Modelling of crack chemistry in sensitized stainless steel in boiling water reactor environments
Description
An advanced model has been used to predict the chemistry and potential in a stress corrosion crack in sensitized stainless steel in a boiling water reactor (BWR) environment. The model assumes trapezoidal crack geometry, incorporates anodic reaction and cathodic reduction within the crack, and takes into account the limited solubility of cations in high temperature water. The results indicate that the crack tip potential is not independent of the external potential, and that the reactions on the walls of the crack must be included for reliable prediction. Accordingly, both the modelling assumptions of Ford and Andresen and of Macdonald and Urquidi-Macdonald, whilst having merit, are not fully satisfactory. Extended application of the model for improved prediction of stress corrosion crack growth rate is constrained by limitations in electrochemical data which are currently inadequate. (author)
Additional details
Publishing Information
- Journal Title
- Corrosion Science
- Journal Volume
- 39
- Journal Issue
- 4
- Journal Page Range
- p. 789-805.
- ISSN
- 0010-938X
- CODEN
- CRRSAA
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 28053705
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; ELECTROCHEMISTRY; MATHEMATICAL MODELS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS