Analysis of heat transfer under high heat flux nucleate boiling conditions
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Y. Liu
Abstract
Analysis was performed for a heater infrared thermometric imaging temperature data obtained from high heat flux pool boiling and liquid film boiling experiments BETA. With the OpenFOAM solver, heat flux distribution towards the coolant was obtained by solving transient heat conduction of heater substrate given the heater surface temperature data as boundary condition. The so-obtained heat flux data was used to validate them against the state-of-art wall boiling model developed by Shaver [1] with the assumption of micro-layer hydrodynamics. Good agreement was found between the model prediction and data for conditions away from the critical heat flux (CHF). However, the data indicate a different heat transfer pattern under CHF, which is not captured by the current model. Experimental data strengthen the notion of burnout caused by the irreversible hot spot due to failure of rewetting. The observation forms a basis for a detailed modeling of micro-layer hydrodynamics under high heat flux.
Kurzfassung
In der Versuchsanlage BETA wurden Blasen- und Filmsiedeexperimente durchgeführt. Dabei wurden Temperaturdaten mit Hilfe einer thermometrischen Infrarotbildaufbereitung gewonnen. Daraus wurden die Wärmeströme zum Kühlmittel berechnet und die Oberflächentemperatur des Heizmaterials wurde als Randbedingung für die Validierungsrechnungen mit dem CFD-Programm OpenFOAM verwendet. Die experimentellen Daten wurden mit dem Wandsiedemodell von Shaver verglichen. Dabei zeigte sich eine gute Übereinstimmung bei Wärmestromwerten, die von der kritischen Wärmestromdichte entfernt liegen. Bei der kritischen Wärmestromdichte zeigte sich in den Experimenten ein anderer Wärmetransport als im Wärmesiedemodell von Shaver zugrunde gelegt wird. Die Experimente zeigen das Auftreten von burn-out durch das Nicht-Wiederbenetzen von Oberflächen infolge irreversibler hot spots. Auf diesen Erkenntnissen aufbauend wurde eine detaillierte Modellierung von der Hydrodynamik in Mikroschichten bei hohen Wärmeströmen entwickelt.
References
1 Shaver, D. R.: Development of a Mechanistic Model for Forced Convection Subcooled Boiling. PhD Thesis; Rensselaer Polytechnic Institute, Troy, New York, 2015.Search in Google Scholar
2 Shirvan, K.; Baglietto, E.; Kazimi, M.: Assessment of a baseline two phase CFD closure for PWR applications. American Nuclear Society Winter Meeting, Washington, DC, 2013Search in Google Scholar
3 Mimouni, S.; Baudry, C.; Guingo, M.; Lavieville,J.; Merigoux, N.; Mechitoua, N.: Computational multi-fluid dynamics predictions of critical heat flux in boiling flow. Nuclear Engineering and Design299 (2016) 28–3610.1016/j.nucengdes.2015.07.017Search in Google Scholar
4 Gilman, L. A.: Development of a general purpose subgrid wall boiling model from improved physical understanding for use in computational fluid dynamics. PhD's thesis, Massachusetts Institute of Technology, Cambridge, Massachusetts, 2014Search in Google Scholar
5 Basu, N.; Warrier, G. R.; Dhir, V. K.: Wall Heat Flux Partitioning During Subcooled Flow Boiling: Part 1 – Model Development. Journal of Heat Transfer. 127 (2005) 131–14010.1115/1.1842784Search in Google Scholar
6 Gao, M.; Zhang, L.; ChengP.; Quan, X.: An investigation of microlayer beneath nucleation bubble by laser interferometric method. International Journal of Heat and Mass Transfer57 (2012) 183–18910.1016/j.ijheatmasstransfer.2012.10.017Search in Google Scholar
7 Jung, S.; Kim, H.: An Experimental Study on Heat Transfer Mechanisms in the Microlayer using Integrated Total Reflection, Laser Interferometry and Infrared Thermometry Technique. Heat Transfer Engineering36 (2015) 1002–101210.1080/01457632.2015.979109Search in Google Scholar
8 Chu, I. C.; No, H. C.; Song, C. H.; Euh, D. J.: Observation of critical heat flux mechanism in horizontal pool boiling of saturated water. Nuclear Engineering and Design279, (2014) 189–19910.1016/j.nucengdes.2014.03.013Search in Google Scholar
9 Gong, S.; Ma, W.; Gu, H.: An experimental investigation on bubble dynamics and boiling crisis in liquid films. International Journal of Heat and Mass Transfer79 (2014) 694–70310.1016/j.ijheatmasstransfer.2014.08.065Search in Google Scholar
10 Theofanous, T. G.; Tu, J. P.; Dinh, A. T.; Dinh, T. N.: The boiling crisis phenomenon: Part I: nucleation and nucleate boiling heat transfer. Experimental Thermal and Fluid Science26 (2002) 775–79210.1016/S0894-1777(02)00192-9Search in Google Scholar
11 Theofanous, T. G.; Dinh, T. N.; Tu, J. P.; Dinh, A. T.: The boiling crisis phenomenon: Part II: dryout dynamics and burnout. Experimental Thermal and Fluid Science26 (2002) 793–81010.1016/S0894-1777(02)00192-9Search in Google Scholar
12 Liu, Y.; Dinh, N.: Treatment of Nucleation and Bubble Dynamics in High Heat Flux Boiling. Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Chicago, Illinois, 2015Search in Google Scholar
13 Wee, S. K.: Microscale observables for heat and mass transport in sub-micron scale evaporating thin film. PhD Thesis, Texas A&M University, College Station, Texas, 2004Search in Google Scholar
14 Kurul, N.; Podowski.,M. Z.: Multidimensional effects in forced convection subcooled boiling. Proceedings of the Ninth International Heat Transfer Conference, Jerusalem, Israel, 199010.1615/IHTC9.40Search in Google Scholar
15 Shaver, D. R.; Podowski, M. Z.: Modeling and Validation of Forced Convection Subcooled Boiling. Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Chicago, Illinois, 2015Search in Google Scholar
16 Liu, Y.; Srivastava, M.; Dinh, T. N.: Micro-hydrodynamics in High Heat Flux Boiling and Burnout: Experimental Data and Model Development. CASL-U-2014-0211-000, 2014Search in Google Scholar
© 2016, Carl Hanser Verlag, München
Articles in the same Issue
- 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
Articles in the same Issue
- 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
