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棒束子通道湍流交混特性的数值模拟研究
引用本文:张锐,马在勇,陆定晟,何清澈,张卢腾,孙皖,潘良明.棒束子通道湍流交混特性的数值模拟研究[J].原子能科学技术,2022,56(6):1204-1211.
作者姓名:张锐  马在勇  陆定晟  何清澈  张卢腾  孙皖  潘良明
作者单位:重庆大学 低品位能源利用技术及系统教育部重点实验室,重庆400044
基金项目:科技部重点研发计划(2018YFB1900400);
摘    要:为了提高核反应堆系统的经济性和安全性,本文采用CFD方法对棒束子通道间湍流交混效应进行研究。对子通道建模,选取SST k-ω模型进行计算,完成了网格敏感性分析。采用类比浓度计算法与间隙湍流热流法对湍流交混系数进行计算。计算结果表明:雷诺数较小时,单相湍流交混系数随雷诺数的增大而增大;当雷诺数达到一定值时,单相湍流交混系数近似为定值;采用类比浓度计算法与间隙湍流热流法计算所得的湍流交混系数无太大差别。本文拟合得到了适用于单相工况的湍流交混系数计算公式。

关 键 词:数值模拟    子通道    湍流交混系数

Numerical Modeling of Turbulent Mixing Characteristic for Rod Bundle Subchannel
ZHANG Rui,MA Zaiyong,LU Dingsheng,HE Qingche,ZHANG Luteng,SUN Wan,PAN Liangming.Numerical Modeling of Turbulent Mixing Characteristic for Rod Bundle Subchannel[J].Atomic Energy Science and Technology,2022,56(6):1204-1211.
Authors:ZHANG Rui  MA Zaiyong  LU Dingsheng  HE Qingche  ZHANG Luteng  SUN Wan  PAN Liangming
Affiliation:Key Laboratory of Low grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing 400044, China
Abstract:The flow and heat transfer characteristics in the fuel assembly of the reactor core bundle affect the relevant thermal parameters of the reactor core, and the critical heat flux (CHF) and departure from nucleate boiling ratio (DNBR) are increased due to turbulent mixing between subchannels. The turbulent mixing effect between sub-channels is a comprehensive mixing effect caused by multiple factors (pressure difference between channels, geometry, mechanical components, etc.). The mixing between sub-channels can be divided into natural mixing and forced mixing. Cross-flow mixing, as one of natural mixing, is a directional flow of coolant through the gap between sub-channels along the pressure gradient due to the pressure difference between adjacent subchannels. Cross-flow mixing is a type of cross-flow mixing with a net mass transfer, which is also accompanied by an exchange of momentum and energy between the coolants. Another kind of natural mixing is turbulent mixing, which is because the fluid micelle itself is in a state of turbulent pulsation, and at the position of the gap between adjacent subchannels, the fluid micelle forms a vortex flow due to turbulent pulsation, resulting in the exchange of coolants on both sides of the gap. However, due to the vortex flow, there is no net mass transfer of the coolant between the subchannels. In order to improve the economy and safety of the nuclear reactor system, this paper intends to use the computational fluid dynamics (CFD) method to study the turbulent mixing effect between the rod bundle subchannels. In this study, the subchannel was modeled, the SST k-ω model was selected for calculation, and the grid sensitivity analysis was completed. It is found by calculation that when the Reynolds number is small, the single-phase turbulent mixing coefficient increases with the Reynolds number, and when the Reynolds number reaches a certain value, the single-phase turbulent mixing coefficient is approximately constant. At the same time, the turbulent mixing coefficients of subchannels can be accurately calculated by the analog concentration calculation method and the gap turbulent heat flow method, and there is no significant difference in the axial distribution of the calculated turbulent mixing coefficients.
Keywords:numerical modeling                                                                                                                        subchannel                                                                                                                        turbulent mixing coefficient
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