节点文献

“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

  • 推荐 CAJ下载
  • PDF下载
  • 不支持迅雷等下载工具,请取消加速工具后下载。

【作者】 刘昌文李庆李兰钟元章李海颖崔怀明张富源康志彬蒲小芬王华金焦拥军冷贵君卢毅力曾忠秀张晓华

【Author】 LIU Chang-wen;LI Qing;LI Lan;ZHONG Yuan-zhang;LI Hai-ying;CUI Huai-ming;ZHANG Fu-yuan;KANG Zhi-bin;PU Xiao-fen;WANG Hua-jin;JIAO Yong-jun;LENG Gui-jun;LU Yi-li;ZENG Zhong-xiu;ZHANG Xiao-hua;Nuclear Power Institute of China;

【机构】 中国核动力研究设计院

【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。

【Abstract】 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.

  • 【文献出处】 中国核电 ,China Nuclear Power , 编辑部邮箱 ,2017年04期
  • 【分类号】TM623.2
  • 【被引频次】17
  • 【下载频次】816
节点文献中: