Journal article
An experimental investigation of subcooled choked flow in actual steam generator tube cracks
Abstract
The work presented here is an experimental investigation of the two-phase choked flow of initially subcooled water through a stress corrosion crack on the steam generator tube. The study was designed to provide an extensive experimental data set for predicting leak flow rates of nuclear reactor coolant using actual tube steam generator tubes sample. Five samples of steam generator tubes with stress corrosion axial cracks taken from steam …
Authors
Revankar ST; Riznic J
Journal
Nuclear Engineering and Design, Vol. 354, ,
Publisher
Elsevier
Publication Date
December 2019
DOI
10.1016/j.nucengdes.2019.06.006
ISSN
0029-5493