AP1000非能动余热排出热交换器缩比C型管束二次侧传热模型实验研究  

Experimental Investigation on Heat Transfer Model for Secondary Side of Scaled C-shape Bundle Used in PRHR HX of AP1000

作　　者：张钰浩[1,2] 陆道纲[1,2] 王忠毅 吴广皓 傅孝良 杨燕华 

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]华北电力大学北京市非能动安全重点实验室,北京102206 [3]国家核电软件技术中心,北京102209 [4]国家能源核电软件重点实验室,北京102209

出　　处：《原子能科学技术》2016年第10期1763-1770,共8页Atomic Energy Science and Technology

基　　金：国家科技重大专项大型先进压水堆核电站重大专项资助(2011ZX06004-024-07-03-00)

摘　　要：建立了非能动余热排出热交换器(PRHR HX)及内置换料水箱(IRWST)分离效应缩比实验系统,研究了PRHR HX排出堆芯余热过程中,单相自然对流阶段及两相池式沸腾阶段下的传热特性,并采用实验数据评价了传统经验关系式在预测PRHR HX缩比模型特殊C型传热管束时的适用性。实验结果表明,在PRHR HX余热排出过程中,IRWST内出现明显热分层现象。对于PRHR HX竖直管束自然对流、池式沸腾传热,传统经验关系式预测值均较为保守;对于下部水平管束,自然对流阶段推荐Churchill自然对流传热公式,池式沸腾阶段推荐Rohsenow经典池式沸腾传热公式;上部水平管束由于受到流体浮升、气泡扰动等因素的附加影响,在自然对流阶段及池式沸腾阶段的传热效果均优于下部水平管束。The separate-effect overall scaled-down passive residual heat removal heat exchanger（PRHR HX）and in-containment refueling water storage tank（IRWST）experiment was conducted to investigate the secondary side heat transfer characteristics of the scaled C-shape bundle used in PRHR HX in both the single-phase natural convec-tion stage and the two-phase boiling heat transfer stage.The experimental data were used to validate the traditional heat transfer correlations predicting the heat transfer effects of PRHR HX.The experimental results indicate that the thermal stratification phenomenon is very obvious in the heat removal process.For the vertical bundle of PRHR HX,the traditional correlations tend to be conservative in both the single-phase and two-phase heat transfer processes.In the aspect of the lower horizontal bundle,the Churchill correlation is recommended in natural convection stage,and the Rohsenow pool boiling correlation is appropriate in the boiling heat transfer stage.However,for the upper horizontal bundle,because of the additional influences of the buoyancy effects and agitation of the fluid and bubbles,the heat transfer effects are better than those of the lower horizontal bundle.

关 键 词：非能动余热排出热交换器 内置换料水箱 自然对流 池式沸腾 传热经验关系式 

分 类 号：TL33[核科学技术—核技术及应用]