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 …
[HTML][HTML] Modelling FeCrAl cladding thermo-mechanical performance. Part II: Comparative analysis with Zircaloy under LOCA conditions
P Aragón, F Feria, LE Herranz - Progress in Nuclear Energy, 2023 - Elsevier
The demonstration of the enhanced thermo-mechanical response of iron-chromium-
aluminum (FeCrAl) cladding under any circumstances, particularly under postulated …
aluminum (FeCrAl) cladding under any circumstances, particularly under postulated …
Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4
Accident-tolerant fuel (ATF) cladding materials aim to improve fuel reliability and safety
during accident scenarios in water-cooled reactors. These ATF cladding should also perform …
during accident scenarios in water-cooled reactors. These ATF cladding should also perform …
Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500 C in steam
The oxidation mechanism and kinetics of two nuclear-grade FeCrAl alloys were investigated
in steam up to 1500° C by transient and isothermal oxidation tests. The slow α-alumina …
in steam up to 1500° C by transient and isothermal oxidation tests. The slow α-alumina …
[图书][B] Accident-tolerant materials for light water reactor fuels
RB Rebak - 2020 - books.google.com
Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an
accident tolerant fuel is and the benefits and detriments of each concept. The book begins …
accident tolerant fuel is and the benefits and detriments of each concept. The book begins …
Oxidation behavior and microstructure evolution of alumina-forming austenitic & high entropy alloys in steam environment at 1200° C
H Shi, C Tang, A Jianu, R Fetzer, A Weisenburger… - Corrosion …, 2020 - Elsevier
Oxidation tests of alumina-forming austenitic (AFA) alloys and high entropy alloys (HEA)
have been performed in steam at 1200° C. AFA alloys with composition formula Fe-3Al-16Cr …
have been performed in steam at 1200° C. AFA alloys with composition formula Fe-3Al-16Cr …
A study of the oxidation behaviour of FeCrAl-ODS in air and steam environments up to 1400° C
K Lipkina, D Hallatt, E Geiger, BWN Fitzpatrick… - Journal of Nuclear …, 2020 - Elsevier
As a candidate accident tolerant fuel cladding material, the high temperature oxidation
behaviour of an Oxygen Dispersion Strengthened (ODS) Fe–12Cr–6Al alloy has been …
behaviour of an Oxygen Dispersion Strengthened (ODS) Fe–12Cr–6Al alloy has been …
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 …
Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1)
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 …
applications including accident tolerant fuel cladding, structural components for fast fission …
Oxidation characteristics of Fe22Cr5Al3Mo-xNb alloys in high temperature steam
The oxidation behaviors of Fe22Cr5Al3Mo-xNb (x= 0.5, 1.0, 2.0 wt%) alloys under simulated
loss of coolant accident (LOCA) conditions at 1000 and 1200℃ were investigated. The …
loss of coolant accident (LOCA) conditions at 1000 and 1200℃ were investigated. The …