A device has been constructed which crevice in a pressurized water reactor (PWR) mimics the geometry and operating conditions of a tube/tube support plate steam generator. This apparatus is instrumented to measure the tube wall temperature in the crevice, the free span and crevice potentials, and the crevice chemistry. Results have been obtained for 280°C NaOH solutions continuously pumped through the autoclave under several crevice temperature and power levels. Changes in tube wall temperature changes after superheat was applied indicated that various depths in the crevice underwent several thermal-hydraulic transitions before reaching equilibrium conditions. The lower third of the crevice was wetted at equilibrium. Sodium hydroxide concentrated at rates near the theoretical limit until equilibrium was reached at concentration factors...
Keywords: heated crevice, steam generator, hideout, alloy 600, PWR, heat transfer, tubesheet crevice, tube support crevice