Design of the Reactor Containment and Associated Systems for Nuclear Power Plants,
Автор: Ashar Название: Containment Structures Of U.S. Nuclear Power Plants ISBN: 0791860175 ISBN-13(EAN): 9780791860175 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 33403.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: In this book, expert authors recognise the renewed relevance of nuclear power in the U.S. after decades of stagnation. It was imperative to develop an up-to-date, scholarly work on containment structures, incorporating the underlying regulations, safety significance, history, design philosophy, design experience, operating experience, and application to new design.
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.
Advances of Computational Fluid Dynamics in Nuclear Reactor Design and SafetyAssessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors.
Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants.
Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors
Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future
Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization
Автор: Bahman Zohuri Название: Neutronic Analysis For Nuclear Reactor Systems ISBN: 3030049051 ISBN-13(EAN): 9783030049058 Издательство: Springer Рейтинг: Цена: 20962.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: This expanded new edition develops the theory of nuclear reactors from the fundamentals of fission to the operating characteristics of modern reactors. The first half of the book emphasizes reactor criticality analysis and all of the fundamentals that go into modern calculations. Simplified one group diffusion theory models are presented and extended into sophisticated multi-group transport theory models. The second half of the book deals with the two main topics of interest related to operating reactors – reactor kinetics/dynamics, and in-core fuel management. Additional chapters have been added to expand and bring the material up-to-date and include the utilization of more computer codes. Code models and detailed data sets are provided along with example problems making this a useful text for students and researchers wishing to develop an understanding of nuclear power and its implementation in today’s modern energy spectrum.Covers the fundamentals of neutronic analysis for nuclear reactor systems to help understand nuclear reactor theory;Describes the benefits, uses, safety features, and challenges related to implementation of Small Modular Reactors;Provides examples, data sets, and code to assist the reader in obtaining mastery over the subjects.
Автор: Yoshiaki Oka; Takashi Kiguchi Название: Nuclear Reactor Design ISBN: 4431561773 ISBN-13(EAN): 9784431561774 Издательство: Springer Рейтинг: Цена: 14365.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors.
Автор: Yoshiaki Oka; Takashi Kiguchi Название: Nuclear Reactor Design ISBN: 4431548971 ISBN-13(EAN): 9784431548973 Издательство: Springer Рейтинг: Цена: 20962.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors.
Название: Behaviour of spent power reactor fuel during storage ISBN: 9201003196 ISBN-13(EAN): 9789201003195 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 2495.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Focuses on the storage of spent nuclear fuel from power reactors - a topic of increasing importance to Member States. To support their needs, the IAEA has carried out successive coordinated research projects on spent fuel performance and the behaviour of spent fuel assemblies in storage since the 1980s. This publication consolidates their findings.
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