An experimental investigation on dynamics and heat transfer associated with a single droplet impacting on a hot surface above the Leidenfrost point temperature
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J. Park
Abstract
During large loss-of-coolant accidents in nuclear reactors, water splatters as the quench front propagates at the quenching surface, and many droplets of different sizes and velocities are generated and carried with the steam in the cooling channel. Heat transfer due to droplets striking an overheated fuel rod above the Leidenfrost point temperature is important for predicting the peak cladding temperature. This study investigated the dynamics and heat transfer characteristics when a single droplet at room temperature collided with a surface at 425 °C experimentally, using synchronized high-speed video and infrared cameras. Various physical parameters related to heat transfer model development were measured, including the residence time, spreading diameter, local heat flux distribution, effective heat transfer area, average vapor film thickness, and total heat transfer per collision. The measured data were compared with the values of the physical parameters predicted by existing mechanistic models.
Kurzfassung
Bei großen Kühlmittelverluststörfällen spritzt während des Fortschreitens der Quenchfront das Wasser und Tropfen verschiedener Größen und Geschwindigkeiten werden gebildet und mit dem Dampf im Kühlkanal transportiert. Zur Berechnung der maximalen Hüllrohrtemperatur ist die Kenntnis des Wärmeübergangs infolge der auf die heiße Oberfläche auftreffenden Tropfen im Bereich des Leidenfrosteffekts notwendig. Experimente zur Dynamik und zum Wärmeübergang eines einzelnen Tropfens bei Umgebungstemperatur, der auf eine 425 °C heiße Oberfläche trifft, werden in diesem Beitrag vorgestellt. Dabei wurden verschiedene physikalische Parameter wie Verweilzeit, Ablösedurchmesser, lokale Wärmestromverteilung, effektive Wärmeübertragungsfläche, mittlere Dampffilmdicke und Wärmestrom pro Kollision gemessen und mit existierenden mechanistischen Modelldaten verglichen.
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© 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
