Void volumes in subcooled boiling systems
Author(s)Griffith, P.; Clark, John A.; Rohsenow, Warren M.
Massachusetts Institute of Technology. Division of Sponsored Research.
Massachusetts Institute of Technology. Heat Transfer Laboratory.
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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.
Cambridge, Mass. : M.I.T. Division of Industrial Cooperation, 
Technical report (Massachusetts Institute of Technology, Heat Transfer Laboratory) ; no. 12.