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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Format: | Technical Report |
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Cambridge, Mass. : M.I.T. Division of Industrial Cooperation, [1958]
2011
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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. |
first_indexed | 2024-09-23T12:19:18Z |
format | Technical Report |
id | mit-1721.1/61433 |
institution | Massachusetts Institute of Technology |
last_indexed | 2024-09-23T12:19:18Z |
publishDate | 2011 |
publisher | Cambridge, Mass. : M.I.T. Division of Industrial Cooperation, [1958] |
record_format | dspace |
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 |
work_keys_str_mv | AT griffithp voidvolumesinsubcooledboilingsystems AT clarkjohna voidvolumesinsubcooledboilingsystems AT rohsenowwarrenm voidvolumesinsubcooledboilingsystems |