ERVC数值模拟研究

霍飞鹏; 闫大强; 李京浩; 王捷

doi:10.7538/yzk.2015.49.S0.0252

ERVC数值模拟研究

1.
清华大学核能与新能源技术研究院,先进核能技术协同创新中心,北京100084
2.
国家核电技术有限公司北京软件技术中心,北京102209

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- 刊出日期: 2015-05-19

Numerical Simulation Methodology of ERVC

1.
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084, China
2.
State Nuclear Power Software Development Center, Beijing 102209, China

摘要

摘要: 压力容器外部冷却（ERVC)是AP1000的严重事故响应策略堆内熔融物滞留(IVR)中至关重要的环节，ERVC能否实现的关键是压力容器下封头是否会出现临界热流密度（CHF）。本文通过对低压过冷沸腾工况构建三维流体力学模型，对过冷沸腾实验进行模型验证，然后对AP1000 ERVC进行数值模拟研究，结合CHF模型预测压力容器外壁是否发生CHF，并与实验数据进行对比。计算结果表明，CHF不会发生，与实验相符。可见用三维数值模拟方法分析研究ERVC是可行的。
- 压力容器外部冷却 ,
- 临界热流密度 ,
- 计算流体力学
Abstract: External reactor vessel cooling (ERVC) strategy is proposed to be adopted as a key issue of in-vessel retention (IVR) which is applied in AP1000 as an important method to avoid the consequences of severe accidents. Most researches concerning about the critical heat flux (CHF) of ERVC are based on experiments. This paper dedicated to explore a way with computational fluid dynamics (CFD) method to solve where CHF happens and predict the value. And Eulerian multiphase CFD models were developed to resolve wall boiling and CHF. The numerical results for CHF of ERVC were validated against existing experimental data in this paper. The calculation results indicate that CHF will not occur, which agrees well with experimental results, and it is feasible to analyze ERVC by CFD.
- external reactor vessel cooling ,
- critical heat flux ,
- computational fluid dynamics

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参考文献(19)

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ERVC数值模拟研究

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Numerical Simulation Methodology of ERVC

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