Show simple item record

dc.contributor.authorGriffith, P.en_US
dc.contributor.authorClark, John A.en_US
dc.contributor.authorRohsenow, Warren M.en_US
dc.contributor.otherMassachusetts Institute of Technology. Division of Sponsored Research.en_US
dc.contributor.otherMassachusetts Institute of Technology. Heat Transfer Laboratory.en_US
dc.date.accessioned2011-03-04T23:22:03Z
dc.date.available2011-03-04T23:22:03Z
dc.date.issued1958en_US
dc.identifier14871783en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/61433
dc.description.abstractIntroduction: 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.en_US
dc.description.sponsorshipOffice of Naval Research D.S.R. Projecten_US
dc.format.extent[41] leaves in various pagings (some unnumbered)en_US
dc.publisherCambridge, Mass. : M.I.T. Division of Industrial Cooperation, [1958]en_US
dc.relation.ispartofseriesTechnical report (Massachusetts Institute of Technology, Heat Transfer Laboratory) ; no. 12.en_US
dc.subjectBoiling-points.en_US
dc.titleVoid volumes in subcooled boiling systemsen_US
dc.typeTechnical Reporten_US


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record