Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design PDF full book. Access full book title Summary Review on the Application of Computational Fluid Dynamics in Nuclear Power Plant Design by IAEA. Download full books in PDF and EPUB format.
Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201004214
Category : Business & Economics
Languages : en
Pages : 121
Get Book Here
Book Description
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: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201004214
Category : Business & Economics
Languages : en
Pages : 121
Get Book Here
Book Description
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:
Publisher:
ISBN: 9789201003218
Category : Computational fluid dynamics
Languages : en
Pages : 0
Get Book Here
Book Description
"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: Francesco D'Auria
Publisher: Elsevier
ISBN: 0323856098
Category : Technology & Engineering
Languages : en
Pages : 818
Get Book Here
Book Description
Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 3, Procedures and Applications includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided. - Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics - Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix - Covers applicable nuclear reactor safety considerations and design technology throughout
Author:
Publisher:
ISBN:
Category : Mechanics, Applied
Languages : en
Pages : 960
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 704
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages :
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1052
Get Book Here
Book Description
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:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 864
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Abstracts
Languages : en
Pages : 66
Get Book Here
Book Description
Presets the report of the joint IAEA and OECD/NEA technical meeting on the Use of CFD Codes for Safety Analysis of Reactor Systems, including Containment, held in November 2002. It includes summaries of the presentations and of the discussions as well as conclusions and recommendations for further work.
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1124
Get Book Here
Book Description
