Published August 1996
| Version v1
Journal article
Electrochemical corrosion potential models for boiling-water reactor applications
Creators
- 1. General Electric Nuclear Energy, Pleasanton, CA (United States). Vallecitos Nuclear Center
- 2. General Electric Corporate Research and Development, Schenectady, NY (United States)
- 3. Electric Power Research Inst., Palo Alto, CA (United States)
Description
The electrochemical corrosion potential (ECP) of stainless steel (SS) was measured under simulated boiling-water reactor (BWR) coolant circuit conditions using a rotating cylinder electrode (RCE). Based upon those measurements, an empirical model was developed to predict ECP of structure materials in a BWR primary circuit as a function of hydrogen, oxygen, and hydrogen peroxide concentrations in the reactor coolant and of the water flow velocity. Results of ECP modeling using the H2, O2, and H2O2 concentrations calculated by the radiolysis model were compared to internal ECP data obtained in an operating reactor
Additional details
Publishing Information
- Journal Title
- Corrosion (Houston)
- Journal Volume
- 52
- Journal Issue
- 8
- Journal Page Range
- p. 618-625.
- ISSN
- 0010-9312
- CODEN
- CORRAK
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27075561
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BWR TYPE REACTORS; CORROSION RESISTANT ALLOYS; CRACK PROPAGATION; ELECTROCHEMICAL CORROSION; FLOW RATE; INTERGRANULAR CORROSION; MATHEMATICAL MODELS; PRIMARY COOLANT CIRCUITS; STAINLESS STEELS; STRESS CORROSION; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; COOLING SYSTEMS; CORROSION; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Presented at the 7. international symposium on environmental degradation of materials in nuclear power systems, August 1995, Breckenridge, CO (US).