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DVI管小破口失水事故实验研究

彭传新 张妍 黄志刚 昝元锋 卓文彬 闫晓

原子能科学技术2016,Vol.50Issue(10):1787-1792,6.
原子能科学技术2016,Vol.50Issue(10):1787-1792,6.DOI:10.7538/yzk.2016.50.10.1787

DVI管小破口失水事故实验研究

Experimental Investigation on Small Break Loss of Coolant Accident for Direct Vessel Injection Line

彭传新 1张妍 1黄志刚 1昝元锋 1卓文彬 1闫晓1

作者信息

  • 1. 中国核动力研究设计院中核核反应堆热工水力技术重点实验室,四川成都 610041
  • 折叠

摘要

Abstract

T he small break loss of coolant accident (SBLOCA ) experiment for direct vessel injection (DVI ) line , w hich investigated the thermal‐hydraulic phenomena and the performances of passive safety system during the accident ,was performed on the passive safety system test facility for small modular reactor .The experimental results show that the passive safety system of small modular reactor can provide effective cool‐ant injection ,successful removal of core residual heat under the DVI line SBLOCA and protection to reactor core safety .

关键词

小破口失水事故/DVI管/非能动安全系统

Key words

small break loss of coolant accident/DVI line/passive safety system

分类

能源科技

引用本文复制引用

彭传新,张妍,黄志刚,昝元锋,卓文彬,闫晓..DVI管小破口失水事故实验研究[J].原子能科学技术,2016,50(10):1787-1792,6.

基金项目

国家杰出青年科学基金资助项目(11325526);863计划资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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