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Nuclear reactor engineering, Glasstone


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Цена: 30745.00р.
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Автор: Glasstone
Название:  Nuclear reactor engineering
Перевод названия: Разработка ядерных реакторов
ISBN: 9780412985317
Издательство: Springer
Классификация:
ISBN-10: 0412985314
Обложка/Формат: Hardback
Страницы: 404
Вес: 0.74 кг.
Дата издания: 01.10.1994
Серия: Electronic and Computer Engineering
Язык: English
Издание: 4th ed. 1994
Иллюстрации: Xvi, 381 p.
Размер: 23.47 x 16.05 x 2.79
Читательская аудитория: Postgraduate, research & scholarly
Подзаголовок: Reactor systems engineering
Ссылка на Издательство: Link
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Поставляется из: Германии
Описание: Combines the nuclear engineering principles with descriptions of their application in the operation of nuclear power plants. This book concentrates on the fundamentals of nuclear engineering. It investigates the approaches to reactor systems, including computer analysis, and exploiting the potential of IT in nuclear engineering.


Nuclear reactor analysis

Автор: Duderstadt, James J. Hamilton, Louis J.
Название: Nuclear reactor analysis
ISBN: 0471223638 ISBN-13(EAN): 9780471223634
Издательство: Wiley
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Цена: 43552.00 р.
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Описание: Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores.

Structural Materials for Generation IV Nuclear Reactors

Автор: Yvon, Pascal
Название: Structural Materials for Generation IV Nuclear Reactors
ISBN: 0081009062 ISBN-13(EAN): 9780081009062
Издательство: Elsevier Science
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Цена: 30991.00 р.
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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.

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.
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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.


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