Neutronic Analysis for Nuclear Reactor Systems, Zohuri Bahman
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.
Название: Applicability of Design Safety Requirements to Small Modular Reactor Technologies Intended for Near Term Deployment: Light Water Reactors High Temperature Gas Cooled Reactors ISBN: 9201308205 ISBN-13(EAN): 9789201308207 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 17550.00 T Наличие на складе: Нет в наличии. Описание: IAEA Member States have expressed relevant interest in the development and deployment of small and medium-sized or modular reactors (SMRs) to help cover their energy needs in the coming decades. SMR designs may include technological characteristics that differ significantly from those of the large nuclear power plants that are commercially available. Those SMR characteristics can represent a challenge when the existing design requirements, as established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) Safety of Nuclear Power Plants: Design, are intended to be applied to SMRs. This publication focuses on the engineering judgement necessary to apply each of the design requirements in SSR-2/1 (Rev. 1), and also the entire set of requirements, to light water cooled and high temperature gas cooled SMRs. The publication includes the common ground reached by representatives from regulatory bodies, technical and scientific support organizations (TSOs) and SMR design organizations regarding the applicability of the design requirements to both SMR technologies. The insights provided are also intended to contribute to motivating further progress in the harmonization of national and international views on safety approaches for SMR technologies. This publication is intended for use by organizations dealing with nuclear power plant design or operation, and by regulatory bodies and TSOs, particularly from countries that are initiating or enlarging nuclear power programmes that include SMR units.
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.
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: Nuclear Reactor Technology Assessment for Near Term Deployment ISBN: 9201403100 ISBN-13(EAN): 9789201403100 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 27720.00 T Наличие на складе: Невозможна поставка. Описание: Demonstrates how reactor technology assessment is performed and how the process and results of this work enable decision making in nuclear power planning. The approach also provides decision makers with the documentation necessary to support their conclusions.
Автор: ASME Название: ASME 2011 Small Modular Reactor International Symposium ISBN: 0791854736 ISBN-13(EAN): 9780791854730 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 190350.00 T Наличие на складе: Невозможна поставка. Описание: Printed collection of 60 full-length, peer-reviewed technical papers.
Автор: Saha Pradip Название: Nuclear Reactor Thermal-Hydraulics: Past, Present and Future ISBN: 0791861287 ISBN-13(EAN): 9780791861288 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 110880.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Summarizes the major developments on nuclear reactor thermal-hydraulics over the last fifty years, primarily for water-cooled reactors, and provides a direction for the future thermal-hydraulic developments for water-cooled, including small modular reactors or SMR, and Generation IV reactors.
Автор: Wu Yican Название: Neutronics of Advanced Nuclear Systems ISBN: 9811365229 ISBN-13(EAN): 9789811365225 Издательство: Springer Рейтинг: Цена: 149060.00 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.
Автор: Paredes, Gilberto Espinos Название: Fractional-Order Models For Nuclear Reactor Analysis ISBN: 0128236655 ISBN-13(EAN): 9780128236659 Издательство: Elsevier Science Рейтинг: Цена: 185270.00 T Наличие на складе: Есть у поставщика Поставка под заказ.
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.
Автор: Bahman Zohuri Название: Neutronic Analysis For Nuclear Reactor Systems ISBN: 3030049051 ISBN-13(EAN): 9783030049058 Издательство: Springer Рейтинг: Цена: 139750.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: This expanded new edition develops the theory of nuclear reactors from the fundamentals of fission to the operating characteristics of modern reactors. The first half of the book emphasizes reactor criticality analysis and all of the fundamentals that go into modern calculations. Simplified one group diffusion theory models are presented and extended into sophisticated multi-group transport theory models. The second half of the book deals with the two main topics of interest related to operating reactors – reactor kinetics/dynamics, and in-core fuel management. Additional chapters have been added to expand and bring the material up-to-date and include the utilization of more computer codes. Code models and detailed data sets are provided along with example problems making this a useful text for students and researchers wishing to develop an understanding of nuclear power and its implementation in today’s modern energy spectrum.Covers the fundamentals of neutronic analysis for nuclear reactor systems to help understand nuclear reactor theory;Describes the benefits, uses, safety features, and challenges related to implementation of Small Modular Reactors;Provides examples, data sets, and code to assist the reader in obtaining mastery over the subjects.
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.
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