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首页|期刊导航|原子能科学技术|真实表面材料及其老化效应对反应堆压力容器ERVC-CHF影响的试验研究

真实表面材料及其老化效应对反应堆压力容器ERVC-CHF影响的试验研究

陆维 胡腾 赵宇峰 杨胜 常华健

原子能科学技术2016,Vol.50Issue(10):1782-1786,5.
原子能科学技术2016,Vol.50Issue(10):1782-1786,5.DOI:10.7538/yzk.2016.50.10.1782

真实表面材料及其老化效应对反应堆压力容器ERVC-CHF影响的试验研究

Experimental Research on Influence of Real Surface Material and Aging Effect on ERVC-CHF of RPV

陆维 1胡腾 1赵宇峰 1杨胜 1常华健2

作者信息

  • 1. 国家核电技术有限公司北京研发中心,北京 100190
  • 2. 清华大学核能与新能源技术研究院,北京 100084
  • 折叠

摘要

Abstract

In‐vessel retention (IVR) of molten corium through external reactor vessel cooling (ERVC) is one of the most important severe accidents management strategies . In this paper ,a two dimensional full scale facility FIRM was built to investigate critical heat flux (CHF) behaviors under severe accident conditions .CHF limits of RPV lower head in the process of ERVC were investigated with deionized water as working fluid . The influence of real surface material SA508 Gr3. Cl.1 steel and its mechanism were investigated . The aging effect of SA508 Gr3. Cl.1 steel in deionized water was discussed .The test result will provide a profound understanding of CHF behaviors with real RPV material under IVR‐ERVC condition and will be of significance to improve the safety of reactor vessel .

关键词

临界热流密度/SA508Gr3.Cl.1钢/严重事故/熔融物堆内滞留

Key words

critical heat flux/SA508 Gr3.Cl.1 steel/severe accident/in-vessel retention

分类

能源科技

引用本文复制引用

陆维,胡腾,赵宇峰,杨胜,常华健..真实表面材料及其老化效应对反应堆压力容器ERVC-CHF影响的试验研究[J].原子能科学技术,2016,50(10):1782-1786,5.

基金项目

国家科技重大专项资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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