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EBR-Ⅱ余热排出实验及非能动余热排出系统性能分析

隋丹婷 陆道纲 郭超

原子能科学技术2018,Vol.52Issue(5):881-890,10.
原子能科学技术2018,Vol.52Issue(5):881-890,10.DOI:10.7538/yzk.2018.52.05.0881

EBR-Ⅱ余热排出实验及非能动余热排出系统性能分析

Analysis of EBR-Ⅱ Shutdown Heat Removal Test and Passive Decay Heat Removal Performance

隋丹婷 1陆道纲 2郭超1

作者信息

  • 1. 华北电力大学 核科学与工程学院,北京 102206
  • 2. 华北电力大学 非能动核能安全技术北京市重点实验室,北京 102206
  • 折叠

摘要

Abstract

Based on accident analysis code SAC-CFR,EBR-Ⅱ shutdown heat removal tests (SHRT-17,SHRT-45R) were analyzed in the framework of International Atomic Energy Agency Coordinated Research Project (IAEA CRP) in this paper.The key parameters such as direct reactor auxiliary cooling system (DRACS) response,decay heat power,coolant temperature of key components and mass flow rate in primary loop were calculated.The calculated parameters were compared with measured data,and the effectiveness of the new coupled SAC-CFR code was verified.The results show that each direct heat exchanger (DHX) can remove core decay heat 330 406.4 W with opening of DRACS air damper under SHRT-17 condition.DRACS has capacity of cooling reactor core for long term under natural circulation.

关键词

EBR-Ⅱ/事故余热排出系统/SHRT-17/SHRT-45R

Key words

EBR-Ⅱ/direct reactor auxiliary cooling system/SHRT-17/SHRT-45R

分类

能源科技

引用本文复制引用

隋丹婷,陆道纲,郭超..EBR-Ⅱ余热排出实验及非能动余热排出系统性能分析[J].原子能科学技术,2018,52(5):881-890,10.

基金项目

中央高校基本科研业务费资助项目(2017MS042) (2017MS042)

国家自然科学基金资助项目(11705057) (11705057)

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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