堆芯紧急冷却安注热混合实验研究

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基金项目:

大型先进压水堆核电站重大专项资助项目(2011ZX06004-024)

Experimental Study on Thermal Mixing in Emergency Core Cooling System

1. State Key laboratory of Multiphase Flow in Power Engineering Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China;
2. Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China

摘要: 以核电厂压水堆中失水事故(LOCA)堆芯紧急安注系统(ECCS)启动后安注接管与冷管段的T型管处冷、热流体混合为研究对象,进行安注管和主管道内过冷水-高温冷却剂的热混合特性实验以及过冷水-汽水混合物直接接触冷凝特性实验,通过缩比尺寸实验对热混合相关现象进行研究。结果表明,单相热混合实验管内温度场随不同射流流型成一定分布;两相热混合工况安注后冷凝量随主管蒸汽量变化而成线性分布,并总结实验数据形成适用于本实验直接接触冷凝相关关系式。
- 堆芯紧急安注系统(ECCS) /
- 安注系统 /
- 热混合 /
- 两相流
Abstract: Through the postulated loss of coolant accident（LOCA） in pressure water reactors（PWRs）, the cooling water from the emergency core cooling system（ECCS） start and then inject into the cold leg. The scaling-down experiment aims to study the characteristics of thermal mixing in T-junction, including two subprojects: single phase thermal mixing test and two phase flow direct contact condensation test. The conclusion indicated that: The temperature field in the cross-section of pipes was affected by the jet flow on single phase thermal mixing test; In two phase flow direct contact condensation test, the mass of condensation after cooling goes to linear distribution with the jet flux.
- ECCS /
- Safety injection system /
- Thermal mixing /
- Two phase flow