An oxide-semiconductance model of nodular corrosion and its application to zirconium alloy development
Creators
- 1. General Electric Co., Schenectady, NY (USA). Research and Development Center
Description
The mechanisms of nodule initiation and growth on susceptible zirconium alloys both in- and ex-reactor remain unclear. Hypotheses citing locally inadequate concentrations of alloying elements generally can explain more experimental observations than, for example, those relying solely on electrochemical activity at second phase particles, or residual stress, or texture. Since the alloying additions that protect zirconium from rapid oxidation in high-temperature, high-pressure steam all have normal oxidation states other than IV, it seems likely that the incorporation of aliovalent oxides into the monoclinic zirconia lattice plays an important role in providing that protection. Corrosion experiments indicated that effective elements are those forming aliovalent cations that can substitute for Zr(IV) and alter the defect structure without disrupting the oxide matrix. Laboratory alloy optimization for a combination of immunity to nodular corrosion in steam and minimum uniform corrosion in water requires in-reactor confirmation. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 184
- Journal Issue
- 1
- Series
- J. Nucl. Mater.
- Journal Page Range
- 65-77
- ISSN
- 0022-3115
- CODEN
- JNUMA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 22088542
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALLOY SYSTEMS; BISMUTH ALLOYS; COMPARATIVE EVALUATIONS; CORROSION; FUEL CANS; HIGH TEMPERATURE; OPTIMIZATION; OXIDES; RUTHENIUM ADDITIONS; STEAM; TIN ALLOYS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; EVALUATION; OXYGEN COMPOUNDS