Published April 2019 | Version v1
Journal article

Effects of zirconium and oxygen on the oxidation of FeCrAl-ODS alloys under air and steam conditions up to 1500 °C

  • 1. Graduate School of Engineering, Hokkaido University, Sappor 060-8628 (Japan)
  • 2. Faculty of Engineering, Hokkaido University, Sappor 060-8628 (Japan)
  • 3. Graduate School of Engineering, Hokkaido University (Japan)
  • 4. Nippon Nuclear Fuel Development Co., LTD, Oarai, 311-1313 (Japan)

Description

Highlights: • Effects of zirconium and oxygen on the oxidation of FeCrAl-ODS alloys was studied. • Zr and O added FeCrAl-ODS alloys achieve excellent high-temperature strength and oxidation resistance. • Addition of Zr and excessive oxygen can also improve adhesion of alumina scale at 1400 °C. • Once the protective alumina scale is lost during oxidation at 1500 ℃ just beneath the melting point of alloys. - Abstract: Effects of Zr and excessive oxygen addition on the oxidation behavior of FeCrAl-ODS alloys are evaluated by high-temperature air and steam oxidation tests together with analyses using the thermochemical multiphase computer software FactSage. Zr addition to improve the strength of FeCrAl-ODS alloys increases the oxidation rate, but the oxidation rate can be reduced by increasing the excessive oxygen content to the appropriate level. From thermochemical multiphase calculations, Zr activity becomes lower in the alloy matrix with increasing excessive oxygen, and preventing ZrO2 formation within the alumina scale can decelerate oxygen inward diffusion through ZrO2. Addition of Zr and excessive oxygen can also improve adhesion of the alumina scale at 1400 °C. Once the protective alumina scale is lost during oxidation at 1500 °C, FeO direct reaction with exothermic heat takes place and an oxidation reaction with partial melting rapidly proceeds within 30 min.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2019.01.041

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2019.01.041;
PII
S0022311518309498;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
516
Journal Page Range
p. 317-326
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Notes
© 2019 Elsevier B.V. All rights reserved.