A comparison of the CFD simulation results in 5 × 5 sub-channels with mixing grids using different turbulence models
-
L. X. Yang
Abstract
We evaluated the performance of various turbulence models, including eddy viscosity models and Reynolds stress models, when analyzing rod bundles in fuel assemblies using the Computational Fluid Dynamics (CFD) method. The models were assessed by calculating the pressure drop and Nusselt numbers in 5 × 5 rod bundles using the CFD software ANSYS CFX. Comparisons between the numerical and experimental results, as well as the swirl factor, cross-flow factor, and turbulence intensity utilized to evaluate the swirling and cross-flow, were used to analyze the inner relationship between the flow field and heat transfer. These comparisons allow the selection of the most appropriate turbulence model for modeling flow features and heat transfer in rod bundles.
Kurzfassung
Zur Berechnung des Strömungsverhaltens in Unterkanälen eines 5 × 5-Stabbündels wurden mit dem Computational Fluid Dynamics (CFD) Programm ANSYS CFX Rechnungen mit verschiedenen Turbulenzmodellen durchgeführt. Anschließend erfolgte ein Vergleich der berechneten Druckabfälle und Nusselt-Zahlen im 5 × 5-Stabbündel mit experimentellen Daten. Dieser Vergleich wurde erweitert auf die Parameter Verwirbelungs- und Querströmfaktor sowie Turbulenzintensität, so dass schließlich aus den Zusammenhängen zwischen dem Strömungsfeld und der Wärmeübertragung das für diese Aufgabenstellung am besten geeignete Turbulenzmodell ausgewählt werden konnte.
References
1 Lee, K. B.; Jang, H. G.: A numerical prediction on the turbulent flow in closely spaced bare rod arrays by a nonlinear k-∊ model. Nuclear Engineering and Design172 (1997) 35110.1016/S0029-5493(97)00001-0Suche in Google Scholar
2 Smith, L. D.; Conner, M. E.: Benchmarking computational fluid dynamics for application to PWR fuel. Proceedings of the 10th International Conference on Nuclear Engineering, Arlington, Virginia, USA, April, 200210.1115/icone10-22475Suche in Google Scholar
3 Yadigaroglu, G.; Anderani, M.: Trends and needs in experimentation and numerical simulation for LWR safety. Nuclear Engineering and Design221 (2003) 20510.1016/S0029-5493(02)00339-4Suche in Google Scholar
4 Holloway, M. V.; McClusky, H. L.: The effect of support grid features on local, single-phase heat transfer measurements in rod bundles. ASME Journal of Heat Transfer126 (2004) 4310.1115/1.1643091Suche in Google Scholar
5 Holloway, M. V.; Conover, T. A.: The effect of support grid design on azimuthal variation in heat transfer coefficient for rod bundles. ASME Journal of Heat Transfer127 (2005) 59810.1115/1.1863274Suche in Google Scholar
6 Liu, C. C.; Ferng, Y. M.: CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly. Applied Thermal Engineering40 (2012) 38910.1016/j.applthermaleng.2012.02.027Suche in Google Scholar
7 Cui, X. Z.; Kim, K. Y.: Three-dimensional analysis of turbulent heat transfer and flow through mixing vane in a subchannel of nuclear reactor. Journal of Nuclear Science and Technology40 (2003) 71910.1080/18811248.2003.9715412Suche in Google Scholar
8 Lee, C. M.; Choi, Y. D.: Comparison of thermo-hydraulic performances of large scale vortex flow (LSVF) and small scale vortex flow (SSVF) mixing vanes in 17 × 17 nuclear rod bundle. Nuclear Engineering and Design237 (2007) 232210.1016/j.nucengdes.2007.04.011Suche in Google Scholar
9 In, W. K.; Chun, T. H.: CFD analysis of turbulent flows in rod bundles for nuclear fuel spacer design. Transactions of the 15th International Conference on Structural Mechanics in Reactor Technology (SMiRT-15), Seoul, 1995Suche in Google Scholar
10 In, W. K.; Chun, T. H.: Numerical computation of heat transfer enhancement of a PWR rod bundle with mixing vane spacers. Nuclear Technology161 (2008) 6910.13182/NT08-A3914Suche in Google Scholar
© 2016, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF
- Technical Contributions/Fachbeiträge
- Subchannel analysis and correlation of the Rod Bundle Heat Transfer (RBHT) steam cooling experimental data
- CFD analysis on mixing effects of spacer grids with different dimples and sizes for advanced fuel assemblies
- An experimental investigation on dynamics and heat transfer associated with a single droplet impacting on a hot surface above the Leidenfrost point temperature
- Study on effects of mixing vane grids on coolant temperature distribution by subchannel analysis
- Reflood experiments in rod bundles with flow blockages due to clad ballooning
- The effect of spacer grid critical component on pressure drop under both single and two phase flow conditions
- Numerical method improvement for a subchannel code
- Numerical investigation on the characteristics of two-phase flow in fuel assemblies with spacer grid
- Effects of axial power shapes on CHF locations in a single tube and in rod bundle assemblies
- CFD evaluation on the thermohydraulic characteristics of tube support plates in steam generator
- Analysis of heat transfer under high heat flux nucleate boiling conditions
- Review of the correlation developments and a new concept based on mixing mechanism for heat transfer enhancement of spacer grids
- A comparison of the CFD simulation results in 5 × 5 sub-channels with mixing grids using different turbulence models
- Simulation of isothermal multi-phase fuel-coolant interaction using MPS method with GPU acceleration
- RELAP5 investigation on subchannel flow instability
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF
- Technical Contributions/Fachbeiträge
- Subchannel analysis and correlation of the Rod Bundle Heat Transfer (RBHT) steam cooling experimental data
- CFD analysis on mixing effects of spacer grids with different dimples and sizes for advanced fuel assemblies
- An experimental investigation on dynamics and heat transfer associated with a single droplet impacting on a hot surface above the Leidenfrost point temperature
- Study on effects of mixing vane grids on coolant temperature distribution by subchannel analysis
- Reflood experiments in rod bundles with flow blockages due to clad ballooning
- The effect of spacer grid critical component on pressure drop under both single and two phase flow conditions
- Numerical method improvement for a subchannel code
- Numerical investigation on the characteristics of two-phase flow in fuel assemblies with spacer grid
- Effects of axial power shapes on CHF locations in a single tube and in rod bundle assemblies
- CFD evaluation on the thermohydraulic characteristics of tube support plates in steam generator
- Analysis of heat transfer under high heat flux nucleate boiling conditions
- Review of the correlation developments and a new concept based on mixing mechanism for heat transfer enhancement of spacer grids
- A comparison of the CFD simulation results in 5 × 5 sub-channels with mixing grids using different turbulence models
- Simulation of isothermal multi-phase fuel-coolant interaction using MPS method with GPU acceleration
- RELAP5 investigation on subchannel flow instability
