Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design,
Автор: Wang, Jun Название: Nuclear Power Plant Design And Analysis Codes ISBN: 0128181907 ISBN-13(EAN): 9780128181904 Издательство: Elsevier Science Рейтинг: Цена: 207730.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание:
Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li, Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.
Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs.
Автор: Sjoden Glenn E. Название: Foundations in Applied Nuclear Engineering Analysis (2nd Edition) ISBN: 9814630934 ISBN-13(EAN): 9789814630931 Издательство: World Scientific Publishing Рейтинг: Цена: 68640.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Foundations In Applied Nuclear Engineering Analysis (2Nd Edition) Covers A Fast-Paced One Semester Course To Address Concepts Of Modeling In Mathematics, Engineering Analysis, And Computational Problem Solving Needed In Subjects Such As Radiation Interactions, Heat Transfer, Reactor Physics, Radiation Transport, Numerical Modeling, Etc., For Success In A Nuclear Engineering/Medical Physics Curriculum. While Certain Topics Are Covered Tangentially, Others Are Covered In Depth To Target On The Appropriate Amalgam Of Topics For Success In Navigating Nuclear-Related Disciplines. Software Examples And Programming Are Used Throughout The Book, Since Computational Capabilities Are Essential For New Engineers.The Book Contains A Array Of Topics That Cover The Essential Subjects Expected For Students To Successfully Navigate Into Nuclear-Related Disciplines. The Text Assumes That Students Have Familiarity With Undergraduate Mathematics And Physics, And Are Ready To Apply Those Skills To Problems In Nuclear Engineering. Applications And Problem Sets Are Directed Toward Problems In Nuclear Science. Software Examples Using Mathematica Software Are Used In The Text.This Text Was Developed As Part Of A Very Applied Course In Mathematical Physics Methods For Nuclear Engineers. The Course In Nuclear Engineering Analysis That Follows This Text Began At The University Of Florida; The 2Nd Edition Was Released While At The Georgia Institute Of Technology.
Название: Benchmarks of Fuel Burnup and Material Activation Computational Tools Against Experimental Data for Research Reactors ISBN: 9201013221 ISBN-13(EAN): 9789201013224 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Нет в наличии. 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.
Название: Application of Plant Information Models to Manage Design Knowledge through the Nuclear Power Plant Life Cycle ISBN: 9201111207 ISBN-13(EAN): 9789201111203 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Нет в наличии. Описание: A plant information model (PIM) is a set of interlinked information about plant structures, systems and components, incorporating plant data, relationships and rules used to integrate, represent, and describe nuclear facility processes and data, for each phase of the facility lifecycle. Application of the PIM provides an opportunity to radically improve knowledge, information and data capture, integration, use and transfer between stakeholders if industry-wide standards and best practices are adopted. A knowledge-centric plant information model could be developed and leveraged as a modern and efficient approach to better support, manage and enable seamless sharing, transfer and use of sustainable design knowledge within and across each nuclear power plant life cycle phase. The purpose of this publication is to provide an overview of PIMs, emphasize the importance of their application in support and management of design knowledge throughout the nuclear power plant life cycle and present an overview of a knowledge-centric plant information model that builds on the basic concept of a PIM. The target users of this publication are decision-making organizations in Member States having experience with nuclear power programmes and those embarking on new nuclear power programmes.
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: Benchmarking of computational fluid dynamics codes for fuel assembly design ISBN: 9201068204 ISBN-13(EAN): 9789201068200 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Draws on the work carried out during an IAEA coordinated research project to benchmark computational fluid dynamics (CFD) codes used in fuel assembly design and model options and methods against `CFD quality` experimental data under single phase flow conditions.
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: International Atomic Energy Agency Название: Application of wireless technologies in nuclear power plant instrumentation and control systems ISBN: 920104819X ISBN-13(EAN): 9789201048196 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 42510.00 T Наличие на складе: Невозможна поставка. Описание: Summarises the results of an IAEA coordinated research project on the application of wireless technologies in the nuclear industry. The publication provides an overview of current knowledge, practices, operating experiences and benefits and challenges related to the use of the technology in instrumentation and control systems of nuclear facilities.
Автор: Yousry Azmy; Enrico Sartori Название: Nuclear Computational Science ISBN: 9400790538 ISBN-13(EAN): 9789400790537 Издательство: Springer Рейтинг: Цена: 104480.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Nuclear engineering has undergone extensive progress over the years. Advances in areas such as high-order discretization methods, Krylov Methods and Iteration Acceleration have steadily grown. This landmark publication addresses these topics and many more.
Казахстан, 010000 г. Астана, проспект Туран 43/5, НП2 (офис 2) ТОО "Логобук" Тел:+7 707 857-29-98 ,+7(7172) 65-23-70 www.logobook.kz
