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Two-Phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems

Two-Phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems PDF Author:
Publisher:
ISBN: 9780070233058
Category :
Languages : en
Pages :

Book Description


Two-Phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems

Two-Phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems PDF Author:
Publisher:
ISBN: 9780070233058
Category :
Languages : en
Pages :

Book Description


Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems

Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems PDF Author: Jean J. Ginoux
Publisher: Hemisphere Pub
ISBN:
Category : Science
Languages : en
Pages : 488

Book Description


Advances in Two-Phase Flow and Heat Transfer

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

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.

Advances in Two-Phase Flow and Heat Transfer

Advances in Two-Phase Flow and Heat Transfer PDF Author: Sadik KakaƧ
Publisher: Springer Science & Business Media
ISBN: 9400968485
Category : Science
Languages : en
Pages : 459

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.

Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems

Two-phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems PDF Author: Jean J. Ginoux
Publisher: Hemisphere Pub
ISBN:
Category : Science
Languages : en
Pages : 488

Book Description


Heat Transfer and Fluid Flow in Nuclear Systems

Heat Transfer and Fluid Flow in Nuclear Systems PDF Author: Henri Fenech
Publisher: Elsevier
ISBN: 148315078X
Category : Science
Languages : en
Pages : 591

Book Description
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 nuclear systems. Chapter 1 tackles the general considerations on thermal design and performance requirements of nuclear reactor cores. The second chapter deals with pressurized subcooled light water systems, and the third chapter covers boiling water reactor systems. Chapter 4 tackles liquid metal cooled systems, while Chapter 5 discusses helium cooled systems. The last chapter deals with heat-exchangers and steam generators. The book will be of great help to engineers, scientists, and graduate students concerned with thermal and hydraulic problems.

Two-Phase Flow, Boiling, and Condensation

Two-Phase Flow, Boiling, and Condensation PDF Author: S. Mostafa Ghiaasiaan
Publisher: Cambridge University Press
ISBN: 1316785300
Category : Technology & Engineering
Languages : en
Pages : 1322

Book Description
Providing a comprehensive introduction to the fundamentals and applications of flow and heat transfer in conventional and miniature systems, this fully enhanced and updated edition covers all the topics essential for graduate courses on two-phase flow, boiling, and condensation. Beginning with a concise review of single-phase flow fundamentals and interfacial phenomena, detailed and clear discussion is provided on a range of topics, including two-phase hydrodynamics and flow regimes, mathematical modeling of gas-liquid two-phase flows, pool and flow boiling, flow and boiling in mini and microchannels, external and internal-flow condensation with and without noncondensables, condensation in small flow passages, and two-phase choked flow. Numerous solved examples and end-of-chapter problems that include many common design problems likely to be encountered by students, make this an essential text for graduate students. With up-to-date detail on the most recent research trends and practical applications, it is also an ideal reference for professionals and researchers in mechanical, nuclear, and chemical engineering.

A New Method for Determining the Stability of Two-phase Flow in Parallel Heated Channels with Applications to Nuclear Reactors

A New Method for Determining the Stability of Two-phase Flow in Parallel Heated Channels with Applications to Nuclear Reactors PDF Author: J. H. Bick
Publisher:
ISBN:
Category : Fluid dynamics
Languages : en
Pages : 36

Book Description


Thermal-Hydraulic Analysis of Nuclear Reactors

Thermal-Hydraulic Analysis of Nuclear Reactors PDF Author: Bahman Zohuri
Publisher: Springer
ISBN: 3319538292
Category : Technology & Engineering
Languages : en
Pages : 845

Book Description
This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.

Multiphase Flow Dynamics 5

Multiphase Flow Dynamics 5 PDF Author: Nikolay Ivanov Kolev
Publisher: Springer
ISBN: 3319151568
Category : Technology & Engineering
Languages : en
Pages : 911

Book Description
This 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. Therefore the book presents a complete coverage of the modern Nuclear Thermal Hydrodynamics. This present third edition includes various updates, extensions, improvements and corrections.