Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
11029549 | Journal of Nuclear Materials | 2018 | 28 Pages |
Abstract
FeCrAl alloys are proposed and being intensively investigated as alternative accident tolerant fuel (ATF) cladding for nuclear fission application. Herein, the influence of major alloy elements (Cr and Al), reactive element effect and heating schedules on the oxidation behavior of FeCrAl alloys in steam up to 1500â¯Â°C was examined. In case of transient ramp tests, catastrophic oxidation, i.e. rapid and complete consumption of the alloy, occurred during temperature ramp up to above 1200â¯Â°C for specific alloys. The maximum compatible temperature of FeCrAl alloys in steam increases with raising Cr and Al content, decreasing heating rates during ramp period and doping of yttrium. Isothermal oxidation resulted in catastrophic oxidation at 1400â¯Â°C for all examined alloys. However, formation of a protective alumina scale at 1500â¯Â°C was ascertained despite partial melting. The occurrence of catastrophic oxidation seems to be controlled by dynamic competitive mechanisms between mass transfer of Al from the substrate and transport of oxidizing gas through the scale both toward the metal/oxide scale interface.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Chongchong Tang, Adrian Jianu, Martin Steinbrueck, Mirco Grosse, Alfons Weisenburger, Hans Juergen Seifert,