Heated crevice investigation of the effects of feedwater chemistry on crevice chemistry and crevice potential
- Rockwell Science Center, Thousand Oaks, CA (United States)
- Electric Power Research Inst., Palo Alto, CA (United States)
A device has been constructed which mimics the geometry and operating conditions of a tube/tube support plate crevice in a pressurized water reactor (PWR) 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 in the 10{sup 4} range.
- OSTI ID:
- 367716
- Report Number(s):
- CONF-960389-; TRN: IM9640%%462
- Resource Relation:
- Conference: National Association of Corrosion Engineers (NACE) annual corrosion conference and exposition: water and waste water industries, Denver, CO (United States), 24-29 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of Corrosion/96 conference papers; PB: [6615] p.
- Country of Publication:
- United States
- Language:
- English
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