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池式夹带高速区试验研究

张鹏 李纬 邸智 胡啸 张蕾 邹亚亨 陈炼 常华健 陈培培

原子能科学技术2016,Vol.50Issue(12):2188-2193,6.
原子能科学技术2016,Vol.50Issue(12):2188-2193,6.DOI:10.7538/yzk.2016.50.12.2188

池式夹带高速区试验研究

Experimental Investigation of Pool Entrainment in High Gas Flux Region

张鹏 1李纬 1邸智 1胡啸 1张蕾 1邹亚亨 1陈炼 1常华健 1陈培培2

作者信息

  • 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
  • 折叠

摘要

Abstract

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 & 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

Key words

pool entrainment/thermal-hydraulic experiment/reactor safety analysis

分类

能源科技

引用本文复制引用

张鹏,李纬,邸智,胡啸,张蕾,邹亚亨,陈炼,常华健,陈培培..池式夹带高速区试验研究[J].原子能科学技术,2016,50(12):2188-2193,6.

基金项目

大型先进压水堆核电站重大专项资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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