Machine learning in nuclear materials research
Nuclear materials are often demanded to function for extended time in extreme
environments, including high radiation fluxes with associated transmutations, high …
environments, including high radiation fluxes with associated transmutations, high …
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 …
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,∼ …
Structure of surface oxides on martensitic steel under simultaneous ion irradiation and molten LBE corrosion
C Yao, H Zhang, H Chang, T Shen, Y Zhu, L Pang… - Corrosion …, 2022 - Elsevier
Irradiation damage on corrosion process of steels in Pb or LBE melts is a main challenge for
the R&D of LFR. In this paper, A martensitic steel (SIMP) was in-situ irradiated with 247 MeV …
the R&D of LFR. In this paper, A martensitic steel (SIMP) was in-situ irradiated with 247 MeV …
Effect of molybdenum addition on oxidation behavior and secondary protection mechanism of FeCrAl coatings
R Zhou, F Wang, K Xu, Y Yuan, L Chen, M Lou… - Materials …, 2023 - Elsevier
FeCrAl alloy coatings are widely used for their excellent oxidation resistance at high
temperatures, but they can suffer from rapid material degradation due to breakaway …
temperatures, but they can suffer from rapid material degradation due to breakaway …
[HTML][HTML] Effect of Au-ions irradiation on microstructure and mechanical properties of FeCrAl coating
W Zhang, J Deng, H Yin, Y Zhao, X Qiu, M Zhou… - Journal of Materials …, 2023 - Elsevier
Six kinds of FeCrAl coatings with different Cr and Al contents were irradiated by 6 MeV Au-
ions with a damage level of 20 dpa. The results showed that the surface roughness and …
ions with a damage level of 20 dpa. The results showed that the surface roughness and …
Study on high temperature creep behavior of the accident-resistant cladding Fe–13Cr–4Al-1.85 Mo-0.85 Nb alloy
Abstract The Fe–13Cr–4Al-1.85 Mo-0.85 Nb alloy, as accident-resistant fuel cladding
material in light water reactor (LWR), was prepared by a vacuum induction melting, forging …
material in light water reactor (LWR), was prepared by a vacuum induction melting, forging …
[HTML][HTML] Effect of nickel on the oxidation behavior of FeCrAl alloy in simulated PWR and BWR conditions
FeCrAl alloys are being investigated as candidate materials for light water reactor fuel
claddings. The chemical composition of FeCrAl determines its resistance to corrosion under …
claddings. The chemical composition of FeCrAl determines its resistance to corrosion under …
Irradiation accelerated corrosion of alumina-forming austenitic steels in supercritical CO2: The oxide scale formed within an individual grain or affected by grain …
The irradiation accelerated corrosion within monolayer grains of a new AFA steel exposed to
sCO 2 are studied. The presence of irradiation induced dislocation loops accelerate element …
sCO 2 are studied. The presence of irradiation induced dislocation loops accelerate element …
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 …