Void volumes in subcooled boiling systems
Name
HTL_TR_1958_012.pdf
Size
9.67 MB
Format
Adobe PDF
Checksum (MD5)
8966097bf49bba1498d6c8f0ff05d01e
Author(s)
Griffith, P.
Clark, John A.
Rohsenow, Warren M.
Date Issued
1958
Publisher
Cambridge, Mass. : M.I.T. Division of Industrial Cooperation, [1958]
Series/Report no.
Technical report (Massachusetts Institute of Technology, Heat Transfer Laboratory) ; no. 12.
Abstract
Introduction: Knowledge of the pressure drop in a channel and the resulting flow redistribution is essential in predicting the performance of a nuclear reactor. The pressure drop in a channel which is experiencing boiling is, in part, dependent on the void volumes present. In this report the results of an experimental investigation of the void volumes in systems at 500, 1000, and 1500 psia are presented. A method of predicting the void volumes is then presented. Finally, a comparison of measured end predicted void volumes is made with data collected at 2000 psia under completely different conditions. Agreement with the data is very good.
Subjects
Boiling-points.
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