核反应堆非能动余热排出系统分析  

Analyses on Passive Residual Heat Removal System of Nuclear Reactors

作　　者：俞冀阳[1] 俞尔俊[1] 贾宝山[1] 

机构地区：[1]清华大学工程物理系,北京100084

出　　处：《核安全》2004年第4期35-39,共5页Nuclear Safety

摘　　要：本文提出了一种适用于船用核动力装置的非能动余热排出系统的方案设计。该系统利用三个回路的自然循环,把余热排到最终热阱。利用RETRAN02程序,结合陆奥堆的参数,对该系统余热排出能力进行了计算,并分析了影响余热排出能力的几个关键因素。This paper presents a proposal of the passive residual heat removal (PRHR) system of ship-propulsion reactors. The PRHR system uses three natural circulation loops to remove the residual heat from the reactor core to the ultimate heat sink. Taking the parameters of MUTSU reactor, using RE- TRAN02 code, the calculations of the heat removal capability of this system are conducted. Some impor- tant factors that can influence the ability of heat removal are analyzed.

关 键 词：非能动余热排出系统 核反应堆 自然循环 关键因素 能力 适用 影响 程序 方案设计 计算 

分 类 号：TL353.1[核科学技术—核技术及应用] TL364