High Temperature Gas-Cooled Reactors, Takeda Tetsuaki, Inagaki Yoshiyuki
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: Нет в наличии.
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.
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.
Описание: IAEA Member States have expressed relevant interest in the development and deployment of small and medium-sized or modular reactors (SMRs) to help cover their energy needs in the coming decades. SMR designs may include technological characteristics that differ significantly from those of the large nuclear power plants that are commercially available. Those SMR characteristics can represent a challenge when the existing design requirements, as established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) Safety of Nuclear Power Plants: Design, are intended to be applied to SMRs. This publication focuses on the engineering judgement necessary to apply each of the design requirements in SSR-2/1 (Rev. 1), and also the entire set of requirements, to light water cooled and high temperature gas cooled SMRs. The publication includes the common ground reached by representatives from regulatory bodies, technical and scientific support organizations (TSOs) and SMR design organizations regarding the applicability of the design requirements to both SMR technologies. The insights provided are also intended to contribute to motivating further progress in the harmonization of national and international views on safety approaches for SMR technologies. This publication is intended for use by organizations dealing with nuclear power plant design or operation, and by regulatory bodies and TSOs, particularly from countries that are initiating or enlarging nuclear power programmes that include SMR units.
Описание: The rapid pace of technological change constantly gives rise to new ethical dilemmas. This provides a practical introduction for engineering students that emphasizes ethical decision-making. The authors situate engineering ethics in the wider context of business and environmental ethics and guide students through case studies emphasizing value conflicts often encountered in engineering.
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
Описание: Reviews the current state of technology regarding combustible gas related safety issues in water cooled nuclear reactors, with a specific focus on post-Fukushima Daiichi accident developments. The recent results obtained from experimental and analytical research on hydrogen/combustible gas behaviour are discussed.
Описание: Illustrates the state of the art in supercritical water cooled reactor (SCWR) research and development. This is a key supporting publication to researchers and engineers pursuing the development of SCWRs or equipment/components operating at supercritical pressures.
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.
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
Автор: Kurt Kugeler; Zuoyi Zhang Название: Modular High-temperature Gas-cooled Reactor Power Plant ISBN: 3662586061 ISBN-13(EAN): 9783662586068 Издательство: Springer Рейтинг: Цена: 34937.00 р. Наличие на складе: Поставка под заказ.
Описание: 'Modular High-temperature Gas-cooled Reactor Power Plant' introduces the power plants driven by modular high temperature gas-cooled reactors (HTR), which are characterized by their inherent safety features and high output temperatures. HTRs have the potential to be adopted near demand side to supply both electricity and process heat, directly replacing conventional fossil fuels. The world is confronted with two dilemmas in the energy sector, namely climate change and energy supply security. HTRs have the potential to significantly alleviate these concerns. This book will provide readers with a thorough understanding of HTRs, their history, principles, and fields of application.The book is intended for researchers and engineers involved with nuclear engineering and energy technology.
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