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实验研究在5MW核供热反应堆模拟热工水力学实验回路HRTL-5上进行。分析计算基于带有质量,蒸汽质量,能量及动量守恒方程的一维两相流漂移模型。给出了在不同系统压力,进口过冷度及热流密度条件下的稳态和动态分析结果。研究结果表明:加热段中的过冷沸腾及上升段中的闪蒸对空泡份额分布及流动稳定性有重要影响,特别是在低压条件下;在相当宽的两相流条件下,加热段中只发生过冷沸腾;对于沸水设计工况的5MW低温堆,其堆芯出口温度尚未达到饱和。描述了两相流振荡机理,即“零阻降”机理。在进口过冷度相当宽范围内(OK<ΔT<28K),对系统流条件,存在3个区域,即稳定的两相流,整体和过冷沸腾不稳定流和过冷沸腾以及单相稳定流。给出了系统流量在小热流密度扰动下的响应特性。在此基础上给出了稳定边界图的计算和实验值。
The experimental study was carried out on HRTL-5, a simulation thermomechanical experimental loop of 5MW nuclear reactor. The analytical calculation is based on a one-dimensional two-phase flow drift model with mass, steam mass, energy and momentum conservation equations. The steady-state and dynamic analysis results under different system pressures, inlet subcooling degree and heat flux density are given. The results show that the subcooled boiling in the heating section and the flashover in the ascending section have an important influence on the bubble distribution and the flow stability, especially under the condition of low pressure. Under the condition of very wide two-phase flow, the heating section In the case of boiling 5 MW low temperature reactor in boiling water design conditions, the core outlet temperature has not yet reached saturation. The oscillating mechanism of two-phase flow is described, that is, the mechanism of “zero resistance drop”. In the fairly wide range of inlet subcooling (OK <ΔT <28 K), there are three regimes for system flow conditions: steady two-phase flow, global and subcooled boiling unstable flow and subcooled boiling and single phase stabilization flow. The response characteristics of system flow under small heat flux density disturbance are given. On this basis, the calculation and experimental results of the stable boundary map are given.