Bimetallic transition joints using aluminum alloy 6061-T6 and stainless steel 304 L are useful in providing reliable stainless steel welds on nuclear components at temperatures below 200 °C, while maintaining the attractive radiation tolerance of the …
Microstructures of T91 neutron irradiated in the BOR60 reactor at five temperatures between 376 °C and 524 °C to doses between 15.4 and 35.1 dpa were characterized using transmission electron microscopy (TEM), scanning transmission electron …
Alkrothal 720 and Kanthal APMT™, two commercial FeCrAl alloys, were neutron irradiated up to damage doses of 7.0 displacements per atom (dpa) in the temperature range of 320 to 382 °C to characterize the $\alpha$′ precipitation in these alloys using …
Kanthal APMT is a promising FeCrAl-based alloy for accident-tolerant fuel cladding because of its excellent high-temperature oxidation resistance. In this study, powder metallurgy Kanthal APMT alloy, neutron irradiated to 1.8 dpa at nominally 382 °C, …
FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding applications in light water reactors owing to their superior high-temperature oxidation and corrosion resistance compared to the Zr-based alloys currently employed. …
Iron-chromium-aluminum (FeCrAl) alloys are promising as corrosion- and oxidation-resistant materials for high-temperature applications. However, further design and improvement of FeCrAl-based materials require a delicate balance between workability, …
Model FeCrAl alloys of Fe-10\%Cr-5\%Al, Fe-12\%Cr-4.5\%Al, Fe-15\%Cr-4\%Al, and Fe-18\%Cr-3\%Al (in wt \%) were irradiated with 1 MeV Kr++ ions in-situ with transmission electron microscopy to a dose of 2.5 displacements per atom (dpa) at 320 °C. In …