Published August 1996 | Version v1
Journal article

Electrochemical corrosion potential models for boiling-water reactor applications

  • 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

Optional Information

Notes
Presented at the 7. international symposium on environmental degradation of materials in nuclear power systems, August 1995, Breckenridge, CO (US).