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Showing 1 to 20 of 63 for “"Subcooled"”.
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Subcooled Forced-Convection Film Boiling in a Vertical Annulus
Made available in DSpace on 2014-12-10T22:48:20Z (GMT). No. of bitstreams: 1 7317497.pdf: 8594517 bytes, checksum: 8dc75893ecd55a11c9690718d7b1df74 (MD5) Previous issue date: 1973
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Subcooled critical heat flux for water in round tubes,
Massachusetts Institute of Technology. Dept. of Naval Architecture and Marine Engineering. Thesis. 1965. Nav.E. (Also M.S. in Mechanical Engineering).
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Vapor Bubble Detachment in Subcooled Pool Boiling at Zero Gravity
The mechanism of vapor bubble detachment at zero gravity has been studied both analytically and numerically. Instead of analyzing the force balance, this study emphasizes momentum conservation, the time integral of the force. The liquid velocity is derived from the velocity potential. Heat and mass …
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An Investigatio of Subcooled flow Boiling with Emphasis o nits Initiation
Made available in DSpace on 2017-07-06T18:55:40Z (GMT). No. of bitstreams: 2 Nourmohammadi_Khosrow_MS.pdf: 44965532 bytes, checksum: e061f1448c007bf887afc3534ab2da4a (MD5) license.txt: 4813 bytes, checksum: 715c4321821a960fa1a1e91d2ac7ebce (MD5) Previous issue date: 1980
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Bubble behavior in subcooled flow boiling on surfaces of variable wettability
… in flow boiling. Bubbles were visualized during subcooled nucleate flow boiling of water on a surface of variable wettability. Images obtained from the videos were analyzed to find parameters influencing bubble size at departure. A model was developed relating the dimensions of the bubble at …
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Experimental study of heat flux partitioning in pressurized subcooled flow boiling
Understanding of subcooled flow boiling and the critical heat flux (CHF) is of the utmost importance for both safety and profitability of pressurized water nuclear reactors since they are major factors in the determination of the reactor power rating. Motivated by the emergence of a new wall …
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Growth and collapse of vapour bubbles in convective subcooled boiling of water
… and collapse of vapour bubbles during convective subcooled nucleate boiling of water in an internally heated annular test section was visualized using the high speed filming technique. The experiments were performed at atmospheric pressure, mean flow velocities of 0.08-0.8 m/s, liquid bulk …
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Numerical study of vertical subcooled boiling flow with new wall nucleation models
Correct modeling of subcooled boiling flow has generated significant interest considering its use in a large number of industrial applications, including nuclear power plants. Due to the decrease in computational cost and the limitations of experimental studies, CFD simulation is a proven, powerful …
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Synthesis of CRUD and its effects on pool and subcooled flow boiling
… (Chalk River Unidentified Deposits) on pool and subcooled flow boiling parameters. Previous pool boiling studies have demonstrated the potential of porous, hydrophilic surfaces to lead to more efficient boiling. CRUD is a naturally occurring porous, hydrophilic layer that forms on fuel rods …
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An Experimental Investigation of Critical Heat Flux Performance of Hypervapotron in Subcooled Boiling
… material with augmented heating surfaces in subcooled boiling environment. Different fin dimensions were also tested numerically to compare the experimental results, and suggestions are provided with respect to the combination of performance and economy.
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Experimental study on subcooled flow boiling on heating surfaces with different thermal conductivities
Subcooled flow boiling is generally characterized by high heat transfer capacity and low wall superheat, which is essential for cooling applications requiring high heat transfer rate, such as nuclear reactors and fossil boilers. In this study, subcooled flow boiling on copper and stainless steel …
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Infrared Thermometry Analysis of Surface Effects in Subcooled and Saturated Boiling of Water
In this work, the dynamics of subcooled and saturated flow boiling are studied, focusing on the influence of surface characteristics, visualized through advanced diagnostics capturing micro-scale phenomena. Utilizing specially crafted thin-film infrared heaters, we measured bubble dynamics …
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Investigation of Separate Effects of Surface Condition on Subcooled Flow Boiling Heat Transfer
… effectively transferred to the water coolant by subcooled flow boiling. The maximum reactor power is limited by the critical heat flux (CHF), at which the boiling crisis occurs. Understanding the mechanisms that trigger this boiling crisis and predicting the CHF limit is key to the safety and …
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A study of system-induced instabilities in forced-convection flows with subcooled boiling.
Massachusetts Institute of Technology. Dept. of Mechanical Engineering. Thesis. 1965. Ph.D.
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Study of Surface Tension, Natural Evaporation, and Subcooled Boiling Evaporation of Aqueous Surfactant Solutions
… evaporation under natural convection and subcooled pool boiling is examined through experimental methods. Aqueous solutions of sodium lauryl sulfate (SLS), ECOSURFTM EH-14, and ECOSURFTM SA-9 are used in this study. SLS is an anionic surfactant while EH-14 and SA-9 are …
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An Experimental Study of Subcooled Flow Boiling at Elevated Pressure in an Annular Flow Channel
… setup was developed to study the region of subcooled flow boiling. Multiple studies were carried out to investigate the effects of liquid velocity, pressure, and temperature on the boiling heat transfer of subcooled fluid flowing through a heated annular channel. Water was used as the …
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Experimental Investigation of Subcooled Flow Boiling and CHF at Prototypical Pressures of Light Water Reactors
Boiling crisis is an important phenomenon that affects the performance and safety of pressurized water reactors (PWRs). Accurate predictions of the boiling crisis are difficult to make because they require a clear understanding of the physical mechanisms leading to the boiling crisis combined with …
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Initiation of water hammer in horizontal or nearly-horizontal pipes containing steam and subcooled water
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 1983.
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