Correlation of tube support structure studies. Final report

Technical Report · Tue Jul 01 04:00:00 EDT 1986

OSTI ID:5539376

Pathania, R S; Balakrishnan, P V

The objective of this project was to review, analyze and evaluate the results of projects on corrosion of tube support structure materials sponsored by EPRI and to apply these results to nuclear steam generators in order to minimize corrosion problems in operating units. The project consisted of three tasks. In Task 1, the results of isothermal corrosion tests performed by Westinghouse and Combustion Engineering were analyzed and a model relating the corrosion rate to high temperature pH and chloride concentration was developed. It showed that the pH of HC1, and CuCl/sub 2/ and FeCl/sub 2/ solutions was affected by the corrosion reaction, whereas that of MgCl/sub 2/ and sea water was not. Task 2 analyzed the results from heat transfer tests in model boilers, pot boilers and heated crevice devices. The high temperature chemistry of test solutions was calculated as a function of the concentration factor. The correlation developed from isothermal tests was then applied to calculate the chloride concentrations, superheats and concentration factors within crevices. A relationship was developed between corrosion rate, bulk chemistry and superheat. The concentration within the crevice was strongly dependent on the crevice superheat and weakly dependent on the bulk chloride. In Task 3, the results of Tasks 1 and 2 were applied to steam generators. Correlations were developed relating corrosion rate in crevices to bulk chloride concentration in the blowdown in sea water and neutral chloride. The predicted times to denting were in good agreement with observations of denting in sea and brackish water plants. Recommendations are made to minimize denting in operating plants. 40 refs., 25 figs., 19 tabs.

• Research Organization: Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.
• OSTI ID: 5539376
• Report Number(s): EPRI-NP-4672; ON: TI86920410
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Light-Water Moderated
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36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
BOILERS
CHALCOGENIDES
CHEMISTRY
CHLORIDES
CHLORINE COMPOUNDS
COOLING SYSTEMS
CORROSION DENTING
DEFORMATION
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HALIDES
HALOGEN COMPOUNDS
HEAT TRANSFER
HYDRAULICS
IRON COMPOUNDS
IRON ORES
IRON OXIDES
MAGNETITE
MECHANICS
MINERALS
ORES
OXIDE MINERALS
OXIDES
OXYGEN COMPOUNDS
PH VALUE
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SECONDARY COOLANT CIRCUITS
STEAM GENERATORS
TESTING
TRANSITION ELEMENT COMPOUNDS
TUBES
VAPOR GENERATORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS