摘要
以中国超临界水堆(CSR1000)为研究对象,参考日本超临界轻水堆恒压启动系统和超临界锅炉机组启动方式,编制了CSR1000超临界水堆恒压启动分析程序。计算结果表明,CSR1000采用恒压启动,高压补水箱质量流量先增大后减小,主给水泵流量先减小后增大;第一流程包壳温度高于第二流程包壳温度,两个流程的包壳最高温度都低于安全限值1 260℃;第一流程、第二流程冷却剂通道和慢化剂通道线功率密度在堆芯功率达到50%后都趋于稳定。CSR1000采用恒压启动方式不仅能够满足超临界水堆机组启动快速灵活,而且还可以高效平稳地达到安全运行要求。
The supercritical water-cooled reactor of China(CSR1000)is studied in this paper.The constant pressure startup analysis program of the supercritical water reactor,which is based on the supercritical boiler startup method and the supercritical light water reactor constant-pressure startup system of Japan,has been developed.The results showed that CSR1000 adopts constant-pressure startup.The mass flow of the high-pressure makeup tank increases at first and then decreases,while that of the main feed pump is on the contrary in the process of constant-pressure startup.The 2nd maximum cladding surface temperatures(MCST)are higher than the 1st MCST,and both not exceeding 1 260℃.The 1st and 2nd linear power rate of both coolant channels and the moderator channel went stable after the power of CSR1000 reaches 50%.The constant pressure startup mode can not only meet the rapid and flexible characteristics,but also achieve the safe operation requirements efficiently and smoothly.
作者
周涛
李子超
陈杰
刘亮
夏榜样
ZHOU Tao;LI Zi-chao;CHEN Jie;LIU Liang;XIA Bang-yang(School of Nuclear science and Engineering,North China Electric Power University,Beijing,102206,China;Institute of nuclear thermal-hydraulic safety and standardization,North China Electric PowerUniversity,Beijing,102206,China;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy,North China Electric Power University,Beijing,102206,China;State Key Laboratory of Reactor System Design Technology,Chengdu,610041,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2018年第4期569-576,共8页
Nuclear Science and Engineering
基金
北京市自然科学基金(3172032)
中核核反应堆系统设计技术重点实验室课题(2014BH0041)
中央高校基本科研业务费专项资金(2017XS086)
关键词
CSR1000
恒压启动
包壳温度
安全特性
CSR1000
Constant pressure startup
Cladding temperature
Safety characteristics
作者简介
周涛(1965—),男,陕西商州人,教授,研究方向为反应堆热工水力与安全方面研究。
