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断电停机过渡过程中核主泵气液两相流动特性研究

王秀礼 王鹏 袁寿其 朱荣生 付强

原子能科学技术Issue(11):2004-2011,8.
原子能科学技术Issue(11):2004-2011,8.DOI:10.7538/yzk.2014.48.11.2004

断电停机过渡过程中核主泵气液两相流动特性研究

Study on Flow Characteristics of Gas-liquid Two-phase for Reactor Coolant Pump With Power Shutting Down Transition Process

王秀礼 1王鹏 1袁寿其 1朱荣生 1付强1

作者信息

  • 1. 江苏大学流体机械工程技术研究中心,江苏镇江 212013
  • 折叠

摘要

Abstract

For the study of gas‐liquid two‐phase transient flow characteristics with the power shutting down transition process in the reactor coolant pump ,with the help of CFD ,the gas‐liquid two‐phase flow variation and radial force were researched by experi‐mental verification at different gas contents and the calculation results w ere verified by experimental test .The results show that the numerical simulation data agree well with the test data and vortex near the back of the impeller is produced ,w hich makes the gas‐phase region become large and the corresponding gas volume fraction increases .The capacity of the impeller to convert energy reduces with the reductions of flow rate and rotation speed ,w hich leads to a large number of gas‐phase in the impeller and guide vanes .When the gas content is small ,the gas volume fraction will reaches a maximum before it declines in rotating dispersed form .When gas content is large ,the gas volume fraction in the impeller increases with the reduction of flow rate .Gas content has a great influence on speed in flow passage of the impeller , especially for that close to blade inlet .The unbalance of radial force begins to fall off with the increase of gas content , and its maximum unbalanced radial forces changes from imbalance region between posi‐tive and negative value to that of negative value prevailing .

关键词

核主泵/断电停机过渡过程/气液两相/数值模拟/流动特性

Key words

reactor coolant pump/power shutting down transition process/gas-liquid tw o-phase/numerical simulation/flow characteristic

分类

机械制造

引用本文复制引用

王秀礼,王鹏,袁寿其,朱荣生,付强..断电停机过渡过程中核主泵气液两相流动特性研究[J].原子能科学技术,2014,(11):2004-2011,8.

基金项目

国家自然科学基金资助项目(51379091);江苏省自然科学基金科技项目资助(BK20130516);国家博士后基金资助项目(2014M551511);江苏大学高级人才启动基金资助项目(13JDG083);江苏高校优势学科建设工程资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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