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International Heat Transfer Conference 13

ISSN: 2377-424X (online)
ISSN: 2377-4371 (flashdrive)

THERMAL STRATIFICATION IN NUCLEAR REACTOR PIPING SYSTEM

Hugo Cesar Rezende
Nuclear Technology Development Center − Belo Horizonte, Brazil

Moyses Alberto Navarro
Nuclear Technology Development Center − Belo Horizonte, Brazil

Andre Augusto Campagnole dos Santos
Federal University of Minas Gerais − Belo Horizonte, Brazil

DOI: 10.1615/IHTC13.p7.30
10 pages

Résumé

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.

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Bibliothèque numérique IHTC

Measurement of fluid temperature with an arrangement of three thermocouples