摘要
华龙一号反应堆及一回路系统是中国核动力研究设计院在现有压水堆核电厂科研、设计、制造、建设和运行经验的基础上,根据福岛核事故等经验反馈,借鉴国际先迚核电技术设计理念,遵循国际最高安全要求研収的具有完全自主知识产权的国际先迚的三代百万千瓦压水堆核心系统,是华龙一号三代核电机型的'収动机'。本文概述了中国核动力研究设计院围绕'177堆芯'迚行华龙一号反应堆及一回路系统研制的历程,简要介绍了在反应堆技术方案、一回路系统设备设计和主要实验验证等方面开展的工作,展示了华龙一号'収动机'的先迚性、经济性和安全性。
HPR1000 reactor core and primary loop is a third generation PWR system designed by Nuclear Power Institute of China(NPIC)based on the experiences of research,design,manufacture,construction and operation of existing pressurized water reactor power plants,and the experience feedback from Fukushima nuclear accident,and considering the preeminent design concept of world-wide advanced nuclear power plants.The reactor core and primary circuit is the core system and engine of HPR1000.This paper presents the design process of HPR1000 reactor core and primary circuit in NPIC based on'177 core'.The design of reactor core,primary circuit and equipment,and experimental verification are introduced to show the advancement,economy,and safety of HPR1000.
作者
吴琳
许余
曹锐
刘昌文
李朋洲
张知竹
Wu Lin;Xu Yu;Cao Rui;Liu Changwen;Li Pengzhou;Zhang Zhizhu(Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第A01期1-7,共7页
Nuclear Power Engineering