Abo Bibliothek: Guest
Advanced Course in Heat Transfer in Nuclear Reactor Safety
September, 1-5, 1980, Dubrovnik, Yugoslavia

DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf


ISBN Print: 978-0-89116-223-0

2.9 Critical Flow of Flashing Water through Long Tubes

pages 409-419
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.210
Get accessGet access

ABSTRAKT

Several models have been proposed to calculate critical flow-rates. Our experimental data on critical flow of flashing water through long tubes show poor agreement with these models except by one : Lackme's model, which has been recently established.
This model considers that the flashing liquid flow is made up of satured and superheated liquid. It enables to determine not only the value of the critical flow-rate, but also the values of the flow parameters at the critical section.
In this paper comparisons with our experimental data are given and it is shown that LacKme's model is a promising tool for safety analysis of nuclear plants, and, more generally, for design engineering.

Digitales Portal Digitale Bibliothek eBooks Zeitschriften Referenzen und Berichte Forschungssammlungen Preise und Aborichtlinien Begell House Kontakt Language English 中文 Русский Português German French Spain