大亚湾核电站堆芯换料设计  

In-Core Reload Design for Daya Bay Nuclear Power Station

作　　者：章宗耀[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1期52-55,共4页Nuclear Power Engineering

摘　　要：介绍了大亚湾核电站堆芯换料设计准则、计算机程序、设计内容以及设计预计值与测量值的比较。结果表明 ,中国核动力研究设计院承担的两个机组反应堆第四至第六循环换料设计均满足该电站的安全和经济性要求 。The design criteria,codes,basic principles and contents of the reload design for Daya Bay Nuclear Power Station are briefly introduced.The in core reload design results,and the comparison between the calculated values and the measured values of the both units from cycle four to cycle six are also given.The reload design results of the two units are satisfied with all the safety criteria and economic requirement.The experimented results show that the predicated values are good consistent with all the measureed values.

关 键 词：大亚湾核电站 堆芯换料设计 堆芯燃料管理 

分 类 号：TL351.1[核科学技术—核技术及应用] TL384