Generation and Size Distribution of Droplet in Annulat Two-phase Flow

Generation and Size Distribution of Droplet in Annulat Two-phase Flow PDF Author: Isao Kataoka
Publisher:
ISBN:
Category :
Languages : en
Pages : 9

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Generation and Size Distribution of Droplet in Annulat Two-phase Flow

Generation and Size Distribution of Droplet in Annulat Two-phase Flow PDF Author: Isao Kataoka
Publisher:
ISBN:
Category :
Languages : en
Pages : 9

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Drop Size Distribution in Annular Two-phase Flow

Drop Size Distribution in Annular Two-phase Flow PDF Author: Steven Ralph Smits
Publisher:
ISBN:
Category : Drops
Languages : en
Pages : 114

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Summary of Reported Droplet Size Distribution Data in Dispersed Two-phase Flow

Summary of Reported Droplet Size Distribution Data in Dispersed Two-phase Flow PDF Author: Raymond Virgil Smith
Publisher:
ISBN:
Category : Fluid dynamics
Languages : en
Pages : 40

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Advances in Two-Phase Flow and Heat Transfer

Advances in Two-Phase Flow and Heat Transfer PDF Author: Sadik Kakaç
Publisher: Springer Science & Business Media
ISBN: 9400968450
Category : Science
Languages : en
Pages : 465

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Book Description
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 and condensive heat exchangers in the chemical industry. This publication is based on the invited lectures presented at the NATO Advanced Research Workshop on the Advances in Two-Phase Flow and Heat Transfer. The Horkshop was attended by more than 50 leading scientists and practicing engineers who work actively on two-phase flow and heat transfer research and applications in dif ferent sectors (academia, government, industry) of member countries of NATO. Some scientific leaders and experts on the subject matter from the non-NATO countries were also invited. They convened to discuss the state-of-the-art in two-phase flow and heat transfer and formulated recommendations for future research directions. To achieve these goals, invited key papers and a limited number of contributions were presented and discussed. The specific aspects of the subject were treated in depth in the panel sessions, and the unresolved problems identified. Suitable as a practical reference, these volumes incorporate a systematic approach to two-phase flow analysis.

Droplets in Annular Two Phase Flow

Droplets in Annular Two Phase Flow PDF Author: David Ruey-Chyi Chang
Publisher:
ISBN:
Category : Two-phase flow
Languages : en
Pages : 484

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Photographic Technique to Determine the Droplet Size Distribution in Two-phase Gas-liquid Flow

Photographic Technique to Determine the Droplet Size Distribution in Two-phase Gas-liquid Flow PDF Author: James Henderson Roberts
Publisher:
ISBN:
Category : Drops
Languages : en
Pages : 102

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THE GENERATION, MOVEMENT, AND DESPOSITION OF DROPLETS IN ANNULAR TWO-PHASE FLOW

THE GENERATION, MOVEMENT, AND DESPOSITION OF DROPLETS IN ANNULAR TWO-PHASE FLOW PDF Author: DAVID R. CHANG
Publisher:
ISBN:
Category :
Languages : en
Pages : 242

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Multiphase Flow Dynamics 5

Multiphase Flow Dynamics 5 PDF Author: Nikolay Ivanov Kolev
Publisher: Springer Science & Business Media
ISBN: 3642206018
Category : Technology & Engineering
Languages : en
Pages : 839

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Book Description
The present Volume 5 of the successful book package "Multiphase Flow Dynamics" is devoted to nuclear thermal hydraulics which is a substantial part of nuclear reactor safety. It provides knowledge and mathematical tools for adequate description of the process of transferring the fission heat released in materials due to nuclear reactions into its environment. It step by step introduces into the heat release inside the fuel, temperature fields in the fuels, the "simple" boiling flow in a pipe described using ideas of different complexity like equilibrium, non equilibrium, homogeneity, non homogeneity. Then the "simple" three-fluid boiling flow in a pipe is described by gradually involving the mechanisms like entrainment and deposition, dynamic fragmentation, collisions, coalescence, turbulence. All heat transfer mechanisms are introduced gradually discussing their uncertainty. Different techniques are introduced like boundary layer treatments or integral methods. Comparisons with experimental data at each step demonstrate the success of the different ideas and models. After an introduction of the design of the reactor pressure vessels for pressurized and boiling water reactors the accuracy of the modern methods is demonstrated using large number of experimental data sets for steady and transient flows in heated bundles. Starting with single pipe boiling going through boiling in the rod bundles the analysis of complete vessel including the reactor is finally demonstrated. Then a powerful method for nonlinear stability analysis of flow boiling and condensation is introduced. Models are presented and their accuracies are investigated for describing critical multiphase flow at different level of complexity. Basics of designing of steam generators, moisture separators and emergency condensers are presented. Methods for analyzing a complex pipe network flows with components like pumps, valves etc. are also presented. Methods for analysis of important aspects of the severe accidents like melt-water interactions, external cooling and cooling of layers of molten nuclear reactor material are presented. Valuable sets of thermo-physical and transport properties for severe accident analysis are presented for the following materials: uranium dioxide, zirconium dioxide, stainless steel, zirconium, aluminum, aluminum oxide, silicon dioxide, iron oxide, molybdenum, boron oxide, reactor corium, sodium, lead, bismuth, and lead-bismuth eutectic alloy. The emphasis is on the complete and consistent thermo dynamical sets of analytical approximations appropriate for computational analysis. Therefore the book presents a complete coverage of the modern Nuclear Thermal Hydrodynamics. This present second edition includes various updates, extensions, improvements and corrections. This present second edition includes various updates, extensions, improvements and corrections.

Annular Two-Phase Flow

Annular Two-Phase Flow PDF Author: Geoffrey Hewitt
Publisher: Elsevier
ISBN: 1483285235
Category : Technology & Engineering
Languages : en
Pages : 327

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Book Description
Annular Two-Phase Flow presents the wide range of industrial applications of annular two-phase flow regimes. This book discusses the fluid dynamics and heat transfer aspects of the flow pattern. Organized into 12 chapters, this book begins with an overview of the classification of the various types of interface distribution observed in practice. This text then examines the various regimes of two-phase flow with emphasis on the regions of occurrence of the annular flow regime. Other chapters consider the single momentum and energy balances, which illustrate the differences and analogies between single- and two-phase flows. This book discusses as well the simple modes for annular flow with consideration to the calculation of the profile of shear stress in the liquid film. The final chapter deals with the techniques that are developed for the measurement of flow pattern, entrainment, and film thickness. This book is a valuable resource for chemical engineers.

Multiphase Flow Dynamics 4

Multiphase Flow Dynamics 4 PDF Author: Nikolay Ivanov Kolev
Publisher: Springer Science & Business Media
ISBN: 3540929185
Category : Technology & Engineering
Languages : en
Pages : 761

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Book Description
The nuclear thermal hydraulic is the science providing knowledge about the physical processes occurring during the transferring the fission heat released in structural materials due to nuclear reactions into its environment. Along its way to the environment the thermal energy is organized to provide useful mechanical work or useful heat or both. Chapter 1 contains introductory information about the heat release in the re- tor core, the thermal power and thermal power density in the fuel, structures and moderator, the influence of the thermal power density on the coolant temperature, the spatial distribution of the thermal power density. Finally some measures are introduced for equalizing of the spatial distribution of the thermal power density. Chapter 2 gives the methods for describing of the steady and of the transient temperature fields in the fuel elements. Some information is provided regarding influence of the cladding oxidation, hydrogen diffusion and of the corrosion pr- uct deposition on the temperature fields. Didactically the nuclear thermal hydraulic needs introductions at different level of complexity by introducing step by step the new features after the previous are clearly presented. The followed two Chapters serve this purpose. Chapter 3 describes mathematically the “simple” steady boiling flow in a pipe. The steady mass-, momentum- and energy conservation equations are solved at different level of complexity by removing one after the other simplifying assu- tions. First the idea of mechanical and thermodynamic equilibrium is introduced.