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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
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.
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.
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
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.
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.
This book introduces readers to basic approaches in and principles of marine nuclear power design, including overall reactor design, in-core design, coolant systems and devices, I&C system design, safety system design, and dynamic analysis assessment. It comprehensively reviews both the fundamentals of and latest trends in nuclear-powered devices, covering their entire lifespan, from design and testing to operation and decommissioning. Further, it explores in detail various real-world conditions in the marine context – such as insufficient space for equipment deployment and frequently changing operating conditions as well as swinging and tilting. Offering extensive information on the design and operation of marine nuclear power systems, the book is a valuable resource for researchers and professionals in the area of marine science and nuclear engineering, and graduate students intending to embark on a career in the field.
Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. - Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors - Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes - Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting
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.
Fundamentals of Thermal and Nuclear Power Generation is the first volume in the JSME Series in Thermal and Nuclear Power Generation. The first part of this volume provides a thorough and complete reference on the history of thermal and nuclear power generation, which has informed and sculpted today's industry. It prepares readers for subsequent publications in the series that address more advanced topics and will particularly benefit early career researchers and those approaching the industry from an alternative discipline. Modern thermal and nuclear power generation systems and technologies are then explored, including clear analysis on the fundamentals of thermodynamics, hydrodynamics, thermal engineering, combustion engineering, and nuclear physics. The impact of these technologies on society is considered throughout, as well as supply issues, accident risk analysis, and important emission and sustainability considerations. This book is an invaluable resource for researchers and professional engineers in nuclear and thermal energy engineering, and postgraduate and undergraduate students in power generation, especially nuclear and thermal. Written by experts from the leaders and pioneers in thermal and nuclear power engineering research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan and other key regions such as the United States and Europe to provide a deeper learning opportunity Considers societal impact and sustainability concerns and goals throughout