压水堆核电站堆芯物理热工水力耦合特性研究  

Study on Physical Thermal-hydraulic Coupling Characteristics of PWR Nuclear Power Plant Core

作　　者：姚亦珺 YAO Yijun(China Nuclear Power Engineering Corporation,Beijing 100142,China)

机构地区：[1]中国核电工程有限公司,北京100142

出　　处：《信息与电脑》2024年第9期4-6,共3页Information & Computer

摘　　要：随着信息技术高速发展,人工智能、大数据以及物联网等多种技术在核电站中应用日益广泛。其中反应堆的物理热工耦合特性是其整体性能的重要体现,也是评估其经济性、安全的主要依据。基于此,本文主要计算单根燃料棒模型耦合以及3*3组件模型耦合,了解其在不同工况中的变化,有利于事故预测以及方案优化。With the rapid development of information technology,artificial intelligence,big data,the Internet of Things and other technical means are increasingly used in nuclear power plants.The physical and thermal coupling characteristic of the reactor is an important embodiment of its overall performance,and also the main basis for evaluating its economy and safety.Based on this,this paper mainly calculates the coupling of single fuel rod model and 3*3 component model,and understands the changes in different working conditions,which is conducive to accident prediction and scheme optimization for reference.

关 键 词：压水堆核电站堆芯 物理热工水力 耦合特性 信息技术 

分 类 号：TL364[核科学技术—核技术及应用]