FeCrAl fuel/clad chemical interaction in light water reactor environments
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 …
commercial FeCrAl alloys, APMT composition (Fe-21Cr-5Al-3Mo wt.%) and C35M (Fe-13Cr …
Distinctive Oxide Films Develop on the Surface of FeCrAl as the environment changes for nuclear fuel cladding
The corrosion-resistant properties of IronChromium–Aluminum (FeCrAl) alloys have been
known for nearly a century. Since the 1950s, they have been explored for application in the …
known for nearly a century. Since the 1950s, they have been explored for application in the …
[HTML][HTML] Effect of aging and α'segregation on oxidation and electrochemical behavior of FeCrAl alloys
R Rajendran, AS Chikhalikar, I Roy… - Journal of Nuclear …, 2024 - Elsevier
FeCrAl alloys are promising candidates for next generation nuclear fuel cladding
applications due to their high resistance to hydrothermal corrosion, high temperature steam …
applications due to their high resistance to hydrothermal corrosion, high temperature steam …
Effect of molybdenum on the oxidation resistance of FeCrAl alloy in lower temperature (400° C) and higher temperature (1200° C) steam environments
Abstract The effect of 0, 1, 3 wt% Mo addition on the corrosion behavior of Fe21Cr5. 5Al was
studied through steam tests at 400° C and 1200° C. At 400° C, Mo addition leads to non …
studied through steam tests at 400° C and 1200° C. At 400° C, Mo addition leads to non …
Corrosion of FeCrAl-1Nb alloy in Deaerated Water at 290℃ and 7MPa: The Oxidation Behavior of Grain Boundary
Y Hu, Y Ling, X Zhao, W Zhang, F Zhao, W Wang… - Corrosion …, 2024 - Elsevier
An investigation into the grain boundary corrosion behavior of a FeCrAl-1Nb alloy at 290℃
and 7 MPa deaerated solution comprising lithium hydroxide and boric acid was conducted …
and 7 MPa deaerated solution comprising lithium hydroxide and boric acid was conducted …
Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments
Abstract Iron-Chromium-Aluminum (FeCrAl) alloys are candidate materials for the cladding
of light water reactor (LWR) fuels. The FeCrAl alloys in general range in Cr composition from …
of light water reactor (LWR) fuels. The FeCrAl alloys in general range in Cr composition from …
Effect of grain refinement on high temperature steam oxidation of an FeCrAl alloy
FeCrAl alloys are promising candidates to replace Zr alloys as fuel cladding materials in
nuclear light-water reactors. Grain refinement has been indicated to improve irradiation …
nuclear light-water reactors. Grain refinement has been indicated to improve irradiation …
[HTML][HTML] Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys
Given the focus on developing novel accident-tolerant materials for nuclear fuel cladding
applications, FeCrAl alloys have been considered as one of the promising candidates. To …
applications, FeCrAl alloys have been considered as one of the promising candidates. To …
Oxide Layers in Ni-doped FeCrAl Alloy in 320° C Radioactive Hydrogenated Water
Abstract Iron-chromium-aluminum (FeCrAl) alloys have been the interest of the international
nuclear energy industry as an accident tolerant fuel cladding replacement to the Zircaloy …
nuclear energy industry as an accident tolerant fuel cladding replacement to the Zircaloy …
Nickel Ferrite as a Model Corrosion Product and its Deposition on Current and Future Nuclear Fuel Cladding Materials
BS Nagothi - 2024 - scholarsarchive.library.albany.edu
The primary corrosion products in Light Water Reactors (LWRs) are nickel ferrites (nominal
stoichiometry NiFe 2 O 4) having the spinel crystal structure. These products, commonly …
stoichiometry NiFe 2 O 4) having the spinel crystal structure. These products, commonly …