池式夹带高速区试验研究  

Experimental Investigation of Pool Entrainment in High Gas Flux Region

作　　者：张鹏 李纬 邸智 胡啸 张蕾 邹亚亨 陈炼 常华健[1,2] 陈培培 

机构地区：[1]国核华清(北京)核电技术研发中心有限公司,北京100190 [2]清华大学,北京100084 [3]国家电力投资集团海外投资公司,北京100029

出　　处：《原子能科学技术》2016年第12期2188-2193,共6页Atomic Energy Science and Technology

基　　金：大型先进压水堆核电站重大专项资助项目(2011ZX06004-007)

摘　　要：发生失水事故后的压水堆内会产生池式夹带现象，这一现象将造成反应堆进一步失水，进而发生堆芯裸露或堆芯熔化等严重事故。Kataoka和Ishii于1983年开发的池式夹带模型在反应堆安全分析中被广泛使用，但十分保守。其中一个重要原因是模型中高速夹带区的试验数据极为有限且不确定性较大，导致该区的模型并不完善。本文介绍空气‐水的池式夹带高速区试验，试验本体参考AP1000原型参数，本体内径为380mm，高为2.2m，由透明材料制作，供气流速为0.98～5.41m／s。试验过程中的两相混合液位和夹带液体质量的测量分别使用导波雷达液位计和称重模块。本试验为夹带模型的高速区补充了数据，发展了现有的池式夹带高速区模型，并发现了在夹带高速区出现的夹带饱和现象。The pool entrainment is an important phenomenon in LOCA transient in PWR plants ,and such a phenomenon may cause further loss of coolant and induce uncovering and melt of fuel .Kataoka ＆amp; Ishii pool entrainment model is widely used in reactor safe‐ty analysis ,but is very conservative .T he reason is that the model has limited validation against experimental data in high gas flux region and has large uncertainty .An experi‐mental study of air‐water pool entrainment with prototypic gas flux conditions of AP1000 was studied .The test section was 2.2 m long and 380 mm in diameter ,and built by transparent material for visualization .T he range of air flow superficial velocity was 0.98‐5.41 m/s .The two‐phase mixture level was measured by guided wave radar and the water entrainment was recorded by weight measurement after it was separated from entrainment separator .A correlation of pool entrainment in high gas flux region was proposed based on experimental data obtained in this study .The phenomenon of entrainment saturation was found in high gas flux region .

关 键 词：池式夹带 热工水力学试验 反应堆安全分析 

分 类 号：TL333[核科学技术—核技术及应用]