Published July 2013 | Version v1
Journal article

Protection of Zirconium by Alumina- and Chromia-Forming Steels under High-Temperature Steam Exposure

  • 1. Oak Ridge National Lab,, Oak Ridge, TN (United States). Fuel Cycle and Isotopes Div.
  • 2. Oak Ridge National Lab,, Oak Ridge, TN (United States). Materials Science and Technology Div.

Description

The project examined the viability of advanced oxidation-resistant Fe-base alloys to protect zirconium from rapid oxidation in high-temperature steam environments. Specimens were produced such that outer layers of FeCrAl ferritic alloy and Type 310 austenitic stainless steel were incorporated on the surface of zirconium metal slugs. The specimens were exposed to high-temperature 0.34 MPa steam at 1200 and 1300 deg C. The primary degradation mechanism for the protective layer was interdiffusion with the zirconium, as opposed to high-temperature oxidation in steam. The FeCrAl layer experienced less degradation and protected the zirconium at 1300 deg C for 8 h. Constituents of the Fe-base alloys rapidly diffused into the zirconium and resulted in the formation of various intermetallic layers at the interface and precipitates inside the bulk zirconium. The nature of this interaction for FeCrAl and 310SS has been characterized by use of microscopic techniques as well as computational thermodynamics. Finally, a reactor physics discussion on the applicability of these protective layers in light-water-reactor nuclear fuel structures is offered.

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
438
Journal Issue
1-3
Journal Page Range
p. 64-71
ISSN
0022-3115

Optional Information

Contract/Grant/Project number
AC05-00OR22725
Funding organization
US Department of Energy (United States). Office of Nuclear Energy
Secondary number(s)
OSTIID--1072989