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 …
reactor accident tolerant fuel (ATF) rod cladding because of the unparalleled resistance of …
Roles of major alloying elements in steels and alloys on corrosion under biomass hydrothermal liquefaction (HTL) conversion
M Liu, Y Zeng, JL Luo - Corrosion Science, 2023 - Elsevier
Hydrothermal liquefaction (HTL) is a promising thermochemical technology to convert wet
biomass and biowaste streams into bioenergy products. Significant knowledge gaps exist …
biomass and biowaste streams into bioenergy products. Significant knowledge gaps exist …
Corrosion of Zircaloy-4, Zr-1Nb and FeCrAl alloys in deaerated water at 330 C and 14 MPa: Superior corrosion resistance and corrosion mechanism of FeCrAl alloy by …
After the Fukushima explosion, the research and development of accident tolerant fuel (ATF)
cladding has become a hot spot in the nuclear field. In this work, corrosion behavior of …
cladding has become a hot spot in the nuclear field. In this work, corrosion behavior of …
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 …
Effect of cryogenic laser surface modification on the microstructure evolution and corrosion resistance of accident-tolerant FeCrAl alloys
Y Hu, Y Ling, H Zhong, F Zhao, H Wang… - Surface and Coatings …, 2023 - Elsevier
Accident-tolerant FeCrAl alloys require a thinner cladding wall than zirconium cladding to
overcome the extra neutron loss, thus requiring enhanced corrosion resistance. Surface …
overcome the extra neutron loss, thus requiring enhanced corrosion resistance. Surface …
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 …
[HTML][HTML] Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment
Z Qu, C Meng, J Huang, Y Mei, Y Zhang, J Ma, W Liu… - Materials & Design, 2023 - Elsevier
This study systematically investigated the incipient corrosion behavior of Fe-13Cr-4.5 Al
(wt%) and lean-Cr (7–10 wt%) with 5Al (wt%) FeCrAl alloy with a timescale of 4 months …
(wt%) and lean-Cr (7–10 wt%) with 5Al (wt%) FeCrAl alloy with a timescale of 4 months …
Influence of major operating parameters (temperature, pressure, and flow rate) on the corrosion of candidate alloys for the construction of hydrothermal liquefaction …
M Liu, Y Zeng, JL Luo - Energy & Fuels, 2022 - ACS Publications
Hydrothermal liquefaction (HTL) is a promising thermochemical technology to convert wet
biomass and biowastes into marketable bio-oils and biochemicals in an environmentally …
biomass and biowastes into marketable bio-oils and biochemicals in an environmentally …
Incipient corrosion of FeCrAl alloys in H3BO3-and LiOH-containing pure water at 360° C and 18.5 MPa
G Jiang, D Xu, W Yang, L Liu, S Guo, S Wang - Journal of Nuclear Materials, 2021 - Elsevier
The demand of accident tolerant fuel cladding materials provides a momentum for the
development of FeCrAl alloys. To prove its potential, this work studied the corrosion …
development of FeCrAl alloys. To prove its potential, this work studied the corrosion …
[HTML][HTML] In-situ TEM study of loop evolution in FeCrAl alloy under Fe+ irradiation: Effects of temperatures, dislocations and precipitates
K Pei, G Ran, Y Li, Z Cao, D Cui, R Zhang, G Yang - Nuclear Analysis, 2022 - Elsevier
Abstract Fe13. 5Cr4. 7Al alloy was irradiated in-situ with 400 keV Fe+ in TEM at RT and 748
K. The evolution of dislocation loops under the influence of temperatures, irradiation dose …
K. The evolution of dislocation loops under the influence of temperatures, irradiation dose …