中子倍增公式在连续提棒事故瞬态特性模拟中的应用  

Application of Neutron Multiplication Formula in Simulating of Nuclear Power Plant During the Accident of Control Rod Raised Continuously

作　　者：王少明[1] 郝建立[1] 章德[1] 秦田夫[1] 

机构地区：[1]海军工程大学核能科学与工程系,武汉430033

出　　处：《船海工程》2009年第4期84-87,共4页Ship & Ocean Engineering

基　　金：国家自然科学基金(10575131)

摘　　要：通过中子倍增公式建立模型,分别计算船用核动力反应堆在低功率和高功率运行时发生连续提棒事故后的各主要参数的变化,并将计算结果与三维实时仿真软件计算结果进行比较。结果表明,计算结果与三维实时仿真软件计算结果比较符合,可为事故的处置提供依据。The model was established with neutron multiplication formula, and main parameters of the marine nuclear reactor were calculated under two typical operation conditions during the accident of control rod raised continuously. The results were compared with those obtained by 3 D real time simulation software of reactors. The model was proved properly. The results can be used as the basis of accident treatment and useful for the marine nuclear reactor safety operation.

关 键 词：核动力装置 连续提棒事故 中子倍增 瞬态特性 

分 类 号：U664.15[交通运输工程—船舶及航道工程] TL329[交通运输工程—船舶与海洋工程]