Deep learning object detection in materials science: Current state and future directions

R Jacobs - Computational Materials Science, 2022 - Elsevier
Deep learning-based object detection models have recently found widespread use in
materials science, with rapid progress made in just the past two years. Scanning and …

Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors

G Jiang, D Xu, P Feng, S Guo, J Yang, Y Li - Journal of Alloys and …, 2021 - Elsevier
The safety of nuclear power plants has put forward new requirements for the corrosion
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …

Automated defect analysis in electron microscopic images

W Li, KG Field, D Morgan - npj Computational Materials, 2018 - nature.com
Electron microscopy and defect analysis are a cornerstone of materials science, as they offer
detailed insights on the microstructure and performance of a wide range of materials and …

Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys

JC Haley, SA Briggs, PD Edmondson, K Sridharan… - Acta Materialia, 2017 - Elsevier
Abstract 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 …

[HTML][HTML] Additive manufacturing of FeCrAl alloys for nuclear applications-A focused review

S Palaniappan, SS Joshi, S Sharma… - Nuclear Materials and …, 2024 - Elsevier
FeCrAl alloys exhibit outstanding high-temperature oxidation resistance and impressive
mechanical strength, rendering them as forefront materials with broad applicability across …

High-temperature creep deformation in FeCrAl-oxide dispersion strengthened alloy cladding

S Ukai, S Kato, T Furukawa, S Ohtsuka - Materials Science and …, 2020 - Elsevier
The FeCrAl-oxide dispersion strengthened (ODS) alloy is the promising cladding material for
the accident-tolerant fuel (ATF) of the light water reactors (LWR) to suppress the oxidation …

An in situ study on the effect of grain boundaries on helium bubble formation in dual beam irradiated FeCrAl alloy

T Sun, T Niu, Z Shang, WY Chen, M Li, H Wang… - Acta Materialia, 2023 - Elsevier
FeCrAl alloy is one of the promising cladding materials in the advanced nuclear reactors.
Here we compare the irradiation response of the nanolaminate (NL) and coarse-grained …

[PDF][PDF] Handbook on the material properties of FeCrAl alloys for nuclear power production applications

KG Field, MA Snead, Y Yamamoto… - Nuclear Technology …, 2017 - academia.edu
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 …

Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures

KS Mao, CP Massey, Y Yamamoto, KA Unocic… - Acta Materialia, 2022 - Elsevier
Post–neutron irradiation examination is performed on advanced accident-tolerant fuel (ATF)
cladding iron-chromium-aluminum (FeCrAl) alloys with∼ 10–13at.% Cr,∼ 10–12 at.% Al,∼ …

Microstructural control of FeCrAl alloys using Mo and Nb additions

Z Sun, H Bei, Y Yamamoto - Materials Characterization, 2017 - Elsevier
The effects of Mo and Nb additions on the microstructure and mechanical properties of two
FeCrAl alloys were studied. Fine and uniform recrystallized grain structures (~ 20–30 μm) …