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安全壳冷却系统蒸汽冷凝传热研究综述

宿吉强 范黎 高力

原子能科学技术2016,Vol.50Issue(11):1956-1966,11.
原子能科学技术2016,Vol.50Issue(11):1956-1966,11.DOI:10.7538/yzk.2016.50.11.1956

安全壳冷却系统蒸汽冷凝传热研究综述

Review of Steam Condensation Heat Transfer under Containment Cooling System Condition

宿吉强 1范黎 1高力1

作者信息

  • 1. 中国核电工程有限公司,北京 100840
  • 折叠

摘要

Abstract

Part of new generation reactors are widely using passive containment cooling system (PCCS) in order to export the decay heat and maintain the integrity of the con‐tainment under long term post accidents .During the steam condensation ,the presence of non‐condensable gases (air/hydrogen) is an important issue affecting the efficiency of the w hole thermodynamic process .For this reason ,many researchers have investigated it by theoretical or experimental methods .In this paper ,the review of steam condensa‐tion with non‐condensable gases under nuclear plant accident was made .By the depth and comprehensive analysis of the heat transfer process , specific comments were proposed aimed at enhancing the thermal‐hydraulic research foundation of steam conden‐sation under nuclear power plant containment cooling system condition .

关键词

不凝性气体/蒸汽冷凝/传热/综述

Key words

non-condensable gas/steam condensation/heat transfer/review

分类

能源科技

引用本文复制引用

宿吉强,范黎,高力..安全壳冷却系统蒸汽冷凝传热研究综述[J].原子能科学技术,2016,50(11):1956-1966,11.

基金项目

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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