Published 1996 | Version v1
Book

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).

Optional Information

Secondary number(s)
CONF-950926--.