Published April 1979 | Version v1
Report Restricted

PWR blowdown heat transfer separate-effects program data evaluation report. THTF test series II

Creators

Description

Thermal-hydraulic phenomena are analyzed for test series II conducted at the Thermal-Hydraulic Test Facility (THTF) as part of the Pressurized-Water Reactor Blowdown Heat Transfer Separate-Effects Program at Oak Ridge National Laboratory. A discussion of the effects of test section outlet fluid subcooling, bundle power, and inactive rods on thermal-hydraulic behavior in the THTF is presented. A mechanism that may be responsible for departure from nucleate boiling (DNB) in the bundle of the THTF is presented. Heater rod surface temperatures are found to be sensitive to relatively small variations in flow

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A10/MF A01.

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Additional details

Publishing Information

Imprint Pagination
202 p.
Report number
NUREG/CR--0539

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10473246
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BLOWDOWN; HEAT TRANSFER; LOSS OF COOLANT; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION
Descriptors DEC
ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
ORNL/NUREG--53.