Inscrição na biblioteca: Guest
International Heat Transfer Conference 13
Graham de Vahl Davis (open in a new tab) School of Mechanical and Manufacturing Engineering, University of New South Wales, Kensington, NSW, Australia
Eddie Leonardi (open in a new tab) Computational Fluid Dynamics Research Laboratory, School of Mechanical and Manufacturing Engineering, The University of New South Wales, Sydney, Australia 2052

ISSN Online: 2377-424X

ISBN CD: 1-56700-226-9

ISBN Online: 1-56700-225-0

THERMAL STRATIFICATION IN NUCLEAR REACTOR PIPING SYSTEM

page 10
DOI: 10.1615/IHTC13.p7.30
Get accessGet access

RESUMO

Stratified flows can occur when two different layers of the same liquid at different temperatures flow separately in horizontal pipes without appreciable mixing. This condition may lead to considerable top to bottom temperature gradient on the pipe wall and may result in excessive differential expansion from upper to lower parts of the pipe threatening its integrity. This paper reports a thermal-hydraulic study for one phase stratified flows, under conditions similar to those of nuclear reactors cooling piping systems. An experimental facility simulates the steam generator injection nozzle of a pressurized water reactor. Numerical results obtained with a commercial finite volume CFD code CFX-5.7 are presented and compared with experimental data. Both results confirmed the occurrence of thermal stratification and of the striping phenomenon, the oscillation of the hot and cold interface, under simulated conditions.

Portal Digital Begell Biblioteca digital da Begell eBooks Diários Referências e Anais Coleções de pesquisa Políticas de preços e assinaturas Begell House Contato Language English 中文 Русский Português German French Spain