大亚湾核电站两个机组反应堆第四循环堆芯换料设计  

Incore Reload Design for Cycle 4 of Day Bay Nuclear Power Station Both Units

作　　者：章宗耀[1] 刘旭东[1] 咸春宇[1] 李冬生[1] 张虹[1] 刘昌文[1] 王英明[1] 赵科[1] 张洪 肖岷 

机构地区：[1]中国核动力研究设计院 [2]广东核电合营有限公司

出　　处：《核动力工程》1998年第5期385-389,共5页Nuclear Power Engineering

摘　　要：简要介绍了大亚湾核电站换料设计的基本原理和内容，以及两个机组第四循环换料设计的主要结果，并与测量值作了比较。计算结果表明，两个机组的换料设计都满足了安全性准则和经济性要求；测量结果表明，理论预测值与实测值符合良好。The basic principles and the contents of the reload design for Daya Bay nuclear power station are briefly introduced.The incore reload design results,and the comparison between the calculated values and the measured values of both units the fourth cycle are also given.The reload design results of the two units satisfy all the economic requirements and safety criteria.The experimented results shown that the predicated values are tally good with all the measurement values.

关 键 词：核电站 换料设计 堆芯 燃料管理 

分 类 号：TM623.7[电气工程—电力系统及自动化] TL351.1[核科学技术—核技术及应用]