The M4F project brings together the fusion and fission materials communities working on the
prediction of radiation damage production and evolution and their effects on the mechanical …

Abstract The Fe–Cr–Al alloy system has the potential to form an important class of enhanced
accident-tolerant cladding materials in the nuclear power industry owing to the alloy …

After the Fukushima nuclear accident, the development of new accident-tolerant fuel
cladding materials has become a research hotspot around the world. Due to its outstanding …

FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding
applications in light water reactors owing to their superior high-temperature oxidation and …

Abstract Model FeCrAl alloys with varying compositions (Fe (10–18) Cr (10–6) Al at.%) have
been neutron irradiated at~ 320 to damage levels of~ 7 displacements per atom (dpa) to …

FeCrAl alloys are a class of alloys that have seen increased interest for nuclear power
applications including accident tolerant fuel cladding, structural components for fast fission …

Radiation-enhanced precipitation of Cr-rich α′ in irradiated Fe-Cr alloys, which results in
hardening and embrittlement, depends on the irradiating particle and the displacement per …

This paper provides an overview of advanced scanning transmission electron microscopy
(STEM) techniques used for characterization of irradiated BCC Fe-based alloys. Advanced …

A cross-correlative precession electron diffraction–atom probe tomography investigation of
Cr segregation in a Fe (Cr) nanocrystalline alloy was undertaken. Solute segregation was …

Formation of large volume fractions of Mn-Ni-Si precipitates (MNSPs) causes excess
irradiation embrittlement of reactor pressure vessel (RPV) steels at high, extended-life …