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State space modeling of reactor core in a pressurized water reactor

机译:压水堆中堆芯的状态空间建模

摘要

The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.
机译:核反应堆的功率控制系统是确保核电厂安全运行的关键系统。但是,核电厂的数学模型是非线性过程和时间相关的形式,很难描述。压水反应堆的重要组件之一是反应堆堆芯。这项研究的目的是使用减速器的温度作为输入来分析从反应堆堆芯产生的功率的性能。提出并分析了反应堆堆芯控制系统状态空间模型的数学表示。数据和参数取自实时VVER型加压水反应堆,并将使用Matlab和Simulink进行验证。在进行的仿真基础上,结果表明调节剂的温度在确定反应堆堆芯功率方面起着重要作用。

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