停堆余热冷却系统-化学容积控制系统热工水力特性分析  

Thermohydraulic Analysis for Residual Heat Removal- Chemical and Volume Control System

作　　者：彭云康[1] 许厚明[1] 罗志远[1] 倪永君[1] 刘莉[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2000年第5期393-397,共5页Nuclear Power Engineering

摘　　要：广东大亚湾核电站 1号机组在维修或冷停堆换料期间，停堆余热冷却系统的化学容积控制系统净化流量严重不足，远远低于设计要求。而该净化流量在电站维修或冷停堆期间起着非常大的作用，改进停堆余热冷却系统，提高化学容积控制系统净化流量成了当务之急。为了确保改进后的停堆余热冷却系统-化学容积控制系统能提供满足系统手册要求的净化流量，本文用 RELAP5/MOD3程序计算分析了大亚湾核电站 1号机组停堆余热冷却系统-化学容积控制系统改进前后的热工水力特性，为制定停堆余热冷却系统-化学容积控制系统的改进方案提供了依据。During maintenance or refueling cold shutdown,the Chemical and Volume Control System (RCV) purification flow of Residual Heat Removal System (RRA) in Daya Bay Nuclear Power Station (NPS) is below half of the expected value which is about 20m3/h.Since the purification flow plays an important role during NPS maintenance or refueling cold shutdown,the RRA system of Daya Bay NPS must be modified in order to increase the purification flow.The thermohydraulic behavior of RRA- RCV system of Guang Dong Daya Bay NPS Uint 1 before and after modification was analyzed by using RELAP5/MOD3 in this paper.After the modification of RRA- RCV system,the purification flow increases significantly and satisfies the requirement of RCV system design manual.

关 键 词：大亚湾电站 热工水力特性 净化系统 RRA RCV 

分 类 号：TL33[核科学技术—核技术及应用] TL382