Thermo Hydraulic Instabilities

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Thermo-hydraulic Instabilities

Author : J-M. Buchlin,Pierre Colinet
Publisher : Unknown
Page : 518 pages
File Size : 52,7 Mb
Release : 2007
Category : Fluid dynamics
ISBN : PSU:000062645508

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Thermo-hydraulic Instabilities by J-M. Buchlin,Pierre Colinet Pdf

Nuclear Reactor Thermal Hydraulics

Author : Robert E. Masterson
Publisher : CRC Press
Page : 1354 pages
File Size : 47,9 Mb
Release : 2019-08-21
Category : Science
ISBN : 9781351849524

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Nuclear Reactor Thermal Hydraulics by Robert E. Masterson Pdf

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, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students. A complete Solutions Manual is available for professors adopting the text.

Coolant Flow Instabilities in Power Equipment

Author : Vladimir B. Khabensky,Vladimir Antonovich Gerliga
Publisher : CRC Press
Page : 388 pages
File Size : 43,5 Mb
Release : 2012-12-17
Category : Science
ISBN : 9781466567054

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Coolant Flow Instabilities in Power Equipment by Vladimir B. Khabensky,Vladimir Antonovich Gerliga Pdf

Thermal-hydraulic instability can potentially impair thermal reliability of reactor cores or other power equipment components. Thus it is important to address stability issues in power equipment associated with thermal and nuclear installations, particularly in thermal nuclear power plants, chemical and petroleum industries, space technology, and radio, electronic, and computer cooling systems. Coolant Flow Instabilities in Power Equipment synthesizes results from instability investigations around the world, presenting an analysis and generalization of the published technical literature. The authors include individual examples on flow stability in various types of equipment, including boilers, reactors, steam generators, condensers, heat exchangers, turbines, pumps, deaerators, bubblers, and pipelines. They also present information that has not been widely available until recently, such as thermal-acoustic instability, flow instability with supercritical parameters, and single-phase coolant flow static instability. The material described in this book is derived from vast amounts of experimental data from thermal-physical test facilities and full-scale installations. It is presented in a manner accessible to readers without advanced mathematical backgrounds. Particular attention has been paid to oscillatory (low-frequency and thermal-acoustic) and static thermal-hydraulic coolant flow instability. In addition, the physical mechanism of instability has been considered in detail. This book provides knowledge of the various types of flow instability, the equipment where this instability can manifest, and the ensuing consequences, as well as makes recommendations concerning possible removal or mitigation of these consequences. The authors provide this information as a useful reference for readers to facilitate the enhanced safety of modern power equipment through qualitative evaluation of design and flow parameters and subsequent selection of the optimal means for increasing flow stability.

Thermal Hydraulics

Author : Maurizio Cumo
Publisher : CRC Press
Page : 163 pages
File Size : 53,8 Mb
Release : 2018-01-18
Category : Technology & Engineering
ISBN : 9781351085717

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Thermal Hydraulics by Maurizio Cumo Pdf

This text, including the description of the most relevant phenomenologies and of some advanced techniques in heat transfer with fluids, is mainly aimed at engineers using design or computer analysis programs and codes, in order to achieve a deeper understanding of the phenomenologies and of the applied analysis methods. This text will be helpful to people engaged in developing original computer programs or design methods, because they may find in it basic information on the computer program-oriented solutions of the conservation equations and of the various flow and heat transfer mechanisms. The selection of up-to-date correlations in various heat and mass transfer branches represents, for the designers using traditional techniques, a helpful instrument to integrate the basic handbooks.The trial of representing phenomenologies and problems through elementary concepts makes this text useful to students at the graduate level involved in the study of fluid flow and heat transfer.

Thermal-Hydraulics of Water Cooled Nuclear Reactors

Author : Francesco D'Auria
Publisher : Woodhead Publishing
Page : 1198 pages
File Size : 54,8 Mb
Release : 2017-05-18
Category : Technology & Engineering
ISBN : 9780081006795

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Thermal-Hydraulics of Water Cooled Nuclear Reactors by Francesco D'Auria Pdf

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 analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants

Numerical Simulation of Power Plants and Firing Systems

Author : Heimo Walter,Bernd Epple
Publisher : Springer
Page : 815 pages
File Size : 46,8 Mb
Release : 2017-04-18
Category : Technology & Engineering
ISBN : 9783709148556

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Numerical Simulation of Power Plants and Firing Systems by Heimo Walter,Bernd Epple Pdf

The book comprises the fundamentals of the numerical simulation of fluid flows as well as the modelling of a power plant and plant components. The fundamental equations for heat and mass transfer will be prepared for the application in the numerical simulation. Selected numerical methods will be discussed in detail. The book will deal with the gas as well as with the water/steam flow. Regulation and controller, simplified models and hybrid models as well as the validation of measurement data are also included in the book.

Nuclear Safety

Author : Anonim
Publisher : Unknown
Page : 600 pages
File Size : 49,6 Mb
Release : 1988
Category : Nuclear engineering
ISBN : STANFORD:36105029357519

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Nuclear Safety by Anonim Pdf

Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs

Author : Masahiro Furuya
Publisher : IOS Press
Page : 148 pages
File Size : 42,8 Mb
Release : 2006
Category : Technology & Engineering
ISBN : 158603605X

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Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs by Masahiro Furuya Pdf

20% of the Nuclear Power Plants are known as Boiling Water Reactors (BWRs). These BWRs have pumps that cool their reactor. In the design of new BWRs, ways to cool the core by a natural circulation flow, without pumps, also called natural circulation BWRs, are being considered. In these new systems, a chimney is installed on top of the core to increase natural circulation flow. A possible disadvantage of natural circulation BWRs might be their susceptibility to instabilities, which could then lead to both flow and power oscillations. The stability features of both natural circulation and forced circulation BWRs have been investigated thoroughly, using dedicated experimental setups, analytical models and numerical codes. We distinguish between pure thermal-hydraulic stability - where the fission power is assumed to be constant - and coupled thermalhydraulic-neutronic stability - where the two-phase mixture in the core influences the fission chain reaction...

Multiphase Flow Dynamics 5

Author : Nikolay Ivanov Kolev
Publisher : Springer Science & Business Media
Page : 818 pages
File Size : 47,8 Mb
Release : 2011-10-18
Category : Technology & Engineering
ISBN : 9783642206016

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Multiphase Flow Dynamics 5 by Nikolay Ivanov Kolev Pdf

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.

Federal Register

Author : Anonim
Publisher : Unknown
Page : 1114 pages
File Size : 55,6 Mb
Release : 1985-02-22
Category : Administrative law
ISBN : UIUC:30112059138716

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Federal Register by Anonim Pdf

Multiphase Flow Dynamics 4

Author : Nikolay Ivanov Kolev
Publisher : Springer Science & Business Media
Page : 761 pages
File Size : 49,8 Mb
Release : 2009-06-12
Category : Technology & Engineering
ISBN : 9783540929185

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Multiphase Flow Dynamics 4 by Nikolay Ivanov Kolev Pdf

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.

Nuclear Reactor Thermal Hydraulics and Other Applications

Author : Donna Guillen
Publisher : BoD – Books on Demand
Page : 204 pages
File Size : 47,6 Mb
Release : 2013-02-13
Category : Technology & Engineering
ISBN : 9789535109877

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Nuclear Reactor Thermal Hydraulics and Other Applications by Donna Guillen Pdf

This book includes contributions from researchers around the world on numerical developments and applications to predict fluid flow and heat transfer, with an emphasis on thermal hydraulics computational fluid dynamics. Our ability to simulate larger problems with greater fidelity has vastly expanded over the past decade. The collection of material presented in this book augments the ever-increasing body of knowledge concerning the important topic of thermal hydraulics. Featured topics include coolant channel analysis, thermal hydraulic transport and mixing, as well as hydrodynamics and heat transfer processes. The contents of this book will interest researchers, scientists, engineers and graduate students.

Computational Science and Its Applications - ICCSA 2011

Author : Beniamino Murgante,Osvaldo Gervasi,Andres Iglesias,David Taniar,Bernady O. Apduhan
Publisher : Springer
Page : 718 pages
File Size : 53,9 Mb
Release : 2011-06-17
Category : Computers
ISBN : 9783642218873

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Computational Science and Its Applications - ICCSA 2011 by Beniamino Murgante,Osvaldo Gervasi,Andres Iglesias,David Taniar,Bernady O. Apduhan Pdf

The five-volume set LNCS 6782 - 6786 constitutes the refereed proceedings of the International Conference on Computational Science and Its Applications, ICCSA 2011, held in Santander, Spain, in June 2011. The five volumes contain papers presenting a wealth of original research results in the field of computational science, from foundational issues in computer science and mathematics to advanced applications in virtually all sciences making use of computational techniques. The topics of the fully refereed papers are structured according to the five major conference themes: geographical analysis, urban modeling, spatial statistics; cities, technologies and planning; computational geometry and applications; computer aided modeling, simulation, and analysis; and mobile communications.

Proceedings of International Conference on Thermofluids

Author : Shripad Revankar,Swarnendu Sen,Debjyoti Sahu
Publisher : Springer Nature
Page : 676 pages
File Size : 42,6 Mb
Release : 2020-11-21
Category : Technology & Engineering
ISBN : 9789811578311

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Proceedings of International Conference on Thermofluids by Shripad Revankar,Swarnendu Sen,Debjyoti Sahu Pdf

This book presents selected and peer-reviewed proceedings of the International Conference on Thermofluids (KIIT Thermo 2020). It focuses on the latest studies and findings in the areas of fluid dynamics, heat transfer, thermodynamics, and combustion. Some of the topics covered in the book include electronic cooling, HVAC system analysis, inverse heat transfer, combustion, nano-fluids, multiphase flow, high-speed flow, and shock waves. The book includes both experimental and numerical studies along with a few review chapters from experienced researchers, and is expected to lead to new research in this important area. This book is of interest to students, researchers as well as practitioners working in the areas of fluid dynamics, thermodynamics, and combustion.