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Thermal-Hydraulics of Water Cooled Nuclear Reactors

Thermal-Hydraulics of Water Cooled Nuclear Reactors
  • Author : Francesco D'Auria
  • Publisher :Unknown
  • Release Date :2017-05-18
  • Total pages :1198
  • ISBN : 9780081006795
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Summary : 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

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
  • Author : Ferry Roelofs
  • Publisher :Unknown
  • Release Date :2018-11-30
  • Total pages :462
  • ISBN : 9780081019818
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Summary : 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

NUCLEAR REACTOR THERMAL-HYDRAU

NUCLEAR REACTOR THERMAL-HYDRAU
  • Author : Pradip Saha
  • Publisher :Unknown
  • Release Date :2017-01-23
  • Total pages :160
  • ISBN : 0791861287
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Summary : 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

Nuclear Thermal Hydraulic and Two-Phase Flow
  • Author : Jun Wang,Kaiyi Shi,Zhaoming Meng,Shripad T. Revankar
  • Publisher :Unknown
  • Release Date :2018-10-11
  • Total pages :229
  • ISBN : 9782889456123
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Summary : 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

Thermal-Hydraulic Analysis of Nuclear Reactors
  • Author : Bahman Zohuri
  • Publisher :Unknown
  • Release Date :2017-05-23
  • Total pages :835
  • ISBN : 9783319538297
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Summary : 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

Heat Transfer and Fluid Flow in Nuclear Systems
  • Author : Henri Fenech
  • Publisher :Unknown
  • Release Date :2013-10-22
  • Total pages :590
  • ISBN : 9781483150789
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Summary : 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

Nuclear Thermal Hydraulics
  • Author : Hajime Akimoto,Yoshinari Anoda,Kazuyuki Takase,Hiroyuki Yoshida,Hidesada Tamai
  • Publisher :Unknown
  • Release Date :2016-11-10
  • Total pages :458
  • ISBN : 9784431556039
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Summary : 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.

Natural Circulation in Water Cooled Nuclear Power Plants

Natural Circulation in Water Cooled Nuclear Power Plants
  • Author : International Atomic Energy Agency
  • Publisher :Unknown
  • Release Date :2005
  • Total pages :635
  • ISBN : UOM:39015062489375
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Summary : 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.

Handbook of Generation IV Nuclear Reactors

Handbook of Generation IV Nuclear Reactors
  • Author : Igor Pioro
  • Publisher :Unknown
  • Release Date :2016-06-09
  • Total pages :940
  • ISBN : 9780081001622
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Summary : 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

Nuclear Engineering Handbook, Second Edition

Nuclear Engineering Handbook, Second Edition
  • Author : Kenneth D. Kok
  • Publisher :Unknown
  • Release Date :2016-10-03
  • Total pages :978
  • ISBN : 9781315356303
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Summary : 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.

Dynamics and Control of Nuclear Reactors

Dynamics and Control of Nuclear Reactors
  • Author : Thomas W. Kerlin,Belle R. Upadhyaya
  • Publisher :Unknown
  • Release Date :2019-10-05
  • Total pages :402
  • ISBN : 9780128152621
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Summary : Dynamics and Control of Nuclear Reactors presents the latest knowledge and research in reactor dynamics, control and instrumentation; important factors in ensuring the safe and economic operation of nuclear power plants. This book provides current and future engineers with a single resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic characteristics of pressurized light-water reactors, boiling light-water reactors, pressurized heavy-water reactors and molten-salt reactors. It also provides pertinent, but less detailed information on small modular reactors, sodium fast reactors, and gas-cooled reactors. Provides case studies and examples to demonstrate learning through problem solving, including an analysis of accidents at Three Mile Island, Chernobyl and Fukushima Daiichi Includes MATLAB codes to enable the reader to apply the knowledge gained to their own projects and research Features examples and problems that illustrate the principles of dynamic analysis as well as the mathematical tools necessary to understand and apply the analysis Publishers Note: Table 3.1 has been revised and will be included in future printings of the book with the following data: Group Decay Constant, li (sec-1) Delayed Neutron Fraction (bi) 1 0.0124 0.000221 2 0.0305 0.001467 3 0.111 0.001313 4 0.301 0.002647 5 1.14 0.000771 6 3.01 0.000281 Total delayed neutron fraction: 0.0067

Super Light Water Reactors and Super Fast Reactors

Super Light Water Reactors and Super Fast Reactors
  • Author : Yoshiaki Oka,Seiichi Koshizuka,Yuki Ishiwatari,Akifumi Yamaji
  • Publisher :Unknown
  • Release Date :2010-07-01
  • Total pages :651
  • ISBN : 9781441960344
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Summary : 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.

Thermal Analysis of Pressurized Water Reactors

Thermal Analysis of Pressurized Water Reactors
  • Author : Long-sun Tong,Joel Weisman
  • Publisher :Unknown
  • Release Date :1979
  • Total pages :417
  • ISBN : UOM:39015004509132
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Summary :

Nuclear Systems: Thermal hydraulic fundamentals

Nuclear Systems: Thermal hydraulic fundamentals
  • Author : Neil E. Todreas,Mujid S. Kazimi
  • Publisher :Unknown
  • Release Date :1990
  • Total pages :705
  • ISBN : UOM:39015016978010
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Summary : 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.

Combined Cycle Driven Efficiency for Next Generation Nuclear Power Plants

Combined Cycle Driven Efficiency for Next Generation Nuclear Power Plants
  • Author : Bahman Zohuri
  • Publisher :Unknown
  • Release Date :2015-03-14
  • Total pages :359
  • ISBN : 9783319155609
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Summary : Introduces the concept of combined cycles for next generation nuclear power plants, explaining how recent advances in gas turbines have made these systems increasingly desirable for efficiency gains and cost-of-ownership reduction. Promulgates modelling and analysis techniques to identify opportunities for increased thermodynamic efficiency and decreased water usage over current Light Water Reactor (LWR) systems. Examines all power conversion aspects, from the fluid exiting the reactor to energy releases into the environment, with special focus on heat exchangers and turbo-machinery. Provides examples of small projects to facilitate nuanced understanding of the theories and implementation of combined-cycle nuclear plants. This book explores combined cycle driven efficiency of new nuclear power plants and describes how to model and analyze a nuclear heated multi-turbine power conversion system operating with atmospheric air as the working fluid. The included studies are intended to identify paths for future work on next generation nuclear power plants (GEN-IV), leveraging advances in natural-gas-fired turbines that enable coupling salt-cooled, helium-cooled, and sodium-cooled reactors to a Nuclear Air-Brayton Combined Cycle (NACC). These reactors provide the option of operating base-load nuclear plants with variable electricity output to the grid using natural gas or stored heat to produce peak power. The author describes overall system architecture, components and detailed modelling results of Brayton-Rankine Combined Cycle power conversion systems and Recuperated Brayton Cycle systems, since they offer the highest overall energy conversion efficiencies. With ever-higher temperatures predicted in GEN-IV plants, this book’s investigation of potential avenues for thermodynamic efficiency gains will be of great interest to nuclear engineers and researchers, as well as power plant operators and students.

Nuclear Reactor Design

Nuclear Reactor Design
  • Author : Yoshiaki Oka
  • Publisher :Unknown
  • Release Date :2014-06-11
  • Total pages :327
  • ISBN : 9784431548980
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Summary : This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

Coolant Flow Instabilities in Power Equipment

Coolant Flow Instabilities in Power Equipment
  • Author : Vladimir B. Khabensky,Vladimir Antonovich Gerliga
  • Publisher :Unknown
  • Release Date :2012-12-17
  • Total pages :388
  • ISBN : 9781466567047
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Summary : 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.

Thermo-Hydraulics of Nuclear Reactors

Thermo-Hydraulics of Nuclear Reactors
  • Author : Christopher Earls Brennen
  • Publisher :Unknown
  • Release Date :2016-05-20
  • Total pages :160
  • ISBN : 9781107139602
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Summary : This book provides a summary of thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. It includes summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima and the major improvements to reactor safety that grew out of those accidents.

Single-phase, Two-phase and Supercritical Natural Circulation Systems

Single-phase, Two-phase and Supercritical Natural Circulation Systems
  • Author : Pallippattu Krishnan Vijayan,Arun K. Nayak,Naveen Kumar
  • Publisher :Unknown
  • Release Date :2019-06-19
  • Total pages :650
  • ISBN : 9780081024874
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Summary : Single-Phase, Two-Phase and Supercritical Natural Circulation Systems provides readers with a deep understanding of natural circulation systems. This book equips the reader with an understanding on how to detect unstable loops to ensure plant safety and reliability, calculate heat transport capabilities, and design effective natural circulation loops, stability maps and parallel channel systems. Each chapter begins with an introduction to the circulation system before discussing each element in detail and analyzing its effect on the performance of the system. The book also presents thermosyphon heat transport devices in nuclear and other industrial plants, a common information need for students and researchers alike. This book is invaluable for engineers, designers, operators and consultants in nuclear, mechanical, electrical and chemical disciplines. Presents single-phase, two-phase and supercritical natural circulation systems together in one resource to fill an existing knowledge gap Guides the reader through relevant processes, such as designing, analyzing and generating stability maps and natural circulation loops, calculating heat transport capabilities, and maintaining natural circulation system operations Includes global case studies and examples to increase understanding, along with important IAEA standards and procedures

Heat Pipe Applications in Fission Driven Nuclear Power Plants

Heat Pipe Applications in Fission Driven Nuclear Power Plants
  • Author : Bahman Zohuri
  • Publisher :Unknown
  • Release Date :2019-02-14
  • Total pages :362
  • ISBN : 9783030058821
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Summary : This book presents a new and innovative approach for the use of heat pipes and their application in a number of industrial scenarios, including space and nuclear power plants. The book opens by describing the heat pipe and its concept, including sizing, composition and binding energies. It contains mathematical models of high and low temperature pipes along with extensive design and manufacturing models, characteristics and testing programs. A detailed design and safety analysis concludes the book, emphasizing the importance of heat pipe implementation within the main cooling system and within the core of the reactor, making this book a useful resource for students, engineers, and researchers.

Heat Transfer and Hydraulic Resistance at Supercritical Pressures in Power Engineering Applications

Heat Transfer and Hydraulic Resistance at Supercritical Pressures in Power Engineering Applications
  • Author : Igorʹ Leonardovich Pioro,Romney B. Duffey
  • Publisher :Unknown
  • Release Date :2007
  • Total pages :334
  • ISBN : STANFORD:36105128372765
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Summary : Mechanical and Nuclear Engineers are currently working on advanced power plants intended for implementation within the next decade. One such Generation IV concept is a supercritical, water-cooled nuclear reactor. In addition, there are already hundreds of supercritical steam generators operating worldwide in the thermal power industry. These system designs reduce emissions and lower cost by attaining high thermodynamic cycle and economic efficiency, utilizing both natural and forced circulation flows and optimizing heat exchanger and turbine layout and performance. Development, design, and successful operation of these power-generating units require knowledge of heat transfer, pressure drop, and thermalhydraulics at supercritical pressures. Demand for reliable information is high, and until now, no single book related to this topic has been published.This book brings together and integrates the results from over 500 of the latest sources from the global publications devoted to heat transfer and hydraulic resistance of fluids flowing inside channels of various geometries at near-critical and supercritical pressures. This book is of interest to nuclear and mechanical engineers in both industry and academia, who are concerned with the development and design of next-generation reactors, as well as engineers and technologists currently working with supercritical steam generators and power systems. Included with this book is a free CD containing fully linked references to help readers navigate the welath of material that is provided.