thermal hydraulics of water cooled nuclear reactors

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Thermal-Hydraulics of Water Cooled Nuclear Reactors
Author : Francesco D'Auria
Publisher : Woodhead Publishing
Release Date : 2017-05-18
ISBN 10 : 0081006799
Pages : 1198 pages

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

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
Author : Ferry Roelofs
Publisher : Woodhead Publishing
Release Date : 2018-11-30
ISBN 10 : 0081019815
Pages : 462 pages

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 : Pradip Saha
Publisher : American Society of Mechanical Engineers
Release Date : 2017-01-23
ISBN 10 : 9780791861288
Pages : 160 pages

This series provides current and future engineers, researchers, technicians and other professionals and practitioners with practical, concise but key information concerning nuclear technologies.

Nuclear Thermal Hydraulic and Two-Phase Flow
Author : Jun Wang,Kaiyi Shi,Zhaoming Meng,Shripad T. Revankar
Publisher : Frontiers Media SA
Release Date : 2018-10-11
ISBN 10 : 2889456129
Pages : 329 pages

Nuclear energy is one of the most important clear energy and contributes more than 10% electric power to human society in the past decades of years. The nuclear thermal hydraulic and two-phase flow is one of the basic branches of nuclear technology and provides structure design and safety analysis to the nuclear power reactors. In the new century, the basic theoretical research of thermal hydraulic and two-phase flow, and innovative design for the next generation nuclear power plants (especially for the small modular reactor and molten salt reactor), along with other nuclear branches, constantly support the development of nuclear technology.

Thermal-Hydraulic Analysis of Nuclear Reactors
Author : Bahman Zohuri
Publisher : Springer
Release Date : 2017-05-23
ISBN 10 : 3319538292
Pages : 835 pages

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.

Heat Transfer and Fluid Flow in Nuclear Systems
Author : Henri Fenech
Publisher : Elsevier
Release Date : 2013-10-22
ISBN 10 : 148315078X
Pages : 590 pages

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.

Nuclear Thermal Hydraulics
Author : Hajime Akimoto,Yoshinari Anoda,Kazuyuki Takase,Hiroyuki Yoshida,Hidesada Tamai
Publisher : Springer
Release Date : 2016-11-10
ISBN 10 : 4431556036
Pages : 458 pages

This volume provides fundamentals of nuclear thermal–hydraulics for reactor design and safety assessment. It also describes the basis for assessing cooling performance of nuclear reactors under accidental conditions. The descriptions in this book are virtually self-contained, beyond the assumption that readers are familiar with the introductory levels of nuclear engineering. This book helps readers understand the processes for nuclear reactor plant design and the most important factors in nuclear thermal-hydraulics.

Handbook of Generation IV Nuclear Reactors
Author : Igor Pioro
Publisher : Woodhead Publishing
Release Date : 2016-06-09
ISBN 10 : 0081001622
Pages : 940 pages

Handbook of Generation IV Nuclear Reactors presents information on the current fleet of Nuclear Power Plants (NPPs) with water-cooled reactors (Generation III and III+) (96% of 430 power reactors in the world) that have relatively low thermal efficiencies (within the range of 32 36%) compared to those of modern advanced thermal power plants (combined cycle gas-fired power plants – up to 62% and supercritical pressure coal-fired power plants – up to 55%). Moreover, thermal efficiency of the current fleet of NPPs with water-cooled reactors cannot be increased significantly without completely different innovative designs, which are Generation IV reactors. Nuclear power is vital for generating electrical energy without carbon emissions. Complete with the latest research, development, and design, and written by an international team of experts, this handbook is completely dedicated to Generation IV reactors. Presents the first comprehensive handbook dedicated entirely to generation IV nuclear reactors Reviews the latest trends and developments Complete with the latest research, development, and design information in generation IV nuclear reactors Written by an international team of experts in the field

Super Light Water Reactors and Super Fast Reactors
Author : Yoshiaki Oka,Seiichi Koshizuka,Yuki Ishiwatari,Akifumi Yamaji
Publisher : Springer Science & Business Media
Release Date : 2010-07-01
ISBN 10 : 1441960341
Pages : 651 pages

Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.

Nuclear Systems: Thermal hydraulic fundamentals
Author : Neil E. Todreas,Mujid S. Kazimi
Publisher : Hemisphere Pub
Release Date : 1990
ISBN 10 :
Pages : 705 pages

Provides an examination of nuclear systems focusing on thermal hydraulic design and analysis of the nuclear core. The coverage includes fluid flow and heat transfer, various reactor types and energy source distribution.

Natural Circulation in Water Cooled Nuclear Power Plants
Author : International Atomic Energy Agency
Publisher : IAEA
Release Date : 2005
ISBN 10 :
Pages : 635 pages

This publication describes the present state of knowledge on natural circulation in water cooled nuclear power plants and passive system reliability, including information on phenomena, models, predictive tools and experiments that currently support design and analysis of natural circulation systems, and highlights areas where additional research is needed.

Nuclear Engineering Handbook, Second Edition
Author : Kenneth D. Kok
Publisher : CRC Press
Release Date : 2016-10-03
ISBN 10 : 1315356309
Pages : 978 pages

Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.