摘要
用ＡＣ６００非能动安全壳冷却系统三维热工水力分析程序ＰＣＣＳＡＣＭＤ，对几种常用的冷凝传热系数结构关系式进行了比较。这些结构关系式包括Ｕｃｈｉｄａ关系式、ＧｉｄｏＫｏｅｓｔｌ关系式、Ｔａｇａｍｉ关系式和基于传热传质相似原理的关系式。研究认为，与ＧｉｄｏＫｏｅｓｔｌ关系式相比，基于稳态实验数据的Ｕｃｈｉｄａ关系式是比较保守的。虽然不同的冷凝传热系数结构关系式计算得到的冷凝传热系数差别较大，但对ＡＣ６００在冷段双端断裂大破口失水事故和主蒸汽管道断裂事故工况下的压力峰值影响不太大，而对热段双端断裂大破口失水事故工况下的压力峰值影响相对较大。研究还认为，Ｔａｇａｍｉ关系式在计算主蒸汽管道断裂事故时安全壳压力峰值最为保守。
This paper gives a warranty to choice condensation heat transfer correlation (HTC) in AC600 passive containment cooling system (PCCS) analysis by comparing some most useful condensation HTC used in PCCSAC MD code which is a multi dimensional thermal hydraulic analysis code for AC600 PCCS.These correlations include Uchida correlation,Gido Koestl correlation,Tagami correlation and heat mass transfer analogy correlation using the heat transfer coefficient on the vapor side of the interface.This paper gets the conclusion that the Uchida correlation based on steady state data of experiment is more conservative than the Gido Koestl correlation.The difference of peak pressure value of AC600 containment under double ended cold leg loss of coolant accident or main steam line break accident calculated by different correlation is similar while for double ended hot leg loss of coolant accident the difference is big,Although different correlation gets different heat transfer coefficient.The Tagami correlation is the most conservative one in the main steam line break accident calculated.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1999年第3期214-218,共5页
Nuclear Power Engineering
关键词
冷凝传热系数
非能动
安全壳
冷却系统
AC600 Condensation heat transfer coefficient Passive containment cooling system
