Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems (Series in thermal and fluids engineering) by Jean J. Ginoux

Cover of: Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems (Series in thermal and fluids engineering) | Jean J. Ginoux

Published by McGraw-Hill Education .

Written in English

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Subjects:

  • Engineering - Nuclear,
  • Technology & Industrial Arts

Book details

The Physical Object
FormatHardcover
Number of Pages480
ID Numbers
Open LibraryOL9249514M
ISBN 100070233055
ISBN 109780070233058

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Heat transfer and phase change phenomena in two-phase flows are often encountered in nuclear reactor systems and are therefore of paramount importance for their optimal design and safe operation. The complex phenomena observed especially during transient operation of nuclear reactor systems necessitate extensive theoretical and experimental Author: Boštjan Končar, Eckhard Krepper, Dominique Bestion, Chul-Hwa Song, Yassin A.

Hassan. Introduction Two phase flow heat transfer in light water cooled nuclear reactors (LWR) is an important area of Nuclear Engineering.

The complex phenomena observed during both the steady state and especially the transient operation of a LWR necessitates. Over the past two decades, two-phase flow and heat transfer problems associated with two-phase phenomena have been a challenge to many investigators. Two-phase flow applications are found in a wide range of engineering systems, such as nuclear and conventional power plants, evaporators of refrigeration systems and a wide vari­ ety of.

Thermohydraulics of Two-phase Systems for Industrial Design and Nuclear Engineering Codes and TwoPhase Flow Heat Transfer Calculations nucleation obtained occur operating oscillations parameters perturbations phase phenomena pipe predict presented pressure drop problems Reactor regime region rewetting saturation shown shows single-phase.

McMaster University. The model, adapted from a closed loop PWR model, is used for safety assessment of decay heat removal in the McMaster Nuclear Reactor under events that involve abnormal core cooling.

The natural convection model calculates the steady state single or two-phase flow rate and quality riseFile Size: KB. Two-phase Fluid Flow. By definition, multiphase flow is the interactive flow of two or more distinct phases with common interfaces in, say, a conduit. Each phase, representing a volume fraction (or mass fraction) of solid, liquid or gaseous matter, has its own properties, velocity, and temperature.

A multiphase flow can be simultaneous flow of. Bengt Sundén, Juan Fu, in Heat Transfer in Aerospace Applications, Two-Phase Flow Measurements. Two-phase flows under microgravity conditions appear in a large number of important applications in fluid handling and storage and in spacecraft thermal and power systems (e.g., condensers, evaporators, piping system).

The physics of this ubiquitous flow is, however, very. J.J. Ginoux (ed.), Two-Phase Flows and Heat Transfer with Application of Nuclear Reactor Design Problems (Hemisphere Publishing Corporation, Washington, DC, ) Google Scholar E.L.

Piret, H.S. Isbin, Natural circulation evaporation two-phase heat transfer. Heat transfer and phase change phenomena in two-phase flows are often encountered in nuclear reactor systems and are therefore extremely important for their optimal design and safe operation.

The complex phenomena observed especially during transient operation of nuclear reactor systems necessitate extensive theoretical and experimental. Now, heat exchanger reactors, frequently based on CHEs such as the plate-fin or printed circuit types, routinely have catalyst coatings on surfaces where heat transfer takes place.

Applications range from fuel-cell reformers to chemical processes, and extend to the more complex surfaces of the metal foam in Figure A catalyst may be applied.

Over the past two decades, two-phase flow and heat transfer problems associated with two-phase phenomena have been a challenge to many investigators.

Two-phase flow applications are found in a wide range of engineering systems, such as nuclear and conventional power plants, evaporators of refrigeration systems and a wide vari ety of evaporative.

Flow Patterns – Two-phase Flow. One of the most challenging aspects of dealing with two-phase flow or multi-phase flow is the fact that it can take many different forms. Spatial distributions and velocities of the liquid and vapor phases in the flow channel is very important aspect in many engineering re drops and also heat transfer coefficients strongly depends on the local.

@article{osti_, title = {Two-phase flow and heat transfer}, author = {Butterworth, D and Hewitt, G F}, abstractNote = {Introductory and advanced level information for graduate engineers and scientists on liquid-gas and liquid-vapor flow and heat transfer are presented.

The topics discussed include: phase distribution; methods for calculating the pressure gradient; mechanisms for boiling. Integration of fluid flow and heat transfer as applied to single- and two-phase coolants Readers will develop the knowledge and design skills needed to improve the next generation of nuclear reactors.

Heat Transfer and Fluid in Flow Nuclear Systems discusses topics that bridge the gap between the fundamental principles and the designed practices. The book is comprised of six chapters that cover analysis of the predicting thermal-hydraulics performance of large nuclear reactors and associated heat-exchangers or steam generators of various.

Fang, J, & Bolotnov, IA. "Bubble Tracking Simulations of Turbulent Two-Phase Flows." Proceedings of the ASME Fluids Engineering Division Summer Meeting collocated with the ASME Heat Transfer Summer Conference and the ASME 14th International Conference on Nanochannels, Microchannels, and Minichannels.

He has over thirty years of experience in industrial thermal systems analysis, heat exchangers, process equipment, two-phase flow, and HVAC. As a research engineer for DuPont at the Savannah River Site (SRS), Dr.

Harris specialized in heat transfer at high thermal flux in reactors and heat transfer related to nuclear waste processing. Two-phase flow can occur in various forms, such as flows transitioning from pure liquid to vapor as a result of external heating, separated flows, and dispersed two-phase flows where one phase is present in the form of particles, droplets, or bubbles in a continuous carrier phase (i.e.

gas or liquid). These include boiling, condensation, gas-liquid mixtures, and gas-solid mixtures. Two-phase heat transfer is involved in numerous applications. These include heat exchangers in refrigeration and air conditioning, conventional and nuclear power generation, solar power plants, aeronautics, chemical processes, petroleum industry, etc.

Ginoux J.J “Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems”, Hemisphere Publishing Corp.,   Collier, J. G.,“Two-Phase Gas-Liquid Flows Within Rod Bundles,” Turbulent Forced Convection in Channels and Bundles: Theory and Applications to Heat Exchangers and Nuclear Reactors, 2, Hemisphere Publishing Corporation, Washington, DC., pp.

– Book description. Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic.

Boiling flows are an extremely efficient mechanism for the transfer of ultrahigh heat fluxes and used in numerous industrial applications.

In this paper, the accuracy of computational fluid dynamics in predicting the temperature distributions and heat transfer performance is examined within a nuclear fusion reactor divertor.

A collection of the edited lecture notes for a course on two-phase flows with application to nuclear reactor design problems presented at the von Karman Institute for Fluid Dynamics in December Chapter 6 in Boiling Heat Transfer and Two- Phase Flow. 2nd ed. Philadelphia, PA: Taylor and Francis, ISBN: Saha, P., M.

Ishii, and N. Zuber. "An Experimental Investigation of the Thermally Induced Flow Oscillations in Two-Phase Systems." Journal of Heat Transfer 98 (): Critical flow, Lecture by Dr. Pavel. Mohamed S.

El-Genk, PhD, Distinguished and Regents' Professor of Nuclear, Mechanical, Chemical and Biological Engineering and Founding Director of the Institute for Space and Nuclear Power Studies at University of New Mexico (UNM).Before joining UNM, he spent 13 years in the energy and nuclear industries.

Inhe was named the 46th Annual Research Lecturer; one of the highest honors. This Research Topic focuses on nuclear energy, including nuclear fuels, nuclear thermal hydraulics, nuclear power plant (NPP) severe accident, core sub-channel, generation IV NPP concept design, experiment two-phase flow, computation fluid dynamics simulation, and applications of new methods (such as artificial neural networks).

These areas of study are devoted to improving the current. remove large heat fluxes under single-phase and two-phase applications. Heat Transfer and Fluid Flow in book is an ideal reference for anyone involved in the design processes of microchannel flow passages in a heat heat transfer properties, and nuclear reactor system descriptions.

Heat Transfer - Si Units - Sie-J. Holman Acceleration Pressure Drops In Two Phase Flow. Download full Acceleration Pressure Drops In Two Phase Flow Book or read online anytime anywhere, Available in PDF, ePub and Kindle.

Click Get Books and find your favorite books in the online library. Create free account to access unlimited books, fast download and ads free. Applied Heat Transfer Digital Signal Processing Noise Control Systems energy systems.

Derivation of two-phase flow field equations and constitutive relations. Thermal-hydraulic modeling of nuclear reactor systems. Analyses of nuclear reactor safety related phenomena based on conservation principles Introduction to Two-phase Flow (2nd.

Two phase flow: Pressure drop and instabilities: Two phase flow: Critical flow: Two phase heat transfer: Pool boiling: Quiz 2: Take-home, open book, all material from Lectures 8– Two phase heat transfer: Flow boiling: Two phase heat transfer: Boiling crises and post-boiling-crisis heat transfer: Two phase flow and heat.

CTF uses a two-fluid, two-phase flow modeling approach for modeling fluid flow and heat transfer and provides both subchannel and 3D solution options. Flow can be modeled as three independent fields: continuous liquid, vapor, and liquid droplets. Two-phase flow and heat transfer models consider both pre- and post-critical heat flux conditions.

The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly levels, then at the core level, and for one-/two-phase flow transport and heat transfer are treated in depth in respective chapters.

Two phase flow (basic parameters and models) Two phase flow (pressure drop and instabilities) Two phase flow (critical flow) Two phase heat transfer (pool boiling) Quiz 2 (take home) All material from Lec # Two phase heat transfer (flow boiling) Two phase heat transfer (boiling crises and post-boiling-crisis heat.

Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations.

The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation.

Key fluid mechanics, heat transfer. Boiling heat transfer and two-phase flow; Nuclear fuel and reactor materials, severe accident analysis, thermal-hydraulics and safety analysis of space and terrestrial nuclear reactors and spent nuclear fuel dry storage; Dynamic simulation of nuclear reactor power and energy systems and static and dynamic energy conversion.

This book was developed during Professor Ghiaasiaan's twelve years of teaching a graduate-level course on convection heat and mass transfer. It is ideal for a graduate course covering the theory and practice of convection heat and mass transfer.

The book treats well-established theory and practice but is also enriched by its coverage of modern areas such as flow in microchannels. Describe two-phase Systems 2. Describe important thermal -hydraulic concepts important to a BWR 3. Describe two-phase flow equations 4. Describe two phase heat transfer rates from fuel to coolant and Boiling Transition 5.

Describe steady state core temperature profiles 6. Describe fluid flow, and pressure drops in two phase systems 7.

Power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and engineering considerations in reactor design.Fundamentals of thermodynamics, fluid mechanics and heat transfer with application to design and safety of nuclear power plants.

Thermal hydraulic characteristics of nuclear power plants, energy conversion cycles, applications of first and second law of thermodynamics, nuclear heat generation, fluid mechanics, conservation laws and governing equations for inviscid and viscous single-phase flow.Multiphase Flow Dynamics 3 Book Review: Multi-phase flows are part of our natural environment such as tornadoes, typhoons, air and water pollution and volcanic activities as well as part of industrial technology such as power plants, combustion engines, propulsion systems, or .

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