摘要
介绍了在西安交通大学高压汽水实验回路上进行的垂直螺旋管内汽水两相流传热实验。得出了沿螺旋管长度方向及圆周方向的壁温分布特性，由此确定了发生传热恶化的临界含汽率及其位置。通过关联实验数据，得到了计算临界含汽率的经验公式，为高温气冷堆（ＨＴＧＲ）螺旋管式蒸汽发生器的设计提供了必要的依据。
Experimental investigations of steam Water two phase flow heat transfer in a vertical helically coiled tube are carried out in high pressure steam water test loop of Xi′an Jiaotong University.Wall temperature profiles along the tube length and around the tube perimeter are recorded.Based on these data,the critical steam qualities of heat transfer deterioration are obtained.A correlation for predicting critical steam quality is derived,it can be recommended to be used for the design of steam generator of High Temperature Gas Cooled Reactor(HTGR).
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1998年第5期408-412,共5页
Nuclear Power Engineering
基金
国家"863"高技术研究项目
国家自然科学基金
关键词
蒸汽发生器
螺旋管
壁温分布
传热恶化
气冷堆
Steam generator Helical coil Steam water two phase flow Wall temperature profile Heat transfer deterioration Critical steam quality
