先进反应堆安全壳非能动特性分析及模拟架构

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Scaling Study for Experimental Test of Advanced Reactor Analysis of Passive Feature of Containment and Its Simulation Hierarchy

1. Institute of Nuclear and New Energy of Tsinghua University, Beijing, 100084, China;
2. Key Laboratory of Nuclear engineering and Safety of Ministry of Education, Beijing, 102201, China

摘要: 分析具有不同安全特征的安全壳系统,结合对事故过程机制及其物理模型分析,形成一整套适用于先进反应堆安全壳系统性能模拟的理论及试验验证分析体系架构,包括模拟需考虑的物理模型、模拟方法、模拟准则即等级划分、模拟数学模型以及相应试验验证流程。
- 安全壳 /
- 相似分析 /
- 非能动安全 /
- 构架式分析方法
Abstract: Different containment safety features are analyzed.Combined with the accident process analysis and physical model classification,a containment system analysis hierarchy,which can be applied to advanced containment system simulation and experimental verification,is built.Different physical models,experimental methodology,scaling criteria,PIRT,mathematical models and test process logic are included.It attempts to provide theoretical support and design reference for future containment system characteristics verification experiments.It is also applicable for the system simulation,including complex coupling of physical phenomena and processes.
- Containment /
- Scaling /
- Passive safety /
- Hierarchical Analysis