“华龙一号”反应堆及一回路系统研发与设计  

Research and Design of HPR1000 Reactor Coolant System

作　　者：刘昌文[1] 李庆[1] 李兰[1] 钟元章[1] 李海颖[1] 崔怀明[1] 张富源[1] 康志彬 蒲小芬[1] 王华金[1] 焦拥军[1] 冷贵君[1] 卢毅力[1] 曾忠秀[1] 张晓华[1] 

机构地区：[1]中国核动力研究设计院,四川成都610041

出　　处：《中国核电》2017年第4期472-477,512,共7页China Nuclear Power

摘　　要：本文概述了中国核动力研究设计院(以下简称"核动力院")进行"华龙一号"反应堆及一回路系统自主创新的历程,介绍了主要研发内容和设计方案,包括堆芯设计、一回路系统设计、主设备设计、事故预防和缓解措施、安全分析等,展示了"华龙一号"作为三代核电技术的安全性、经济性和先进性。This paper summarizes the process of HPR1000 independent innovation by Nuclear Power Institute of China. In this paper, the main research work and design scheme of the reactor coolant system of HPR1000 nuclear power plant are introduced, including core design, coolant system design, main equipment design, accident prevention and mitigation measures, safety analysis, etc. Through the above descriptions, the safety, economy and advancement of HPR1000 nuclear power plant as a third generation nuclear power technology were revealed.

关 键 词：华龙一号 反应堆一回路系统 三代核电技术 

分 类 号：TL4[核科学技术—核技术及应用]