A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding
applications in light water reactors owing to their superior high-temperature oxidation and …
applications in light water reactors owing to their superior high-temperature oxidation and …
Radiation-induced Ostwald ripening in oxide dispersion strengthened ferritic steels irradiated at high ion dose
Oxide dispersion strengthened (ODS) ferritic steels are considered promising candidates as
cladding tubes for Generation IV nuclear reactors. In such reactors, irradiation damage can …
cladding tubes for Generation IV nuclear reactors. In such reactors, irradiation damage can …
Effect of tube processing methods on microstructure, mechanical properties and irradiation response of 14YWT nanostructured ferritic alloys
In this research, innovative thermal spray deposition (Process I) and conventional hot
extrusion processing (Process II) methods have been used to produce thin walled tubing (∼ …
extrusion processing (Process II) methods have been used to produce thin walled tubing (∼ …
Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa
FeCrAl alloys with varying compositions and microstructures are under consideration for
accident-tolerant fuel cladding, but limited details exist on dislocation loop formation and …
accident-tolerant fuel cladding, but limited details exist on dislocation loop formation and …
Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations
A nanostructured ferritic alloy (NFA), 14YWT, was produced in the form of thin walled tubing.
The stability of the nano-oxides (NOs) was determined under 3.5 MeV Fe+ 2 irradiations up …
The stability of the nano-oxides (NOs) was determined under 3.5 MeV Fe+ 2 irradiations up …
Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties
Nanostructured ferritic alloys (NFAs) having sub-micron grain size with a high density of
nano-oxides (NOs)(size of∼ 2–3 nm) are one of the best candidates for structural …
nano-oxides (NOs)(size of∼ 2–3 nm) are one of the best candidates for structural …
Current-driving dissolution of nanoscale brittle precipitates produced by spinodal decomposition in FeCrAl alloys
X Huang, X Zhang - Journal of Alloys and Compounds, 2019 - Elsevier
Due to its excellent resistance to high temperature oxidation and steam corrosion, FeCrAl
alloys have received much attention recently as a highly potential candidate cladding …
alloys have received much attention recently as a highly potential candidate cladding …
Deconvoluting the effect of chromium and aluminum on the radiation response of wrought FeCrAl alloys after low-dose neutron irradiation
FeCrAl alloys have been extensively investigated over the past decade as a candidate
material for accident-tolerant fuel cladding in light water reactors. This work completes a first …
material for accident-tolerant fuel cladding in light water reactors. This work completes a first …
Influence of injected ions on α'formation under ion irradiation in Oxide Dispersion Strengthened Steels
M Loyer-Prost, S Jublot-Leclerc, MJ Saleh-Afif, J Ribis… - Scripta Materialia, 2025 - Elsevier
Abstract Oxide Dispersion Strengthened (ODS) steels hold great promise for applications in
next generation reactors. Under irradiation, a phase separation α/α'can occur within the Fe …
next generation reactors. Under irradiation, a phase separation α/α'can occur within the Fe …
Nano-cluster stability following neutron irradiation in MA957 oxide dispersion strengthened material
J Ribis, S Lozano-Perez - Journal of Nuclear Materials, 2014 - Elsevier
ODS steels are promising materials for Sodium cooled Fast Reactors since their fine
distribution of nano-clusters confers excellent mechanical properties. However, the nano …
distribution of nano-clusters confers excellent mechanical properties. However, the nano …