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 …

Effect of Au-ions irradiation on mechanical and LBE corrosion properties of amorphous AlCrFeMoTi HEA coating: enhanced or deteriorated?

J Yang, F Zhang, Q Chen, W Zhang, C Zhu, J Deng… - Corrosion …, 2021 - Elsevier
The effect of Au-ions irradiation with different damage doses from 10 to 90 dpa on
mechanical properties and LBE corrosion behavior of AlCrFeMoTi HEA coating was …

FeCrAl fuel/clad chemical interaction in light water reactor environments

HJ Qu, M Higgins, H Abouelella, F Cappia… - Journal of Nuclear …, 2023 - Elsevier
This article investigates the fuel-cladding chemical interaction (FCCI) behavior of two
commercial FeCrAl alloys, APMT composition (Fe-21Cr-5Al-3Mo wt.%) and C35M (Fe-13Cr …

Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors

L Yin, TB Jurewicz, M Larsen, M Drobnjak… - Journal of Nuclear …, 2021 - Elsevier
Abstract Iron-Chromium-Aluminum (FeCrAl) alloys are candidate materials for light water
reactor accident tolerant fuel (ATF) rod cladding because of the unparalleled resistance of …

Effect of nickel on the oxidation behavior of FeCrAl alloy in simulated PWR and BWR conditions

HJ Qu, H Abouelella, AS Chikhalikar, R Rajendran… - Corrosion …, 2023 - Elsevier
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 …

Study on high temperature creep behavior of the accident-resistant cladding Fe–13Cr–4Al-1.85 Mo-0.85 Nb alloy

H Sun, H Wang, X He, F Wang, X An, Z Wang - Materials Science and …, 2021 - Elsevier
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 …

Effect of Au-ion irradiation on the morphology, microstructure and lead-bismuth eutectic corrosion behavior of refractory TiNbZrMoV high-entropy alloy coating

J Deng, W Zhang, X Qiu, Q Li, Q Chen, J Yang… - Journal of Nuclear …, 2023 - Elsevier
The effect of Au-ion irradiation on the morphology, microstructure and lead-bismuth eutectic
(LBE) corrosion behavior of refractory TiNbZrMoV high-entropy alloy coating was …

Deuterium permeation behavior in a FeCrAl-based alloy containing Mo, Nb and Ta elements for LWR cladding application

Y Liu, B Luo, H Huang, W Wang, W Li, Z Duan… - Journal of Nuclear …, 2022 - Elsevier
The deuterium permeation behavior of a FeCrAl-based alloy containing Mo, Nb and Ta
elements was investigated by gas-phase deuterium permeation testing, transmission …

[HTML][HTML] Addition of niobium in Fe-13Cr-4.5 Al-2Mo alloy used as ATF cladding: Effect on high temperature water corrosion and in-situ electrochemistry

J Liao, H Wang, J Wu, W Zhang, F Xu, H Sun, X An… - Materials & Design, 2022 - Elsevier
Niobium addition in candidate accident tolerant fuel (ATF) cladding FeCrAl alloy has
received much attention, but its effect on high temperature water corrosion behavior has not …

Early-stage corrosion behavior of Al-based Gd2O3–W shielding composites in a simulated spent fuel wet storage environment

S Cong, G Ran, Y Li, SG Dong, X Huang - Progress in Nuclear Energy, 2021 - Elsevier
The early-stage corrosion behavior of the newly fabricated Al-based Gd 2 O 3–W
composites was investigated in the boron-lithium water at 40° C to simulate the environment …