Corrosion potential behavior in high-temperature water of noble metal-doped alloy coatings deposited by underwater thermal spraying
- 1. General Electric Corporate Research and Development Center, Schenectady, NY (United States)
- 2. General Electric Nuclear Energy, San Jose, CA (United States)
Description
Intergranular stress corrosion cracking (IGSCC) of sensitized stainless steel (SS) components in boiling water reactors (BWR) is a major concern. The SCC susceptibility of structural materials in high-temperature water is affected by the electrochemical corrosion potential (ECP). The ECP of type 304 stainless steel coated under water by hyper-velocity oxy-fuel (HVOF) and plasma-spray (PS) techniques using noble metal-doped powders was measured to evaluate the catalytic behavior in high-temperature water under various water chemistry conditions. Thermal-spray coatings of noble metal-doped powders exhibited catalytic behavior for the recombination of oxygen and hydrogen in high-temperature water, which caused ECP to decrease well below a critical value of -230 mVSHE for intergranular stress corrosion cracking protection in water. This was observed in water containing various amounts of oxygen and hydrogen peroxide when stoichiometric excess hydrogen was present
Additional details
Publishing Information
- Journal Title
- Corrosion (Houston)
- Journal Volume
- 52
- Journal Issue
- 6
- Journal Page Range
- p. 440-446.
- ISSN
- 0010-9312
- CODEN
- CORRAK
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27059059
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ADDITIVES; BWR TYPE REACTORS; CORROSION RESISTANT ALLOYS; ELECTROCHEMICAL CORROSION; FLAME SPRAYING; HYDROGEN; PALLADIUM; PROTECTIVE COATINGS; STAINLESS STEEL-304; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COATINGS; CORROSION; DEPOSITION; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; METALS; NICKEL ALLOYS; NONMETALS; PLATINUM METALS; POWER REACTORS; REACTORS; SPRAY COATING; STAINLESS STEELS; STEEL-CR19NI10; STEELS; SURFACE COATING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Paper presented at the 7th International Symposium on Materials Degradation in Nuclear Power Systems--Water Reactors, Breckenridge, CO (US), August 1995.