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: D`Auria, Francesco Название: Thermal-Hydraulics of Water Cooled Nuclear Reactors ISBN: 0081006624 ISBN-13(EAN): 9780081006627 Издательство: Elsevier Science Рейтинг: Цена: 297560.00 T 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.
Автор: Hensley Trenton Название: Nuclear Reactor Physics ISBN: 1632387077 ISBN-13(EAN): 9781632387073 Издательство: Неизвестно Рейтинг: Цена: 171660.00 T Наличие на складе: Есть у поставщика Поставка под заказ.
Автор: Anglart, Henryk Название: Multilingual Dictionary of Nuclear Reactor Physics and Engineering ISBN: 0367470810 ISBN-13(EAN): 9780367470814 Издательство: Taylor&Francis Рейтинг: Цена: 148010.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: This multilingual dictionary explains, in simple and clear language, the most frequently-used terms and expressions in the field of nuclear reactor physics and engineering, and provides translations of these terms from English into French, German, Swedish and Polish.
Название: Approaches to Safety Evaluation of New and Existing Research Reactor Facilities in Relation to External Events ISBN: 920102617X ISBN-13(EAN): 9789201026170 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 38450.00 T Наличие на складе: Нет в наличии. Описание: This publication provides information and a framework for Member States to conduct realistic safety evaluation for research reactors in terms of external events. The publication provides information with examples on the use of a graded approach, based on the radiological hazard that a facility poses to the environment, public and workers, and takes into account the lessons from the Fukushima accident. This publication supports the development of site specific guidelines for the actual design and safety assessment, and should be used in conjunction with the relevant IAEA Safety Standards. It can also be used as training material for research reactor staff and for a self-assessment of the vulnerability of existing structures to external events.
Название: Management and Storage of Research Reactor Spent Nuclear Fuel: Proceedings of a Technical Meeting Held in Thurso, United Kingdom, 19–22 October 2009 ISBN: 9201382103 ISBN-13(EAN): 9789201382108 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 45270.00 T Наличие на складе: Невозможна поставка. Описание: Presents the proceedings of a technical meeting to discuss good practices for the management and storage of research reactor spent fuel. The information provided on these issues will be of interest to managers of research reactors and research reactor spent nuclear fuel facilities.
Название: Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications ISBN: 920114413X ISBN-13(EAN): 9789201144133 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Reports on the results of an IAEA coordinated research project on benchmarking severe accident computer codes for heavy water reactor applications. This summary report provides a comparison of key results for the selected Station Blackout scenario and concludes with lessons learned and recommendations for future activities.
Автор: Yoshiaki Oka; Takashi Kiguchi Название: Nuclear Reactor Design ISBN: 4431548971 ISBN-13(EAN): 9784431548973 Издательство: Springer Рейтинг: Цена: 139750.00 T 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: Design, Manufacturing and Irradiation Behaviour of Fast Reactor Fuel: Proceedings of a Technical Meeting held in Obninsk, Russian Federation, 30 May–3 June 2011 ISBN: 9201865104 ISBN-13(EAN): 9789201865106 Издательство: Mare Nostrum (Eurospan) Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: This publication presents the proceedings of a technical meeting organized in order to share knowledge and practical experience on the improvement and innovation of fuels for fast reactors. The objective of the meeting was to provide an overview of the status of the design, manufacture and irradiation behaviour of fast reactor fuel. Scientists and engineers from different fields discussed critical issues, with the aim of supporting efforts relating to the design and manufacture of nuclear fuels for the existing and next generation of fast reactors, as well as the optimization of future irradiation experiments.
Название: Design of the Reactor Core for Nuclear Power Plants ISBN: 9201038194 ISBN-13(EAN): 9789201038197 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 39290.00 T Наличие на складе: Невозможна поставка. Описание: The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in SSR-2/1 (Rev. 1) applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical, and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.
Название: Technical Requirements in the Bidding Process for a New Research Reactor ISBN: 9201034148 ISBN-13(EAN): 9789201034144 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 19410.00 T Наличие на складе: Невозможна поставка. Описание: This publication has been developed to assist Member States in the preparation of the technical requirements for the bidding process for a new research reactor. The publication addresses the preparation phase of the bidding process and discusses criteria that may be used in the evaluation of the bids.
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