PWR steam-side chemistry follow program. Final report
Denting is the diametral reduction of Inconel 600 tubes at the support plates of several nuclear steam generators during operation. This tube deformation was shown to be caused by the expansion forces resulting from formation of voluminous oxide generated by corrosion of the carbon steel support plate. The denting phenomenon and potential methods for its inhibition were investigated in the laboratory using isothermal capsules and heated crevice (heat transfer) testing at temperatures relevant to operating steam generators. Both test methods simulate the tube-support plate geometry and materials. Mathematical models were developed to predict the denting behavior of isothermal capsules. Three additives were investigated as potential denting inhibitors. Soaking with calcium hydroxide or sodium phosphate under heat transfer conditions did not inhibit denting when the environment was recontaminated, in contrast to similar soaks in boric acid which inhibited denting for two to four weeks following recontamination. When the boric acid soak was followed by on-line boric acid treatment, inhibition was maintained.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA)
- OSTI ID:
- 5092694
- Report Number(s):
- EPRI-NP-2541; ON: DE82906483
- Country of Publication:
- United States
- Language:
- English
Similar Records
Neutralization of steam generator denting. Volume 2. Final report. [PWR]
Neutralization of steam generator denting. Volume 1. Final report. [PWR]
Related Subjects
CARBON STEELS
CORROSION
CORROSION INHIBITORS
PWR TYPE REACTORS
STEAM GENERATORS
TUBES
DEFORMATION
INCONEL 600
WATER CHEMISTRY
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
REACTORS
STEELS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled