Dynamic Simulation of Sodium Cooled Fast Reactors, Vaidyanathan, G
Автор: Evgeny Adamov Название: Closed nuclear fuel cycle with fast reactors ISBN: 0323993087 ISBN-13(EAN): 9780323993081 Издательство: Elsevier Science Рейтинг: Цена: 18595.00 р. 23244.00-20% Наличие на складе: Есть (5 шт.) Описание: Closed Nuclear Fuel Cycle with Fast Reactors: Handbook of Russian Nuclear Power provides unique insights into research and practical activities from leading Russian experts. It presents readers with unprecedented insight and essential knowledge surrounding nuclear fast reactor technologies, as well as novel methods to close the nuclear fuel cycle to achieve cleaner, more environmentally friendly, and more efficient nuclear power. Using the Proryv Project as a framework, the book's contributors provide detailed descriptions of technologies in development in Russia, allowing readers from around the globe to gain a thorough understanding which they can then apply to their own research and practice.
Nuclear engineers and technologists of fast reactors, advanced reactors and fuel cycles will use this book as a guide to inform new technology development. They will be able to use the experiences from the Proryv Project to drive fast reactor development with closed fuel cycles for the future.
Автор: Vaidyanathan, G., Название: Dynamic simulation of sodium cooled fast reactors / ISBN: 1032254351 ISBN-13(EAN): 9781032254357 Издательство: Taylor&Francis Рейтинг: Цена: 19906.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: The text comprehensively discusses basis of mathematical modelling of the heat transfer process in a fast reactor cooled by sodium in a single volume. The text will be helpful for senior undergraduate, graduate students and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.
Описание: This book highlights the advances and trends in the safety analysis of sodium-cooled fast reactors, especially from the perspective of particle bed-related phenomena during core disruptive accidents. A sodium-cooled fast reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems.
Автор: Morishita, Masaki Название: Sodium-Cooled Fast Reactors,3 ISBN: 0128240768 ISBN-13(EAN): 9780128240762 Издательство: Elsevier Science Рейтинг: Цена: 26107.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Now the most wanted person in Sonande, her only hope of reclaiming what is rightfully hers lies in a divine power hidden in the long-lost city of her ancestors. Meanwhile, the resurrection of Karina`s sister has spiraled the world into chaos, with disaster after disaster threatening the hard-won peace Malik has found as Farid`s apprentice.
Автор: Kale, Ravindra ; Shreedhar, B K Название: Centrifugal Pumps for Sodium Cooled Reactors ISBN: 1032460539 ISBN-13(EAN): 9781032460536 Издательство: Taylor&Francis Рейтинг: Цена: 20671.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Автор: Yoshiaki Oka; Seiichi Koshizuka; Yuki Ishiwatari; Название: Super Light Water Reactors and Super Fast Reactors ISBN: 1489996826 ISBN-13(EAN): 9781489996824 Издательство: Springer Рейтинг: Цена: 22796.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors.
Описание: To understand the current status of the research and development as well as to provide a forum to exchange information on structural materials for HLM cooled reactors, the IAEA organised a technical meeting. This resulted in the current publication.
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: Yoshiaki Oka; Hideo Mori Название: Supercritical-Pressure Light Water Cooled Reactors ISBN: 4431550240 ISBN-13(EAN): 9784431550242 Издательство: Springer Рейтинг: Цена: 14818.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
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.
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.
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