Void volumes in subcooled boiling systems

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...

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Main Authors: Griffith, P., Clark, John A., Rohsenow, Warren M.
Other Authors: Massachusetts Institute of Technology. Division of Sponsored Research.
Format: Technical Report
Published: Cambridge, Mass. : M.I.T. Division of Industrial Cooperation, [1958] 2011
Subjects:
Online Access:http://hdl.handle.net/1721.1/61433
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author Griffith, P.
Clark, John A.
Rohsenow, Warren M.
author2 Massachusetts Institute of Technology. Division of Sponsored Research.
author_facet Massachusetts Institute of Technology. Division of Sponsored Research.
Griffith, P.
Clark, John A.
Rohsenow, Warren M.
author_sort Griffith, P.
collection MIT
description 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.
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spelling mit-1721.1/614332019-04-10T18:06:13Z Void volumes in subcooled boiling systems Griffith, P. Clark, John A. Rohsenow, Warren M. Massachusetts Institute of Technology. Division of Sponsored Research. Massachusetts Institute of Technology. Heat Transfer Laboratory. Boiling-points. 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. Office of Naval Research D.S.R. Project 2011-03-04T23:22:03Z 2011-03-04T23:22:03Z 1958 Technical Report 14871783 http://hdl.handle.net/1721.1/61433 Technical report (Massachusetts Institute of Technology, Heat Transfer Laboratory) ; no. 12. [41] leaves in various pagings (some unnumbered) application/pdf Cambridge, Mass. : M.I.T. Division of Industrial Cooperation, [1958]
spellingShingle Boiling-points.
Griffith, P.
Clark, John A.
Rohsenow, Warren M.
Void volumes in subcooled boiling systems
title Void volumes in subcooled boiling systems
title_full Void volumes in subcooled boiling systems
title_fullStr Void volumes in subcooled boiling systems
title_full_unstemmed Void volumes in subcooled boiling systems
title_short Void volumes in subcooled boiling systems
title_sort void volumes in subcooled boiling systems
topic Boiling-points.
url http://hdl.handle.net/1721.1/61433
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AT clarkjohna voidvolumesinsubcooledboilingsystems
AT rohsenowwarrenm voidvolumesinsubcooledboilingsystems