超临界快堆给水控制失效瞬态控制分析  

Control Analysis for Failure Transient Accident of Feed-Water Control System in Supercritical Water-Cooling Fast Reactor

作　　者：王晗丁[1] 周涛[1] 陈娟[1] 李精精[1] 刘梦影[1] 

机构地区：[1]华北电力大学核热工安全和标准化研究所,北京102206

出　　处：《核动力工程》2011年第5期18-22,共5页Nuclear Power Engineering

基　　金：国家973计划项目(2007CB209800);国家自然科学基金项目(50976033)

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,反应堆各参数可达到较稳定值,且包壳温度在安全范围内,因此可有效缓解给水控制失效瞬态事故,保证超临界快堆的安全。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 turbine valve and control rod,all reactor parameters are stable and the clad temperature is within the safety range,thus the transient accident of feedwater control failure can be mitigated to ensure the safety of the supercritical fast reactors.

关 键 词：超临界快堆 给水控制 瞬态事故 控制方式 安全特性 

分 类 号：TL364.4[核科学技术—核技术及应用]