| 超临界快堆给水控制失效瞬态控制分析 |
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| 引用本文： | 王晗丁,周涛,陈娟,李精精,刘梦影.超临界快堆给水控制失效瞬态控制分析[J].核动力工程,2011,32(5):18-22. |
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| 作者姓名： | 王晗丁 周涛 陈娟 李精精 刘梦影 |
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| 作者单位： | 华北电力大学核热工安全和标准化研究所,北京,102206 |
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| 基金项目： | 国家973计划项目(2007CB209800); 国家自然科学基金项目(50976033) |
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| 摘 要： | 超临界快堆是一次通过循环,瞬态安全特性不同于现有的轻水堆.以控制棒、汽轮机主进汽阀、反应堆冷却剂泵作为超临界快堆的控制方式,在给水控制系统失效瞬态事故工况下,研究该堆采用不同控制方式时,反应堆内压力、功率、冷却剂温度、冷却剂质量流量及包壳表面温度等参数随时间的变化情况.结果表明:采用汽轮机主进汽阀与控制棒联合控制时,反...
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| 关 键 词： | 超临界快堆 给水控制 瞬态事故 控制方式 安全特性 |
Control Analysis for Failure Transient Accident of Feed-Water Control System in Supercritical Water-Cooling Fast Reactor |
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| WANG Han-ding,ZHOU Tao,CHEN Juan,LI Jing-jing,LIU Meng-ying.Control Analysis for Failure Transient Accident of Feed-Water Control System in Supercritical Water-Cooling Fast Reactor[J].Nuclear Power Engineering,2011,32(5):18-22. |
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| Authors: | WANG Han-ding ZHOU Tao CHEN Juan LI Jing-jing LIU Meng-ying |
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| Affiliation: | WANG Han-ding,ZHOU Tao,CHEN Juan,LI Jing-jing,LIU Meng-ying (Institute of Nuclear Thermal-Hydraulic Safety and Standardization,North China Electric Power University,Beijing,102206,China) |
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| Abstract: | Supercritical cooling fast reactor is the once-through cooling system,and its transient safety characteristics is different from that of the existing LWRs.Under the failure transient accident of the feedwa-ter control system,the reactor pressure,power,coolant temperature,coolant mass flow and the surface clad temperature changing with the time are studied with three different control modes(the control rods,steam turbine valves,and reactor coolant pump).The results show that with the combined control by the ... |
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| Keywords: | Supercritical water-cooling fast reactor Feed-water control system Transient accident Control mode Safety characteristics |
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