船用堆预计运行事件下放射性源项计算研究  

Source Term Research for Ship Reactor Anticipated Operational Events

作　　者：张帆[1] 郑映峰[1] 商学利[1] 王伟[1] 

机构地区：[1]海军工程大学核能科学与工程系,湖北武汉430033

出　　处：《原子能科学技术》2013年第1期85-88,共4页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(11075212)

摘　　要：按照预计运行事件的基本假设,根据船用堆的运行特点,采用NSRC程序对预计运行事件下一、二回路水及二次侧蒸汽平衡活度、舱室活度进行了计算,部分结果与安全分析报告计算结果进行了比对。结果表明:本软件模型正确,比对结果符合较好,可用于船用堆设计基准事故的放射性后果分析计算,为船用核动力装置安全运行提供依据。According to the basic hypothesis of anticipated operational events, grounding on the special characters of a ship reactor, the equilibrium vapor specific activity and the cabin activity were calculated using NSRC code for the main loop and the secondary loop. The calculation results show that the computational mode of NSRC code is correct, and the NSRC code can be used to calculate radiactive effect of a ship reactor in anticipated operational events of design basis accidents. The calculation results can provide support to the safe operation of a ship nuclear power device.

关 键 词：船用堆 设计基准事故 放射性源项 

分 类 号：TL732[核科学技术—辐射防护及环境保护]