Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies: Operational Behaviour,
Название: Liquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth Eutectic ISBN: 9201318103 ISBN-13(EAN): 9789201318107 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 23100.00 T Наличие на складе: Невозможна поставка. Описание: Provides a comprehensive summary of the status of the liquid metal coolant technology development for fast reactors with regard to basic data and main technological challenges.
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
Название: Efficient Water Management in Water Cooled Reactors ISBN: 9201326106 ISBN-13(EAN): 9789201326102 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 31410.00 T Наличие на складе: Невозможна поставка. Описание: Discusses current practices for water requirements in nuclear power plants, possible future trends in design of water cooled reactors and the technologies employed. This publication analyses best practices and strategies for lower water withdrawal rates and presents the trade-off between production of electricity and water use and consumption.
Название: Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors ISBN: 9201274106 ISBN-13(EAN): 9789201274106 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Covers the identification and definition of the thermo-hydraulic phenomena that affect the reliability of passive safety systems; characterization of each phenomenon; integral tests to examine the passive systems and natural circulation; and a methodology for examining passive system reliability.
Название: Modelling of Transport of Radioactive Substances in the Primary Circuit of Water Cooled Reactors ISBN: 9201260105 ISBN-13(EAN): 9789201260109 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Provides information on the modelling of corrosion product behaviour in the primary circuit. This publication reports on the research activities and results from an IAEA coordinated research project in this field and includes details of current best practice.
Автор: D`Auria, Francesco Название: Thermal-Hydraulics of Water Cooled Nuclear Reactors ISBN: 0081006624 ISBN-13(EAN): 9780081006627 Издательство: Elsevier Science Рейтинг: Цена: 297560.00 T 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.
Название: Advances in High Temperature Gas Cooled Reactor Fuel Technology ISBN: 9201868103 ISBN-13(EAN): 9789201868107 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments.
Автор: Yvon, Pascal Название: Structural Materials for Generation IV Nuclear Reactors ISBN: 0081009062 ISBN-13(EAN): 9780081009062 Издательство: Elsevier Science Рейтинг: Цена: 206610.00 T 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: Yoshiaki Oka; Hideo Mori Название: Supercritical-Pressure Light Water Cooled Reactors ISBN: 4431550240 ISBN-13(EAN): 9784431550242 Издательство: Springer Рейтинг: Цена: 113190.00 T Наличие на складе: Есть у поставщика Поставка под заказ.
Название: Advances in High Temperature Gas Cooled Reactor Fuel Technology ISBN: 9201253109 ISBN-13(EAN): 9789201253101 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments.
Название: Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of the HTTR and HTR-10 ISBN: 9201162030 ISBN-13(EAN): 9789201162038 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 13860.00 T Наличие на складе: Невозможна поставка. Описание: High-temperature gas cooled reactor (HTGR) designs present special computational challenges related to their core physics and thermal-hydraulic characteristics. Neutron streaming and double heterogeneities are examples of the core physics challenges, while porous gas flow in a high-temperature ceramic core with the interaction of conduction, convection and radiation regimes characterize thermal-hydraulic challenges. In an effort to address such potential calculation uncertainties, computational results made by various international institutes are reported and code-to-code and code-to-experiment comparisons are made. The experimental data are mainly related to the initial testing of the Japanese HTTR and the Chinese HTR-10. Both are high-temperature gas cooled test reactors. The work is part of an IAEA Co-ordinated Research Project (CRP) with the participation of ten international institutes.
Автор: Roelofs, Ferry Название: Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors ISBN: 0081019807 ISBN-13(EAN): 9780081019801 Издательство: Elsevier Science Рейтинг: Цена: 185270.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание:
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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