Summary Review On The Application Of Computational Fluid Dynamics In Nuclear Power Plant Design
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Summary Review On The Application Of Computational Fluid Dynamics In Nuclear Power Plant Design
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Author : IAEA
language : en
Publisher: International Atomic Energy Agency
Release Date : 2022-03-28
Summary Review On The Application Of Computational Fluid Dynamics In Nuclear Power Plant Design written by IAEA and has been published by International Atomic Energy Agency this book supported file pdf, txt, epub, kindle and other format this book has been release on 2022-03-28 with Business & Economics categories.
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.
Summary Review On The Application Of Computational Fluid Dynamics In Nuclear Power Plant Design
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Author :
language : en
Publisher:
Release Date : 2022
Summary Review On The Application Of Computational Fluid Dynamics In Nuclear Power Plant Design written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2022 with Computational fluid dynamics categories.
"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.
Advances Of Computational Fluid Dynamics In Nuclear Reactor Design And Safety Assessment
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Author : Jyeshtharaj Joshi
language : en
Publisher: Woodhead Publishing
Release Date : 2019-06-15
Advances Of Computational Fluid Dynamics In Nuclear Reactor Design And Safety Assessment written by Jyeshtharaj Joshi and has been published by Woodhead Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2019-06-15 with Science categories.
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
Computational Fluid Dynamics Best Practice Guidelines For Dry Cask Applications
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Author : U.s. Nuclear Regulatory Comion
language : en
Publisher: CreateSpace
Release Date : 2014-05-21
Computational Fluid Dynamics Best Practice Guidelines For Dry Cask Applications written by U.s. Nuclear Regulatory Comion and has been published by CreateSpace this book supported file pdf, txt, epub, kindle and other format this book has been release on 2014-05-21 with Science categories.
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.
Nuclear Reactor Thermal Hydraulics And Other Applications
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Author : Donna Guillen
language : en
Publisher: BoD – Books on Demand
Release Date : 2013-02-13
Nuclear Reactor Thermal Hydraulics And Other Applications written by Donna Guillen and has been published by BoD – Books on Demand this book supported file pdf, txt, epub, kindle and other format this book has been release on 2013-02-13 with Technology & Engineering categories.
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.
Applied Mechanics Reviews
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Author :
language : en
Publisher:
Release Date : 1981
Applied Mechanics Reviews written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1981 with Mechanics, Applied categories.
Use And Development Of Coupled Computer Codes For The Analysis Of Accidents At Nuclear Power Plants
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Author : International Atomic Energy Agency
language : en
Publisher:
Release Date : 2007
Use And Development Of Coupled Computer Codes For The Analysis Of Accidents At Nuclear Power Plants written by International Atomic Energy Agency and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2007 with Business & Economics categories.
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.
Scientific And Technical Aerospace Reports
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Author :
language : en
Publisher:
Release Date : 1995
Scientific And Technical Aerospace Reports written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1995 with Aeronautics categories.
Monthly Catalog Of United States Government Publications
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Author :
language : en
Publisher:
Release Date : 1982
Monthly Catalog Of United States Government Publications written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1982 with Government publications categories.
Nuclear Systems Volume Ii
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Author : Neil E. Todreas
language : en
Publisher: CRC Press
Release Date : 2021-12-13
Nuclear Systems Volume Ii written by Neil E. Todreas and has been published by CRC Press this book supported file pdf, txt, epub, kindle and other format this book has been release on 2021-12-13 with Science categories.
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.