Status of Research and Technology Development for Supercritical Water Cooled Reactors,
Автор: Yoshiaki Oka; Hideo Mori Название: Supercritical-Pressure Light Water Cooled Reactors ISBN: 4431550240 ISBN-13(EAN): 9784431550242 Издательство: Springer Рейтинг: Цена: 16979.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Materials and Water Chemistry for Supercritical Water-cooled Reactors uniquely brings together materials and water chemistry, highlighting their interrelationship, their historical perspective, and their application to SCWR conceptual design. Written by world leading experts, all active in the area of materials and chemistry R&D in support of GEN IV SCWR, this book presents a comprehensive reference on the topics, and in particular, how their data relate to the SCWR design itself. It is an essential text for researchers in the areas of supercritical water cooled reactor materials and chemistry.
In addition, the book gives newcomers to the field a survey of all of the available literature and a clear understanding of how these studies relate to the design of the SCWR concept. The material presented is at a specialist's level in materials or corrosion science, or in water chemistry of power plants.
Provides comprehensive coverage of the chemistry and materials of SCWR
Presents the latest research and results condensed into one book
Covers the differences in use of SCW in nuclear reactors and fossil plants, and the resulting differences in materials requirements
Описание: Materials for Ultra-Supercritical and Advanced Ultra-Supercritical Power Plants provides researchers in academia and industry with an essential overview of the stronger high-temperature materials required for key process components, such as membrane wall tubes, high-pressure steam piping and headers, superheater tubes, forged rotors, cast components, and bolting and blading for steam turbines in USC power plants. Advanced materials for future advanced ultra-supercritical power plants, such as superalloys,new martensitic and austenitic steels, are also addressed. Chapters on international research directions complete the volume. The transition from conventional subcritical to supercritical thermal power plants greatly increased power generation efficiency. Now the introductions of the ultra-supercritical (USC) and, in the near future, advanced ultra-supercritical (A-USC) designs are further efforts to reduce fossil fuel consumption in power plants and the associated carbon dioxide emissions. The higher operating temperatures and pressures found in these new plant types, however, necessitate the use of advanced materials.
Автор: Vijayan, Pallippattu Krishnan Название: Single-phase, Two-phase and Supercritical Natural Circulation Systems ISBN: 008102486X ISBN-13(EAN): 9780081024867 Издательство: Elsevier Science Рейтинг: Цена: 37897.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:
Single-phase, Two-phase and Supercritical Natural Circulation Systems brings together the latest research and knowledge into one unique reference and provides the reader with a deep understanding of natural circulation systems. This book will equip the reader with an understanding of 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.
Dr. Vijayan brings to this work a wealth of varied experience and knowledge, and adopts a very methodical, applied approach. Each chapter begins with an introduction of the circulation system, before discussing each element in detail and analyzing their effect on the performance of the system. He presents the use of thermosyphon heat transport devices in nuclear and other industrial plants, a common information need for students and researchers alike, and provides detailed discussion on how to calculate the effects of changing specific elements of a system. 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, aimed at the nuclear, mechanical and chemical engineering disciples
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, as well as important IAEA standards and procedures
Описание: This book systematically presents the technical aspects of supercritical water oxidation and supercritical water gasification for energy and environmental applications, which include reactor design, construction materials, corrosion, salt precipitation, etc. The book provides a comprehensive introduction to the properties of supercritical water, and the industrial applications, reaction mechanisms and reaction kinetics of supercritical water oxidation (SCWO) and supercritical water gasification (SCWG). The reactions occurring in supercritical water are complex, and studying their reaction mechanisms is of great importance for the development of supercritical water processing technologies. Accordingly, the book explains the oxidative mechanisms and kinetics of organic matter in supercritical water in detail. However, the harsh reaction conditions in supercritical water can easily create severe reactor corrosion and salt deposition problems. Therefore, the book also comprehensively reports on the mechanism analysis, state of research, and development trends regarding these two problems. Lastly, the book summarizes the development of supercritical water processing technologies, including studies on SCWO and SCWG, as well as near-zero-emission systems of pollutants based on SCWO technology. In short, the book provides a wealth of valuable information for all readers who are interested in using SCWO for organic waste treatment, and in using SCWG for hydrogen production with wet biomass.
Автор: Yvon, Pascal Название: Structural Materials for Generation IV Nuclear Reactors ISBN: 0081009062 ISBN-13(EAN): 9780081009062 Издательство: Elsevier Science Рейтинг: Цена: 30991.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas.Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors.
Автор: D`Auria, Francesco Название: Thermal-Hydraulics of Water Cooled Nuclear Reactors ISBN: 0081006624 ISBN-13(EAN): 9780081006627 Издательство: Elsevier Science Рейтинг: Цена: 44634.00 р. Наличие на складе: Поставка под заказ.
Описание:
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.
Описание: Summarizes the current status of severe accident analysis codes and recommends areas for research and development. The information is detailed in terms of major findings,
Описание: Since the 1970`s, the IAEA has been involved in the analysis of fuel failures in water cooled reactors in normal (non-accident) operational conditions. This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.
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
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