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
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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
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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
