[en] 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