The comparison of available data on PWR assembly thermal behavior with analytical predictions
"PB-299 393." Topical report for Task #3 of the Nuclear Reactor Safety Research Program sponsored by New England Electric System, Northeast Utilities Service Co. under the MIT Energy Laboratory Electric Power Program.
Main Authors: | , |
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Format: | Technical Report |
Language: | en_US |
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MIT Energy Laboratory
2006
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Online Access: | http://hdl.handle.net/1721.1/31235 |
_version_ | 1826216351086149632 |
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author | Liu, Jack S. H. Todreas, Neil E. |
author_facet | Liu, Jack S. H. Todreas, Neil E. |
author_sort | Liu, Jack S. H. |
collection | MIT |
description | "PB-299 393."
Topical report for Task #3 of the Nuclear Reactor Safety Research Program sponsored by New England Electric System, Northeast Utilities Service Co. under the MIT Energy Laboratory Electric Power Program. |
first_indexed | 2024-09-23T16:46:16Z |
format | Technical Report |
id | mit-1721.1/31235 |
institution | Massachusetts Institute of Technology |
language | en_US |
last_indexed | 2024-09-23T16:46:16Z |
publishDate | 2006 |
publisher | MIT Energy Laboratory |
record_format | dspace |
spelling | mit-1721.1/312352019-04-12T07:24:17Z The comparison of available data on PWR assembly thermal behavior with analytical predictions Liu, Jack S. H. Todreas, Neil E. "PB-299 393." Topical report for Task #3 of the Nuclear Reactor Safety Research Program sponsored by New England Electric System, Northeast Utilities Service Co. under the MIT Energy Laboratory Electric Power Program. The comparison of available data with analytical predictions has been illustrated in this report. Since few data on the cross flow are available, a study of parameters in the transverse momentum equation were performed to assess the sensitivity of results to their assumed values. It is confirmed that effects of these parameters on the overall results are not significant under PWR operating conditions. Data on subchannel properties of quality and mass flux were also assessed. From the data comparisons, it is evident that COBRA which is the tool of the simplified method can successfully predict the PWR normal operating conditions and cannot predict the trend under bulk quality conditions (e>0.02). New England Electric System & Northeast Utilities Service Co. 2006-03-06T16:43:56Z 2006-03-06T16:43:56Z 1979-02 Technical Report 11428437 http://hdl.handle.net/1721.1/31235 en_US MIT-EL 77-009 3207389 bytes application/pdf application/pdf MIT Energy Laboratory |
spellingShingle | Liu, Jack S. H. Todreas, Neil E. The comparison of available data on PWR assembly thermal behavior with analytical predictions |
title | The comparison of available data on PWR assembly thermal behavior with analytical predictions |
title_full | The comparison of available data on PWR assembly thermal behavior with analytical predictions |
title_fullStr | The comparison of available data on PWR assembly thermal behavior with analytical predictions |
title_full_unstemmed | The comparison of available data on PWR assembly thermal behavior with analytical predictions |
title_short | The comparison of available data on PWR assembly thermal behavior with analytical predictions |
title_sort | comparison of available data on pwr assembly thermal behavior with analytical predictions |
url | http://hdl.handle.net/1721.1/31235 |
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