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船用堆控制棒失控抽出事故时堆芯安全特性研究
引用本文:王乔,陈文振,张帆. 船用堆控制棒失控抽出事故时堆芯安全特性研究[J]. 原子能科学技术, 2010, 44(10): 1223-1227. DOI: 10.7538/yzk.2010.44.10.1223
作者姓名:王乔  陈文振  张帆
作者单位:海军工程大学 ;核能科学与工程系,湖北 ;武汉430033
摘    要:采用船用堆三维动态安全分析仿真软件对发生控制棒失控抽出事故时堆芯安全特性进行了仿真分析,研究了反应堆分别处于高、低功率运行工况下1组或1束控制棒以不同的速率失控抽出时堆芯燃料芯块中心最高温度、最小烧毁比和冷却剂出口温度等参数的变化规律,并进行了比较,得出了一些有益的结论,对于考察反应堆安全状况和事故发生后反应堆操纵人员制定安全措施具有重要的指导意义。

关 键 词:反应堆   控制棒   失控抽出   安全分析

Safety Analysis of Ship Reactor With Inadvertent Control Rod Withdrawal Accident
WANG Qiao,CHEN Wen-zhen,ZHANG Fan. Safety Analysis of Ship Reactor With Inadvertent Control Rod Withdrawal Accident[J]. Atomic Energy Science and Technology, 2010, 44(10): 1223-1227. DOI: 10.7538/yzk.2010.44.10.1223
Authors:WANG Qiao  CHEN Wen-zhen  ZHANG Fan
Affiliation:Department of Nuclear Energy Science and Engineering, Naval University of Engineering, Wuhan 430033, China
Abstract:The safety characteristic of the reactor core, in which the inadvertent control rod withdrawal accident happens, was simulated and analyzed by the three-dimensional safety analysis and simulation software of the ship reactor. When one group or bundle of control rods in the reactor that was operating under the high or power condition were inadvertently withdrawn at the different velocities, variations of important reactor parameters, such as the peak temperature in the fuel center, the minimal departure from nucleate boiling ratio (DNBR) and the outlet coolant temperature, et al, were investigated. Some useful conclusions are drawn, which are very significant and important to estimate the reactor safety state and to provide safety operation rules for the reactor operator after the accident.
Keywords:reactor  control rod  inadvertent withdrawal  safety analysis
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