Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants,
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: 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.
Название: Liquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth Eutectic ISBN: 9201318103 ISBN-13(EAN): 9789201318107 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 23100.00 T Наличие на складе: Невозможна поставка. Описание: Provides a comprehensive summary of the status of the liquid metal coolant technology development for fast reactors with regard to basic data and main technological challenges.
Название: Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions: Proceedings of a Technical Meeting Held in Mito, Japan, 18–21 October 2011 ISBN: 9201924100 ISBN-13(EAN): 9789201924100 Издательство: Mare Nostrum (Eurospan) Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: This publication is the proceedings of a technical meeting on fuel behaviour and modelling under severe transient and loss of coolant accident (LOCA) conditions. It was attended by nuclear fuel specialists representing fuel vendors, nuclear utilities, research and development institutions and regulatory bodies. Papers were presented in areas including analytical and experimental reactivity initiated accidents, and power ramp and severe accident analysis. The proceedings highlight the key findings and recommendations based on the summaries of the session chairpersons.
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.
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: Iaea Название: Challenges for coolants in fast neutron spectrum systems ISBN: 920107820X ISBN-13(EAN): 9789201078209 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 17550.00 T Наличие на складе: Невозможна поставка. Описание: This publication evaluates the different coolant options considered for nuclear applications with a fast neutron spectrum (i.e. fusion, fission and accelerators), compiles the latest information in the field and identifies research needs. In this study, systems cooled by light and heavy liquid metals, molten salts, as well as gas and water choices are analysed and discussed. This TECDOC documents the present state of knowledge in the area of fusion, fission and accelerator applications, and the major progress in methods and approaches made in the past years based on observations, experimental findings and operational experience. Moreover, it identifies knowledge gaps and addresses near term research and development efforts required to overcome them.
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.
Автор: Iaea Название: Benchmarking of computational fluid dynamics codes for reactor vessel design ISBN: 9201074204 ISBN-13(EAN): 9789201074201 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: This publication provides a description of the Rossendorf coolant mixing (ROCOM) test facility, used to provide benchmark experiments related to the phenomena of pressurized thermal shock (PTS) and boron dilution, the calculation results using computational fluid dynamics (CFD) codes and methods, and the conclusions drawn from comparison of CFD results with experimental measurements. The aim of this benchmarking was to provide CFD practitioners with two high quality datasets of relevance to reactor transients inside a pressurized water reactor pressure vessel with different configurations and involving mixed convection, stratification, jet impingement and unsteady (inverse) plumes. The focus of the benchmarking was on the three main regions of the cold domain of the primary circuit, i.e. the cold leg, the downcomer and the core entry region. The work was carried out within the framework of an IAEA coordinated research project on application of computational fluid dynamics codes to nuclear power plant design.
Автор: Zohuri Bahman Название: Neutronic Analysis for Nuclear Reactor Systems ISBN: 3319827065 ISBN-13(EAN): 9783319827063 Издательство: Springer Рейтинг: Цена: 139750.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: This book covers the entire spectrum of the science and technology of nuclear reactor systems, from underlying physics, to next generation system applications and beyond.
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.
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