Closed nuclear fuel cycle with fast reactors, Evgeny Adamov
Название: Limited Scope Sustainability Assessment of Planned Nuclear Energy Systems Based on BN-1200 Fast Reactors ISBN: 9201091214 ISBN-13(EAN): 9789201091215 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 13860.00 T Наличие на складе: Поставка под заказ. Описание: Provides an example of a limited scope INPRO sustainability assessment of an innovative nuclear energy system used the BN-1200 fast reactor as a case study. The INPRO assessment was performed at the full-depth criteria level and helped to identify actions for sustainable long term deployment of sodium cooled fast reactors.
Название: Passive Shutdown Systems for Fast Neutron Reactors ISBN: 9201042191 ISBN-13(EAN): 9789201042194 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 29260.00 T Наличие на складе: Невозможна поставка. Описание: Designs for nuclear power plants increasingly include passive features. A major focus of the design of modern fast reactors is on inherent and passive safety. This publication discusses the past experience in the development of such systems along with the research that is ongoing.
Название: Benchmarks of Fuel Burnup and Material Activation Computational Tools Against Experimental Data for Research Reactors ISBN: 9201013221 ISBN-13(EAN): 9789201013224 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 13860.00 T Наличие на складе: Поставка под заказ. Описание: Provides the final consolidated results of an IAEA coordinated research project (CRP). The publication comprises the benchmark studies, details of the calculations in the annexes and individual reports of the CRP participants in the online supplementary files.
Название: Structural Materials for Heavy Liquid Metal Cooled Fast Reactors: Proceedings of a Technical Meeting ISBN: 9201288212 ISBN-13(EAN): 9789201288219 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 13860.00 T Наличие на складе: Поставка под заказ. 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.
Название: Review of Fuel Failures in Water Cooled Reactors (2006–2015) (Russian Edition) ISBN: 9204295201 ISBN-13(EAN): 9789204295207 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 26950.00 T Наличие на складе: Поставка под заказ. Описание: Since the 1970s, the IAEA has been involved in the analysis of fuel failures in water cooled reactors in normal (nonaccident) operational conditions. This updated version of IAEA Nuclear Energy Series No. NFT2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.
Автор: International Atomic Energy Agency Название: Benefits and challenges of small modular fast reactors ISBN: 920124021X ISBN-13(EAN): 9789201240217 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 14630.00 T Наличие на складе: Поставка под заказ. Описание: In the world market of power-producing nuclear reactors, there is growing interest in small and medium sized or modular reactors (SMRs). These can be assembled in-factory, transported by ship or train, installed on site and connected to the electricity grid in a short time, significantly reducing the financial burden of the investment. This publication, which is the outcome of a technical meeting, presents a detailed overview of the different concepts of fast SMRs and highlights the technological, economic and safety potential of these reactors and the associated innovative systems. Although it is mainly focused on innovative reactor solutions aimed to increase safety and simplicity of design, the parameters that contribute to the final cost of the plant are also considered.
Автор: Iaea Название: Management of spent fuel from nuclear power reactors ISBN: 9201086202 ISBN-13(EAN): 9789201086204 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 39710.00 T Наличие на складе: Невозможна поставка. Описание: This publication presents the proceedings of the IAEA International Conference on the Management of Spent Fuel from Nuclear Power Reactors, held in 2019, with the theme ‘Learning from the Past, Enabling the Future’. The purpose of the event was to provide a forum for the exchange of information on national spent fuel management strategies and on the ways in which a changing energy mix could influence these strategies and on how they support the achievement of national energy goals. The broad scope of the conference covered all stages of the management of spent fuel from the past, present and future technologies, and how it can be affected by the decisions taken in the rest of the nuclear fuel cycle. The event brought together experts from countries with decades of nuclear power operating experience and those from countries currently developing or considering a nuclear power programme. The importance of sharing data, operational experience, lessons learned and international collaboration in research and development (R&D) activities, and how its development and implementation can lead to attainable solutions was highlighted. Special attention was given to the young generation of professionals to support bridging the gap with the current ageing industry workforce.
Автор: Kerlin, Thomas W. (professor Emeritus Of Nuclear Engineering, University Of Tennessee) Upadhyaya, Belle R. (professor Emeritus Of Nuclear Engineering, Название: Dynamics and control of nuclear reactors ISBN: 0128152613 ISBN-13(EAN): 9780128152614 Издательство: Elsevier Science Рейтинг: Цена: 129130.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание:
Dynamics and Control of Nuclear Reactors presents the latest knowledge and research in reactor dynamics, control and instrumentation; important factors in ensuring the safe and economic operation of nuclear power plants. This book provides current and future engineers with a single resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic characteristics of pressurized light-water reactors, boiling light-water reactors, pressurized heavy-water reactors and molten-salt reactors. It also provides pertinent, but less detailed information on small modular reactors, sodium fast reactors, and gas-cooled reactors.
Provides case studies and examples to demonstrate learning through problem solving, including an analysis of accidents at Three Mile Island, Chernobyl and Fukushima Daiichi
Includes MATLAB codes to enable the reader to apply the knowledge gained to their own projects and research
Features examples and problems that illustrate the principles of dynamic analysis as well as the mathematical tools necessary to understand and apply the analysis
Publishers Note: Table 3.1 has been revised and will be included in future printings of the book with the following data:
Автор: D`Auria, Francesco Название: Thermal-Hydraulics of Water Cooled Nuclear Reactors ISBN: 0081006624 ISBN-13(EAN): 9780081006627 Издательство: Elsevier Science Рейтинг: Цена: 247970.00 T 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.
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