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Modular High-temperature Gas-cooled Reactor Power Plant, Kurt Kugeler; Zuoyi Zhang


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Цена: 34937.00р.
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Автор: Kurt Kugeler; Zuoyi Zhang
Название:  Modular High-temperature Gas-cooled Reactor Power Plant
ISBN: 9783662586068
Издательство: Springer
Классификация:




ISBN-10: 3662586061
Обложка/Формат: Soft cover
Страницы: 893
Вес: 2.23 кг.
Дата издания: 2019
Язык: English
Иллюстрации: XII, 893 p. 1024 illus., 28 illus. in color.
Размер: Book (Paperback Initiative)
Основная тема: Energy
Ссылка на Издательство: Link
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Поставляется из: Германии
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.
Дополнительное описание: General Aspects of High Temperature Reactors.- Physical Aspects of Core Layout.- Thermo Hydraulic Aspects of Core Layout.- Fuel Elements.- Internals of Reactor and Core Relevant Components.- Primary Enclosure.- Components of Helium Cycle.- Reactor Contain



Thermal-Hydraulics of Water Cooled Nuclear Reactors

Автор: D`Auria, Francesco
Название: Thermal-Hydraulics of Water Cooled Nuclear Reactors
ISBN: 0081006624 ISBN-13(EAN): 9780081006627
Издательство: Elsevier Science
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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.

Status of Research and Technology Development for Supercritical Water Cooled Reactors

Название: Status of Research and Technology Development for Supercritical Water Cooled Reactors
ISBN: 920101919X ISBN-13(EAN): 9789201019196
Издательство: Mare Nostrum (Eurospan)
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Цена: 2495.00 р.
Наличие на складе: Нет в наличии.

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.

Название: Review of Fuel Failures in Water Cooled Reactors (2006–2015): An Update of IAEA Nuclear Energy Series No. NF-T-2.1
ISBN: 9201043198 ISBN-13(EAN): 9789201043191
Издательство: Mare Nostrum (Eurospan)
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Цена: 4851.00 р.
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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.

Supercritical-Pressure Light Water Cooled Reactors

Автор: Yoshiaki Oka; Hideo Mori
Название: Supercritical-Pressure Light Water Cooled Reactors
ISBN: 4431550240 ISBN-13(EAN): 9784431550242
Издательство: Springer
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Цена: 16979.00 р.
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Materials and Water Chemistry for Supercritical Water-cooled Reactors

Автор: Guzonas, David
Название: Materials and Water Chemistry for Supercritical Water-cooled Reactors
ISBN: 008102049X ISBN-13(EAN): 9780081020494
Издательство: Elsevier Science
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Цена: 26949.00 р.
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Описание:

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

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