模型外,还必须向轴向一维中子动力学模型进行扩展。本文通过在现有轴向一维物理程序基础上进行改造和开发,实现了RELAP5程序与一维物理程序的耦合,并且通过例题验证了耦合的正确性。
- RELAP5程序 /
- 热工水力 /
- 一维中子动力学 /
- 程序耦合
Abstract: For better analyzing of the nuclear power transient in rod-controlled reactor core by RELAP5 code, a nuclear reactor thermal-hydraulic best-estimate system code, it is expected to get the nuclear power using not only the point neutron kinetics model but also one-dimension neutron kinetics model. Thus an existing one-dimension nuclear reactor physics code was modified, to couple its neutron kinetics model with the RELAP5 thermal-hydraulic model. The detailed example test proves that the coupling is valid and correct.
- RELAP5 /
- Hermal-hydraulic /
- One-dimension neutron kinetics /
- Code coupling