The comparison of available data on PWR assembly thermal behavior with analytical predictions
Name
MIT-EL-77-009-11428437.pdf
Size
3.06 MB
Format
Adobe PDF
Checksum (MD5)
2aed2e8437517b6a8b4419bae694c84a
Author(s)
Liu, Jack S. H.
Todreas, Neil E.
Date Issued
February 1979
Publisher
MIT Energy Laboratory
Series/Report no.
MIT-EL
77-009
Abstract
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).
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.
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