摘要
针对各国超临界水冷堆燃料组件设计方案,选取圆管、圆环形通道、方环形通道3种具有热工水力代表性的简单通道,开展超临界条件下水工质的传热特性实验研究。实验结果表明,热流密度、质量流速和压力3种热工参数对不同简单通道传热特性的影响趋势基本一致;在相同质量流速和压力下,换热系数在靠近拟临界温度处存在峰值,且随热流密度的增大而减小;在相同热流密度和压力下,相同主流体焓处对应的换热系数随着质量流速增加而增加;压力对超临界水传热特性影响较弱,仅在拟临界区域内换热系数峰值稍有不同;实验中出现了拟临界区域的传热恶化现象,传热恶化发生时壁温出现局部峰值。
Heat transfer experiments of supercritical water in circular tube, circular annulus and rectangular annulus were carried out, which were abstracted as simple channels to represent the thermal hydraulic characteristics of several Supercritical Water Cooled Reactor （SCWR） fuel assembly design. It was found that, the effect of heat flux, mass flux and pressure on supercritical water heat transfer performance in different simple channels was similar in general. Under the same mass flux and pressure, there was a peak of heat transfer coefficient in pseudo-critical area, which would be decreased with the increasing of heat flux. Under the same heat flux and pressure, the heat transfer coefficient at the same bulk fluid enthalpy would be increased with the increasing of mass flux. The effect of pressure on supercritical water heat transfer performance in different simple channels was not strong except in the pseudo-critical area where the peak of heat transfer coefficient would occur. The heat transfer deterioration phenomenon was also found at different pressures and mass fluxes in different simple channels.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2013年第1期101-107,共7页
Nuclear Power Engineering
关键词
超临界水
简单通道
传热
实验研究
Supercritical water, Simple channels, Heat transfer, Experimental study
