Long-term in situ corrosion investigation of Zr alloys in simulated PWR environment by electrochemical measurements
- 1. Univ. of Erlangen (Germany)
- 2. Siemens AG, Erlangen (Germany). Power Generation Group
Description
The corrosion behavior of Zircaloy-type alloys with different tin contents of 1.55, 0.70, and 0.55 wt% was studied at 350 C and 17 MPa in an environment similar to PWR primary water. Impedance spectra were taken at time intervals and evaluated for thickness and morphology of the oxide layer as well as for its electrical resistance. The tests without any temperature and pressure cycling showed similar oxidation behavior with repeated transitions as in discontinuously performed standard autoclave tests. Early in the pre-transition range, a dense oxide layer is formed, and fast changes of corrosion potential and electrical resistance are observed. The dense layer increases in thickness and homogeneity up to the transition, where a sudden breakdown occurs. Abrupt changes of the corrosion potential and electrical resistance were observed also at those points. After transition, a new dense layer is built up. The corrosion potential changes are caused by a decrease of the electrical corrosion current with increasing oxide layer thickness, by the formation of a potential drop over the high-resistance dense oxide layer, and by structural changes at the transition points. In general, alloys with different tin contents show similar behavior. However, they show differences in the time to transition, the kinetic constants deduced from their impedance spectra, and in the ionic and electronic resistance of the dense inner layer controlling corrosion
Additional details
Publishing Information
- Publisher
- American Society for Testing and Materials.
- Imprint Place
- West Conshohocken, PA (United States)
- ISBN
- 0-8031-2406-6
- Imprint Title
- Zirconium in the nuclear industry: Eleventh international symposium
- Imprint Pagination
- 911 p.
- Series
- American Society for Testing and Materials STP 1295.
- Journal Page Range
- p. 181-202.
- ISSN
- 1050-7558
Conference
- Title
- 11. international symposium on zirconium in the nuclear industry.
- Dates
- 11-14 Sep 1995.
- Place
- Garmisch-Partenkirchen (Germany).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28058488
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; CORROSION PRODUCTS; ELECTROCHEMISTRY; OXIDES; PWR TYPE REACTORS; TIN ADDITIONS; ZIRCALOY
- Descriptors DEC
- ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; ENRICHED URANIUM REACTORS; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-950926--.