首页 | 本学科首页   官方微博 | 高级检索  
     

核电站给水加热器建模仿真
引用本文:冯可新,彭敏俊,徐宇翔,刘新凯.核电站给水加热器建模仿真[J].原子能科学技术,2014,48(2):310-317.
作者姓名:冯可新  彭敏俊  徐宇翔  刘新凯
作者单位:哈尔滨工程大学 核安全与仿真技术国防重点学科实验室,黑龙江 哈尔滨150001
摘    要:给水加热器是核电站二回路系统的重要设备之一,能否正常运行对于核电站的安全性和热经济性具有重要影响,采用仿真手段研究给水加热器的运行特性,可为给水加热器的设计和运行提供重要的理论依据。本文针对压水堆核电站的给水加热器建立了分布参数仿真模型,在处理两相流体时采用了近分相模型,对实际核电站给水加热器在不同工况下的运行特性进行了仿真分析,并将仿真值与实际电站运行值进行了对比。结果表明,所建仿真模型的精度有明显改进。

关 键 词:核电站    给水加热器    建模仿真    近分相模型

Modeling and Simulation on Feed-water Heater of Nuclear Power Plant
FENG Ke-xin,PENG Min-jun,XU Yu-xiang,LIU Xin-kai.Modeling and Simulation on Feed-water Heater of Nuclear Power Plant[J].Atomic Energy Science and Technology,2014,48(2):310-317.
Authors:FENG Ke-xin  PENG Min-jun  XU Yu-xiang  LIU Xin-kai
Affiliation:Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, China
Abstract:The feed-water heater is one of the major equipments in the secondary loop of nuclear power plant (NPP), and its behavior has an important influence on the safe and economical operation of NPP. The research on the behavior of feed-water heater by means of modeling and simulation can provide important theoretical basis for its design and operation. In this paper, the distributed parameter dynamic models of NPP feed-water heater were established, in which the nearly separated model was used to deal with two-phase flow. By simulating the behavior of actual NPP feed-water heaters under various operating conditions and comparing the differences between the simulation values and the actual values, the accuracy of the simulation models was proven to be higher than that of existing models.
Keywords:nuclear power plant  feed-water heater  modeling and simulation  nearly separated model
本文献已被 CNKI 等数据库收录!
点击此处可从《原子能科学技术》浏览原始摘要信息
点击此处可从《原子能科学技术》下载全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号