Use of computational fluid dynamics codes for safety analysis of nuclear reactor systems : summary report of a technical meeting jointly organized by the International Atomic Energy Agency and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development held in Pisa, Italy, 11-14 November 2002
Author(s)
Bibliographic Information
Use of computational fluid dynamics codes for safety analysis of nuclear reactor systems : summary report of a technical meeting jointly organized by the International Atomic Energy Agency and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development held in Pisa, Italy, 11-14 November 2002
(IAEA-TECDOC, 1379)
International Atomic Energy Agency, 2003.11
Available at 1 libraries
  Aomori
  Iwate
  Miyagi
  Akita
  Yamagata
  Fukushima
  Ibaraki
  Tochigi
  Gunma
  Saitama
  Chiba
  Tokyo
  Kanagawa
  Niigata
  Toyama
  Ishikawa
  Fukui
  Yamanashi
  Nagano
  Gifu
  Shizuoka
  Aichi
  Mie
  Shiga
  Kyoto
  Osaka
  Hyogo
  Nara
  Wakayama
  Tottori
  Shimane
  Okayama
  Hiroshima
  Yamaguchi
  Tokushima
  Kagawa
  Ehime
  Kochi
  Fukuoka
  Saga
  Nagasaki
  Kumamoto
  Oita
  Miyazaki
  Kagoshima
  Okinawa
  Korea
  China
  Thailand
  United Kingdom
  Germany
  Switzerland
  France
  Belgium
  Netherlands
  Sweden
  Norway
  United States of America
Note
Includes bibliographical references
CD-ROM contains the proceedings and the presentations of the Technical Meeting on use of computational fluid dynamics (CFD) codes for safety analysis of reactor systems, including containment, held from 11 to 14 November 2002 in Pisa, Italy
Description and Table of Contents
Description
With further progress in safety analysis techniques, the increasing use of three dimensional computational fluid dynamics (CFD) codes for nuclear applications is expected. The present publication constitutes 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 Pisa, Italy, from 11 to 14 November 2002. It includes summaries of the presentations and of the discussions as well as conclusions and recommendations for further work. A CD containing the entire collection of papers is provided as a supplement to this report.
CFD codes provide a unique tool for analysis of local phenomena and have a broad potential for qualitative assessment in areas in which traditional methods (lumped parameter or 1-D simulations) are inadequate. They contribute to a deeper understanding of flow physics, and thus lead to better designs at reduced cost and/or to more precisely quantified safety margins. In nuclear safety, CFD codes have a complementary role to play in combination with traditional system codes, particularly in those areas where multidimensional aspects are important. Combined applications, supported by proper experiments, may guarantee a more precise evaluation of safety margins.
by "Nielsen BookData"