Описание: These proceedings present the outcome of the 2015 IAEA international conference on the management of spent fuel from nuclear power reactors. Achievements and lessons learned in connection with the back end of the nuclear fuel cycle and associated challenges were shared and reviewed. The conference was organized around seven themes, covering spent fuel management strategies; status and challenges in an integrated approach; safety aspects of spent fuel management; ageing management programmes; storage options in support of an integrated approach; impact of the front end of the nuclear fuel cycle on the back end; and research and development required to deliver an integrated approach. Key goals were to raise awareness on how developments in power generation and availability of disposal can impact on spent fuel management, to evaluate the advances in management of spent fuel from power reactors since the inception of IAEA conferences on this topic, and to identify pending issues and anticipated future challenges. The main ideas and messages expressed and discussed at the conference are presented in the opening addresses, the session summaries and the President’s summary and conclusions of the conference. The attached CD contains the papers and posters presented at the conference.
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.
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.
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.
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: 2633.00 р. Наличие на складе: Нет в наличии.
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.
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.
Название: Nuclear Power Reactors in the World ISBN: 9201027192 ISBN-13(EAN): 9789201027191 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 2495.00 р. Наличие на складе: Нет в наличии.
Описание: Presents the most recent reactor data available to the IAEA. This publication contains summarized information as of the end of 2018 on power reactors operating, under construction and shut down as well as performance data on reactors operating in the IAEA Member States.
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: 23244.00 р. 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: 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.
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