“华龙一号”反应堆冷却剂系统调试研究与设计  

R &D on the Commissioning of Reactor Coolant System of HPR1000

作　　者：黄宗仁[1] 赖建永[1] 刘昌文[1] 赵禹[1] 李海颖[1] HUANG Zong-ren;LAI Jian-yong;LIU Chang-wen;ZHAO Yu;LI Hai-ying(Key Laboratory of Reactor System Design Technology,Nuclear Power Institute of China,Chengdu,Sichuan Prov.610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,四川成都610213

出　　处：《中国核电》2020年第3期282-285,共4页China Nuclear Power

摘　　要：本文介绍了NNSA、IAEA和NRC对反应堆冷却剂系统调试的相关要求,结合NRC对首堆试验的要求和核电厂运行经验反馈,确定了华龙一号反应堆冷却剂系统调试设计的总体思路。接着,介绍了部件试验、系统试验和首堆试验的试验阶段和主要试验内容。通过实施以上试验,可以验证"华龙一号"反应堆冷却剂系统和部件的性能符合设计和安全要求。This paper introduced the NNSA,IAEA and NRC requirements for the commissioning of reactor coolant system of nuclear power plant,and determined the general design idea for the commissioning of reactor coolant system of HPR1000,combined with the requirements of the first-of-its-kind testing by NRC guiding rule and the operation experience feedback of nuclear power plants.Then,it introduced the test stage and main test contents of the component tests,system tests,and first-of-its-kind tests.By performing the above tests,in can verify the performance of the reactor coolant system and components complied with the design and safety requirements.

关 键 词：华龙一号 反应堆冷却剂系统 调试 研究与设计 

分 类 号：TM623[电气工程—电力系统及自动化]