Published February 1979 | Version v1
Report Restricted

The comparison of available data on PWR assembly thermal behavior with analytical predictions. Topical report (final)

Creators

Description

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 was 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 can successfully predict the PWR normal operating conditions but cannot predict the trend under bulk quality conditions

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.

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Additional details

Publishing Information

Imprint Pagination
100 p.
Report number
PB--299393

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
11552867
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTER CALCULATIONS; FUEL ASSEMBLIES; HEAT TRANSFER; PWR TYPE REACTORS; THERMAL ANALYSIS
Descriptors DEC
ENERGY TRANSFER; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS