Neutronic Analysis For Nuclear Reactor Systems, Bahman Zohuri
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: Yican Wu Название: Neutronics of Advanced Nuclear Systems ISBN: 9811365199 ISBN-13(EAN): 9789811365195 Издательство: Springer Рейтинг: Цена: 121110.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание:
This book provides a systematic and comprehensive introduction to the neutronics of advanced nuclear systems, covering all key aspects, from the fundamental theories and methodologies to a wide range of advanced nuclear system designs and experiments. It is the first-ever book focusing on the neutronics of advanced nuclear systems in the world.
Compared with traditional nuclear systems, advanced nuclear systems are characterized by more complex geometry and nuclear physics, and pose new challenges in terms of neutronics. Based on the achievements and experiences of the author and his team over the past few decades, the book focuses on the neutronics characteristics of advanced nuclear systems and introduces novel neutron transport methodologies for complex systems, high-fidelity calculation software for nuclear design and safety evaluation, and high-intensity neutron source and technologies for neutronics experiments. At the same time, it describes the development of various neutronics designs for advanced nuclear systems, including neutronics design for ITER, CLEAR and FDS series reactors. The book not only summarizes the progress and achievements of the author’s research work, but also highlights the latest advances and investigates the forefront of the field and the road ahead.
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: Duderstadt, James J. Hamilton, Louis J. Название: Nuclear reactor analysis ISBN: 0471223638 ISBN-13(EAN): 9780471223634 Издательство: Wiley Рейтинг: Цена: 290350.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores.
Название: Data Analysis and Collection for Costing of Research Reactor Decommissioning ISBN: 9201087179 ISBN-13(EAN): 9789201087171 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: This publication is intended to assist those Member States with limited decommissioning expertise, to estimate the overall cost of decommissioning during the early planning stages. The lack of published data has made it difficult to benchmark estimated costs against international practice. The DACCORD (data analysis and collection for costing of research reactor decommissioning) project was established to address this deficiency. Based on the outcome of the three main working groups, this publication provides representative input data and benchmarking data needed for the costing of research reactor decommissioning at preliminary planning stages. All detailed cost cases considered in the DACCORD project are presented in a special format, following a software tool, developed by the IAEA, and which helps to ensure uniformity of the presented data and generally to facilitate the analysis of the available information.
Название: Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of the HTTR and HTR-10 ISBN: 9201162030 ISBN-13(EAN): 9789201162038 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 13860.00 T Наличие на складе: Невозможна поставка. Описание: High-temperature gas cooled reactor (HTGR) designs present special computational challenges related to their core physics and thermal-hydraulic characteristics. Neutron streaming and double heterogeneities are examples of the core physics challenges, while porous gas flow in a high-temperature ceramic core with the interaction of conduction, convection and radiation regimes characterize thermal-hydraulic challenges. In an effort to address such potential calculation uncertainties, computational results made by various international institutes are reported and code-to-code and code-to-experiment comparisons are made. The experimental data are mainly related to the initial testing of the Japanese HTTR and the Chinese HTR-10. Both are high-temperature gas cooled test reactors. The work is part of an IAEA Co-ordinated Research Project (CRP) with the participation of ten international institutes.
Название: Design of the Reactor Containment and Associated Systems for Nuclear Power Plants ISBN: 9201028199 ISBN-13(EAN): 9789201028198 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 37890.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Provides recommendations on meeting the requirements of IAEA Safety Standards Series No SSR-2/1 (Rev 1). The guide addresses the containment structure and the systems with the functions of isolation, control and management of mass and energy releases, control and limitation of radioactive releases, and control and management of combustible gases.
Автор: Yican Wu Название: Fusion Neutronics ISBN: 9811054681 ISBN-13(EAN): 9789811054686 Издательство: Springer Рейтинг: Цена: 111790.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: This book provides a systematic and comprehensive introduction to fusion neutronics, covering all key topics from the fundamental theories and methodologies, as well as a wide range of fusion system designs and experiments.
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: Status of Fast Reactor Research and Technology Development ISBN: 9201306105 ISBN-13(EAN): 9789201306104 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 32340.00 T Наличие на складе: Невозможна поставка. Описание: Provides comprehensive and detailed information on the technology of fast neutron reactors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors.
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.
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