Modeling hideout processes in prototypical tube/tube support plate heated crevices
- 1. Electric Power Research Inst., Palo Alto, CA (United States)
- 2. San Jose State Univ., CA (United States)
- 3. Rockwell Science Center (United States)
Description
Over the past several years, several forms of corrosion of steam generator tubing have been a problem of significant concern. In local crevices and occluded regions, restricted flow combined with excessive heat fluxes results in the local concentration of non volatile impurities. Corrosion products and particulate matter accumulate in the form of porous deposits to create an aggressive environment leading to corrosion. A detailed model of the transport processes that processes that produce concentrated solutions locally in pressurized water reactor steam generators has been developed. The model describes the heat, mass and momentum transfer processes that occur in porous deposits of the crevices. The model is used to predict the concentration of a species in the pore solution as a function of time and at steady state and the model predictions are compared to available experimental data. Rockwell International has constructed a device which mimics the geometry and operating conditions of a Tube/Tube support plate crevice in a pressurized water reactor steam generator. This apparatus is instrumented to measure the crevice chemistry as a function of time. Under conditions with caustic contamination, solutions were extracted from the crevice and the bulk while the system was operating at temperature.The mass of caustic accumulated was measured as a function of time. A similar simulator has been utilized by San Jose State University. Using feed solutions of 30, 60, and 120 ppm sodium chloride and crevice powers of 85, 150 and 230 Watts, San Jose State University has measured the mass of sodium chloride in the packed crevice as a function of time. The application of the model to the experimental data obtained by Rockwell International and San Jose University is described in this paper.The modeling predictions were in good agreement with the experimental results. (authors)
Additional details
Additional titles
- Original title (English)
- Fontevraud 4. Contribution des expertises sur materiaux a la resolution des problemes rencontres dans les reacteurs a eau pressurisee
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- Fontevraud 4. Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors
- Imprint Pagination
- (v.1) 730 p.
- Journal Page Range
- p. 477-485
Conference
- Title
- International symposium Fontevraud 4. Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors
- Dates
- 14-18 Sep 1998
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 31000480
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONCENTRATION RATIO; CREVICE CORROSION; HEAT TRANSFER; MASS TRANSFER; MOMENTUM TRANSFER; PWR TYPE REACTORS; SODIUM CHLORIDES; STEAM GENERATORS; TUBES
- Descriptors DEC
- ALKALI METAL COMPOUNDS; BOILERS; CHEMICAL REACTIONS; CHLORIDES; CHLORINE COMPOUNDS; CORROSION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HALIDES; HALOGEN COMPOUNDS; POWER REACTORS; REACTORS; SODIUM COMPOUNDS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs. Imprint:Fontevraud 4. Contribution des expertises sur materiaux a la resolution des problemes rencontres dans les reacteurs a eau pressurisee