首页|燃料组件辐照后出堆及脱水过程传热特性研究

燃料组件辐照后出堆及脱水过程传热特性研究

Study on Heat Transfer Characteristics of Irradiation Testing Fuel Assembly Discharged from Reactor and Dewatering Process

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为建立燃料组件在研究堆考验回路内辐照后出堆冷却过程的传热特性分析方法,本研究以高通量工程试验堆(HFETR)考验回路辐照后的某型压水堆燃料组件为对象,对其在辐照考验后的出堆过程及脱水过程进行计算流体动力学(CFD)模拟,建立了三维流场、温度场计算模型并计算获得各自的传热特性.研究结果表明,出堆过程流体最高温度大于组件出口温度;而在室温较低的情况下,脱水后组件散热情况更好,可提前进行脱水过程.该方法可以计算出堆过程所允许最大时间及达到脱水条件所需冷却时间,能够用于研究堆考验回路内辐照后燃料组件出堆冷却过程传热特性的分析及预测.
In order to establish a method to analyze the heat transfer characteristics of the fuel assembly after irradiation in the test loop of the research reactor,this study takes a PWR fuel assembly irradiated in the test loop of the High Flux Engineering Test Reactor(HFETR)as the object,simulates its discharge process and dewatering process after irradiation test by computational fluid dynamics(CFD),establishes a three-dimensional flow field and temperature field calculation model,and calculates their respective heat transfer characteristics.The results show that the maximum fluid temperature during discharging process is higher than the assembly outlet temperature.In the case of low room temperature,the heat dissipation of the dehydrated assembly is better,and the dehydration process can be carried out in advance.This method can calculate the maximum allowable time of the discharging process from the reactor and the cooling time required to achieve the dewatering condition.The method in this research can be applied to heat transfer characteristics analysis and prediction for the cooling process of fuel assemblies after irradiation in the test loop of research reactor.

Computational fluid dynamics(CFD)simulationTest loopFuel assemblyRadiation heat transferNatural convection

岳潇、卜仁越、梅星、李科均、黄敏、田志龙、田晓瑞

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中国核动力研究设计院,成都,610213

计算流体动力学(CFD)模拟 考验回路 燃料组件 辐射换热 自然对流

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(3)