Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors
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 …
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …
Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan
K Sakamoto, Y Miura, S Ukai, NH Oono… - Journal of Nuclear …, 2021 - Elsevier
The FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the
accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently …
accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently …
The evolution of dislocation loop and its interaction with pre-existing dislocation in He+-irradiated molybdenum: in-situ TEM observation and molecular dynamics …
Y Li, G Ran, Y Guo, Z Sun, X Liu, Y Li, X Qiu, Y **n - Acta Materialia, 2020 - Elsevier
In-situ TEM observation and molecular dynamics simulation were used to investigate the
evolution of irradiation-induced dislocation loops and their interactions with the pre-existing …
evolution of irradiation-induced dislocation loops and their interactions with the pre-existing …
In-situ TEM observation of the evolution of dislocation loops and helium bubbles in a pre helium irradiated FeCrAl alloy during annealing
Y Chen, Y Li, G Ran, L Wu, C Ye, Q Han… - Progress in Nuclear …, 2020 - Elsevier
FeCrAl alloys are regarded as excellent potential candidates of fuel claddings in nuclear
reactors. To further understand the evolution of helium bubbles and dislocation loops during …
reactors. To further understand the evolution of helium bubbles and dislocation loops during …
An in situ study on the effect of grain boundaries on helium bubble formation in dual beam irradiated FeCrAl alloy
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 …
Here we compare the irradiation response of the nanolaminate (NL) and coarse-grained …
Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures
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,∼ …
cladding iron-chromium-aluminum (FeCrAl) alloys with∼ 10–13at.% Cr,∼ 10–12 at.% Al,∼ …
Performance and limitations of deep learning semantic segmentation of multiple defects in transmission electron micrographs
Transmission electron microscopy (TEM) is a popular method for characterizing and
quantifying defects in materials. Analyzing digitized TEM images is typically done manually …
quantifying defects in materials. Analyzing digitized TEM images is typically done manually …
Corrosion behavior of Nb-doped FeCrAl alloy in 500° C steam
The corrosion behavior of Fe-13Cr-4Al-2.2 Mo, a candidate cladding material for accident
tolerant fuel, doped with varying concentrations of Nb (0, 0.5, 1.0, and 1.5 wt%), was …
tolerant fuel, doped with varying concentrations of Nb (0, 0.5, 1.0, and 1.5 wt%), was …
In situ micro-pillar compression to examine radiation-induced hardening mechanisms of FeCrAl alloys
Abstract The effects of 5 MeV Fe 2+ ion irradiation at 300° C on the microstructure evolution
and deformation behavior of a FeCrAl C26M alloy are presented. It has been found that …
and deformation behavior of a FeCrAl C26M alloy are presented. It has been found that …
Systematic study of radiation-induced segregation in neutron-irradiated FeCrAl alloys
This work systematically reports grain boundary radiation-induced segregation (RIS), and
insights into RIS mechanisms, in FeCrAl alloys. Recently, FeCrAl alloys have received …
insights into RIS mechanisms, in FeCrAl alloys. Recently, FeCrAl alloys have received …