Published 2011 | Version v1
Miscellaneous

Ceramic coatings for metallic components in supercritical water-cooled reactors

  • 1. National Research Council, Inst. for Fuel Cell Innovation, Vancouver, BC (Canada)
  • 2. Univ. of New Brunswick, Dept. of Chemical Engineering, Fredericton, NB (Canada)

Description

Zr-2.5Nb, a Zirconium alloy, cannot be used itself as a material of construction for SCWR applications, although it is desirable, from a neutron economy standpoint to use zirconium alloys for in-core materials. Thus, improving the oxidation resistance of zirconium through corrosion-resistant coatings is of interest for the SCWR. Plasma Electrolytic Oxidation (PEO) deposition was used to fabricate oxide coatings on Zr-2.5%Nb substrates from a sodium aluminate solution, which yielded an Al(0.18)Zr(0.82)O(1.91) coating. Spray Pyrolysis Deposition (SPD) was also used to fabricate Cr2O3 films on Zircaloy substrates. The samples were tested under supercritical water conditions (500oC, 25 MPa, deaerated) at exposure times of 100 and 250 hours. A reduction in corrosion rates of up to 50% at 100 hours of exposure, and up to 28% at 250 hours of exposure was noted. Both samples show improved corrosion resistance compared to the uncoated substrate. (author)

Part of:
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-02-5
Imprint Title
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors
Imprint Pagination
90.1 Megabytes
Journal Page Range
[11 p.]

Conference

Title
5. International Symposium on Supercritical-Water-Cooled Reactors
Dates
13-16 Mar 2011
Place
Vancouver, BC (Canada)

Optional Information

Notes
11 refs., 1 tab., 7 figs.