Summary Review On The Application Of Computational Fluid Dynamics In Nuclear Power Plant Design

Author : IAEA
Publisher : International Atomic Energy Agency
Page : 121 pages
File Size : 44,5 Mb
Release : 2022-03-28
Category : Business & Economics
ISBN : 9789201004215

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Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design by IAEA Pdf

This publication documents the results of an IAEA coordinated research project (CRP)on the application of computational fluid dynamics (CFD) codes for nuclear power plant design. The main objective was to benchmark CFD codes, model options and methods against CFD experimental data under single phase flow conditions. This publication summarizes the current capabilities and applications of CFD codes, and their present qualification level, with respect to nuclear power plant design requirements. It is not intended to be comprehensive, focusing instead on international experience in the practical application of these tools in designing nuclear power plant components and systems. The guidance in this publication is based on inputs provided by international nuclear industry experts directly involved in nuclear power plant design issues, CFD applications, and in related experimentation and validation highlighted during the CRP.

Author : Anonim
Publisher : Unknown
Page : 0 pages
File Size : 48,7 Mb
Release : 2022
Category : Computational fluid dynamics
ISBN : 9201003218

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Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design by Anonim Pdf

"This publication documents the results of an IAEA coordinated research project (CRP)on the application of computational fluid dynamics (CFD) codes for nuclear power plant design. The main objective was to benchmark CFD codes, model options and methods against CFD experimental data under single phase flow conditions. This publication summarizes the current capabilities and applications of CFD codes, and their present qualification level, with respect to nuclear power plant design requirements. It is not intended to be comprehensive, focusing instead on international experience in the practical application of these tools in designing nuclear power plant components and systems. The guidance in this publication is based on inputs provided by international nuclear industry experts directly involved in nuclear power plant design issues, CFD applications, and in related experimentation and validation highlighted during the CRP."--Publisher's description.

Author : Jyeshtharaj Joshi,Arun K Nayak
Publisher : Woodhead Publishing
Page : 888 pages
File Size : 40,7 Mb
Release : 2019-06-15
Category : Science
ISBN : 9780081023372

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Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment by Jyeshtharaj Joshi,Arun K Nayak Pdf

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment 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

Author : Donna Guillen
Publisher : BoD – Books on Demand
Page : 204 pages
File Size : 48,5 Mb
Release : 2013-02-13
Category : Technology & Engineering
ISBN : 9789535109877

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Nuclear Reactor Thermal Hydraulics and Other Applications by Donna Guillen Pdf

This book includes contributions from researchers around the world on numerical developments and applications to predict fluid flow and heat transfer, with an emphasis on thermal hydraulics computational fluid dynamics. Our ability to simulate larger problems with greater fidelity has vastly expanded over the past decade. The collection of material presented in this book augments the ever-increasing body of knowledge concerning the important topic of thermal hydraulics. Featured topics include coolant channel analysis, thermal hydraulic transport and mixing, as well as hydrodynamics and heat transfer processes. The contents of this book will interest researchers, scientists, engineers and graduate students.

Author : Anonim
Publisher : Unknown
Page : 960 pages
File Size : 51,8 Mb
Release : 1981
Category : Mechanics, Applied
ISBN : OSU:32435026160986

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Applied Mechanics Reviews by Anonim Pdf

Author : Anonim
Publisher : Unknown
Page : 704 pages
File Size : 49,5 Mb
Release : 1995
Category : Aeronautics
ISBN : UIUC:30112050127304

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Scientific and Technical Aerospace Reports by Anonim Pdf

Author : Anonim
Publisher : Unknown
Page : 128 pages
File Size : 44,7 Mb
Release : 1982
Category : Government publications
ISBN : WISC:89117116806

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Monthly Catalog of United States Government Publications by Anonim Pdf

Author : Anonim
Publisher : Unknown
Page : 1052 pages
File Size : 42,7 Mb
Release : 1993
Category : Power resources
ISBN : MINN:30000006337277

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Energy Research Abstracts by Anonim Pdf

Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.

Author : Jiyuan Tu,Guan Heng Yeoh,Chaoqun Liu
Publisher : Butterworth-Heinemann
Page : 458 pages
File Size : 55,9 Mb
Release : 2012-11-07
Category : Computers
ISBN : 9780080982434

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Computational Fluid Dynamics by Jiyuan Tu,Guan Heng Yeoh,Chaoqun Liu Pdf

An introduction to CFD fundamentals and using commercial CFD software to solve engineering problems, designed for the wide variety of engineering students new to CFD, and for practicing engineers learning CFD for the first time. Combining an appropriate level of mathematical background, worked examples, computer screen shots, and step by step processes, this book walks the reader through modeling and computing, as well as interpreting CFD results. The first book in the field aimed at CFD users rather than developers. New to this edition: A more comprehensive coverage of CFD techniques including discretisation via finite element and spectral element as well as finite difference and finite volume methods and multigrid method. Coverage of different approaches to CFD grid generation in order to closely match how CFD meshing is being used in industry. Additional coverage of high-pressure fluid dynamics and meshless approach to provide a broader overview of the application areas where CFD can be used. 20% new content .

Author : U.s. Nuclear Regulatory Comion
Publisher : CreateSpace
Page : 174 pages
File Size : 48,5 Mb
Release : 2014-05-21
Category : Science
ISBN : 1499636210

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Computational Fluid Dynamics Best Practice Guidelines for Dry Cask Applications by U.s. Nuclear Regulatory Comion Pdf

ABSTRACT Dry storage cask designs for spent nuclear fuel are submitted to the U.S. Nuclear Regulatory Commission (NRC) for certification under Title 10 of the Code of Federal Regulations (10 CFR) Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High- Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste.” The NRC staff technical review of these designs is performed in accordance with 10 CFR Part 72 and the “Standard Review Plan (SRP) for Spent Fuel Dry Storage Systems at a General License Facility” (NUREG-1536, 2010). To ensure that the cask and fuel material temperatures of the dry cask storage system will remain within the allowable limits or criteria for normal, off-normal, and accident conditions, a thermal review is performed as part of the application's technical review. Recent applications increasingly have used thermal-hydraulic analyses and computational fluid dynamics (CFD) codes (e.g., FLUENT) to demonstrate the adequacy of the thermal design. Therefore, in cooperation with the Division of Spent Fuel Storage and Transportation of the Office of Nuclear Material Safety and Safeguards, the Office of Nuclear Regulatory Research developed this guide to provide practical advice for reviewing CFD methods used in vendor applications and for achieving high-quality CFD simulations of a dry cask. To assist in the analysis, the report includes procedures, analysis methods, and acceptable assumptions.

Author : Neil E. Todreas,Mujid S. Kazimi,Mahmoud Massoud
Publisher : CRC Press
Page : 671 pages
File Size : 54,6 Mb
Release : 2021-12-13
Category : Science
ISBN : 9781482239614

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Nuclear Systems Volume II by Neil E. Todreas,Mujid S. Kazimi,Mahmoud Massoud Pdf

This book provides advanced coverage of a wide variety of thermal fluid systems and technologies in nuclear power plants, including discussions of the latest reactor designs and their thermal/fluid technologies. Beyond the thermal hydraulic design and analysis of the core of a nuclear reactor, the book covers other components of nuclear power plants, such as the pressurizer, containment, and the entire primary coolant system. Placing more emphasis on the appropriate models for small-scale resolution of the velocity and temperature fields through computational fluid mechanics, the book shows how this enhances the accuracy of predicted operating conditions in nuclear plants. It introduces considerations of the laws of scaling and uncertainty analysis, along with a wider coverage of the phenomena encountered during accidents. FEATURES Discusses fundamental ideas for various modeling approaches for the macro- and microscale flow conditions in reactors Covers specific design considerations, such as natural convection and core reliability Enables readers to better understand the importance of safety considerations in thermal engineering and analysis of modern nuclear plants Features end-of-chapter problems Includes a solutions manual for adopting instructors This book serves as a textbook for advanced undergraduate and graduate students taking courses in nuclear engineering and studying thermal/hydraulic systems in nuclear power plants.

Author : International Atomic Energy Agency
Publisher : Unknown
Page : 34 pages
File Size : 55,7 Mb
Release : 2007
Category : Business & Economics
ISBN : UOM:39015068765661

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Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants by International Atomic Energy Agency Pdf

This publication summarizes the results of the Technical Meeting on "Progress in development and use of coupled codes for accident analysis". The significantly increased capacity of new computation technology has made it possible to proceed the code coupling not only between neutronics and thermal hydraulics but also between thermal hydraulics and one or more other disciplines. This publication contains a review of state-of-the-art technologies in code coupling and its application to the accident analysis of nuclear power plants. The presentations and the papers given at the Technical Meeting are enclosed on the attached CD.--Publisher's description.

Author : Igor Pioro
Publisher : Woodhead Publishing
Page : 1112 pages
File Size : 41,5 Mb
Release : 2022-12-07
Category : Technology & Engineering
ISBN : 9780128226537

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Handbook of Generation IV Nuclear Reactors by Igor Pioro Pdf

Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors Includes new trends and developments since the first publication, as well as brand new case studies and appendices Covers the latest research, developments and design information surrounding generation IV nuclear reactors

Author : Y. A. Hassan,Chun H. Cho
Publisher : Unknown
Page : 68 pages
File Size : 51,7 Mb
Release : 1998
Category : Technology & Engineering
ISBN : STANFORD:36105021980086

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Proceedings of the ASME Nuclear Engineering Division, 1998 by Y. A. Hassan,Chun H. Cho Pdf

Contains eight papers presented at the November 1998 symposium on computational and thermal hydraulic analysis in nuclear reactors, organized by the nuclear engineering division of the ASME. The papers emphasize various areas of application of CFD and system computer codes in nuclear reactor analysi

Author : Anonim
Publisher : Unknown
Page : 1124 pages
File Size : 46,9 Mb
Release : 1982
Category : Government publications
ISBN : UIUC:30112063912353

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Monthly Catalogue, United States Public Documents by Anonim Pdf