Thermal Hydraulics Aspects Of Liquid Metal Cooled Nuclear Reactors

Author : Ferry Roelofs
Publisher : Woodhead Publishing
Page : 464 pages
File Size : 52,9 Mb
Release : 2018-11-30
Category : Science
ISBN : 9780081019818

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Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors by Ferry Roelofs Pdf

Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. Presents the latest information on one of the deliverables of the SESAME H2020 project Provides an overview on the design and history of liquid metal cooled fast reactors worldwide Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications

Author : Francesco D'Auria
Publisher : Woodhead Publishing
Page : 1198 pages
File Size : 50,9 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

Author : Henri Fenech
Publisher : Elsevier
Page : 590 pages
File Size : 54,8 Mb
Release : 2013-10-22
Category : Science
ISBN : 9781483150789

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Heat Transfer and Fluid Flow in Nuclear Systems by Henri Fenech Pdf

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.

Author : Bahman Zohuri
Publisher : Springer
Page : 835 pages
File Size : 55,5 Mb
Release : 2017-05-23
Category : Technology & Engineering
ISBN : 9783319538297

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Thermal-Hydraulic Analysis of Nuclear Reactors by Bahman Zohuri Pdf

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.

Author : Neil E. Todreas,Mujid S. Kazimi,Mahmoud Massoud
Publisher : CRC Press
Page : 659 pages
File Size : 53,9 Mb
Release : 2021-12-13
Category : Science
ISBN : 9781482239591

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Nuclear Systems Volume II by Neil E. Todreas,Mujid S. Kazimi,Mahmoud Massoud Pdf

Discusses fundamental ideas for various modeling approaches for the macro- and micro-scale flow conditions in the reactor. Covers specific design considerations, such as natural convection and core reliability. Enables the reader to better understand the importance of safety considerations in thermal engineering and analysis of a modern nuclear plant. Features end-of-chapter problems. Includes a Solutions Manual for adopting instructors.

Author : Heinz Martin Kottowski-Dümenil
Publisher : Unknown
Page : 397 pages
File Size : 48,6 Mb
Release : 1994
Category : Heat
ISBN : 3926956224

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Liquid Metal Thermal-hydraulics by Heinz Martin Kottowski-Dümenil Pdf

Author : R. H. S. Winterton
Publisher : Elsevier
Page : 206 pages
File Size : 49,9 Mb
Release : 2014-04-23
Category : Technology & Engineering
ISBN : 9781483145242

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Thermal Design of Nuclear Reactors by R. H. S. Winterton Pdf

Thermal Design of Nuclear Reactors

Author : Richard T. Lahey,Frederick J. Moody
Publisher : Unknown
Page : 658 pages
File Size : 48,7 Mb
Release : 1993
Category : Science
ISBN : UOM:39015038123025

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The Thermal-hydraulics of a Boiling Water Nuclear Reactor by Richard T. Lahey,Frederick J. Moody Pdf

This edition of the classic monograph gives a comprehensive overview of the thermal-hydraulic technology underlying the design, operation, and safety assessment of boiling water reactors. In addition, new material on pressure suppression containment technology is presented.

Author : International Atomic Energy Agency
Publisher : IAEA Tecdoc
Page : 211 pages
File Size : 54,7 Mb
Release : 2013-09-13
Category : Science
ISBN : 9201399103

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Challenges Related to the Use of Liquid Metal and Molten Salt Coolants in Advanced Reactors by International Atomic Energy Agency Pdf

This publication documents the results of experimental investigations and computational fluid dynamics studies on thermal hydraulics, specifically models and correlations on pressure drop and heat transfer involving to liquid metal and molten salt coolants under different operating conditions, including the feedback on neutronics effects. It presents new or verifies existing data on thermo-physical properties of liquid metal and molten salt coolants, and describes tools for on-line monitoring and control of coolant chemistry. Methods to improve the corrosion resistance between heavy liquid metal coolant and components, structure material and instrumentation are also examined.

Author : Donna Guillen
Publisher : BoD – Books on Demand
Page : 204 pages
File Size : 47,8 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.

Author : Songbai Cheng,Wenzhong Zhou,Long Gu,Hongli Chen,Di Yun,Koji Morita,Hidemasa Yamano,Shripad T. Revankar
Publisher : Frontiers Media SA
Page : 244 pages
File Size : 48,9 Mb
Release : 2023-03-03
Category : Technology & Engineering
ISBN : 9782832516768

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Experimental and numerical studies on liquid metal cooled fast reactors by Songbai Cheng,Wenzhong Zhou,Long Gu,Hongli Chen,Di Yun,Koji Morita,Hidemasa Yamano,Shripad T. Revankar Pdf

Author : R. D. Brooks,A. L. Rosenblatt
Publisher : Unknown
Page : 12 pages
File Size : 51,8 Mb
Release : 1953
Category : Nuclear power plants
ISBN : UOM:39015095098193

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Nuclear Power Plants by R. D. Brooks,A. L. Rosenblatt Pdf

Author : F. Roelofs,P. Planquart
Publisher : Unknown
Page : 128 pages
File Size : 49,8 Mb
Release : 2017
Category : Electronic
ISBN : 2875161148

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Thermohydraulics and Chemistry of Liquid Metal Cooled Reactors by F. Roelofs,P. Planquart Pdf

Author : Yu S. Tang,R. D. Coffield,R. A. Markley
Publisher : American Nuclear Society
Page : 432 pages
File Size : 41,7 Mb
Release : 1978
Category : Technology & Engineering
ISBN : UOM:39015004474311

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Thermal Analysis of Liquid-metal Fast Breeder Reactors by Yu S. Tang,R. D. Coffield,R. A. Markley Pdf

This monograph is written as a treatise on the state-of-the-art of liquid-metal fast breeder reactor thermal and hydraulic design and analysis.

Author : Neil E. Todreas,Mujid S. Kazimi
Publisher : CRC Press
Page : 927 pages
File Size : 54,9 Mb
Release : 2021-01-11
Category : Science
ISBN : 9781351030496

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Nuclear Systems Volume I by Neil E. Todreas,Mujid S. Kazimi Pdf

Offers rigorous coverage of nuclear power generation fundamentals. Provides description and analysis of the latest nuclear power plant designs and technologies. Includes extensive examples in each chapter to illustrate the analysis methods, which are also presented. Includes program code to demonstrate computer analysis of nuclear power generation. Provides an integration of fluid flow and heat transfer, as applied to single- and two-phase coolants.