增压换热器在先进压水堆应用的可行性研究  

Feasibility Research on Advanced PWR for Steam-Water Flow Injector

作　　者：彭云康[1] 赵良举[2] 倪永君[1] 

机构地区：[1]中国核动力研究设计院,成都610041 [2]重庆大学热能工程学院,400700

出　　处：《核动力工程》2002年第3期76-78,共3页Nuclear Power Engineering

摘　　要：非能动安全系统是先进压水堆的重要特征之一,世界各核电发达国家对此进行了大量的理论及实验研究,我国的AC600即是应用非能动安全概念的一种堆型。本文初步探讨了提高AC600二次侧非能动余热排出系统除热能力的方法,介绍了增压换热器的工作原理,以及增压换热器在AC600二次侧非能动余热排出系统中的布置方式,并对下一步的工作提出了建议。Passive safety concept is one of the important feature of advanced PWR. Experimental and theoretical researches have been conducted in many developed country on nuclear power. AC-600 is one of the advanced PWR which adapt the passive safety concept developed by China. The feasibility for improve the residual heat removal capacity was discussed in this paper. Also the work mechanism of the steam-water flow injector was introduced and the arrangement in the AC-600 secondary passive residual heat removal system was proposed.

关 键 词：增压换热器 先进压水堆 可行性 

分 类 号：TL3[核科学技术—核技术及应用] TK2[动力工程及工程热物理—动力机械及工程]