Results 21 to 30 of about 288 (181)

A comparative study on the corrosion performance of four FeCrAl alloys with different Cr contents in contact with oxygen-saturated LBE

open access: yesJournal of Materials Research and Technology, 2023
The corrosion behavior of a series of FeCrAl alloys with four Cr contents was investigated in static oxygen-saturated liquid lead–bismuth eutectic (LBE) at 600 °C for 720 h.
Hui Wang   +5 more
doaj   +1 more source

Hafnium influence on the microstructure of FeCrAl alloys

open access: yesIOP Conference Series: Materials Science and Engineering, 2016
Due to their special properties at high temperatures, FeCrAl alloys micro-alloyed with Zr can be regarded as potential materials for use at nuclear power plants, generation 4R. These materials are resistant to oxidation at high temperatures, to corrosion, erosion and to the penetrating radiations in liquid metal environments.
V Geanta, I Voiculescu, E-M Stanciu
openaire   +1 more source

Understanding Impacts of Chemistry on Oxidation of FeCrAl Alloys

open access: yes, 2022
Abstract Traditionally, FeCrAl alloys played an important role in high-temperature applications due to their ability to form a passive Al oxide film at temperatures above ~800°C. Recently, FeCrAl alloys became of interest for the application of accident tolerant nuclear fuel cladding.
Indranil Roy   +10 more
openaire   +1 more source

Positron annihilation investigation of hardening behavior induced by Fe2+ irradiation in low-Cr FeCrAl alloys

open access: yesJournal of Materials Research and Technology, 2023
Compared with 13Cr–FeCrAl alloy, micro-alloyed low-Cr FeCrAl alloy is expected to provide higher potential for application as accident-tolerant fuel (ATF) cladding material.
Mingyou Niu, Hui Wang, Xuefei Huang
doaj   +1 more source

Effect of Rolling Deformation on Creep Properties of FeCrAl Alloys [PDF]

open access: yesFrontiers in Energy Research, 2021
FeCrAl alloy is one of the most promising nuclear fuel claddings among many accident tolerant fuel (ATF) materials due to its excellent oxidation resistance and good mechanical properties. However, the effect of process conditions on the creep properties of the FeCrAl alloy is not clear till now.
Huan Sheng Lai   +6 more
openaire   +2 more sources

Effect of High-Density Nanoparticles on Recrystallization and Texture Evolution in Ferritic Alloys

open access: yesCrystals, 2019
Ferritic alloys are important for nuclear reactor applications due to their microstructural stability, corrosion resistance, and favorable mechanical properties.
Eda Aydogan   +5 more
doaj   +1 more source

Development of nano-oxide particles dispersed alumina scale formed on Zr-added FeCrAl ODS ferritic alloys

open access: yesNuclear Materials and Energy, 2020
In order to develop a robust alumina scale dispersed with nano-oxide particles for FeCrAl oxide dispersion strengthened (ODS) ferritic alloys, the oxidation behavior of FeCrAl ODS ferritic alloys with zirconium and excessive oxygen (Ex.
Hao Yu   +5 more
doaj   +1 more source

Cyclic Corrosion and Chlorination of an FeCrAl Alloy in the Presence of KCl [PDF]

open access: yesOxidation of Metals, 2015
The KCl-induced corrosion of the FeCrAl alloy Kanthal® APMT in an O2 + N2 + H2O environment was studied at 600 °C. The samples were pre-oxidized prior to exposure in order to investigate the protective nature of alumina scales in the present environment. The microstructure and composition of the corroded surface was investigated in detail.
Israelsson, N.   +4 more
openaire   +1 more source

Hydrogen Atom and Molecule Adsorptions on FeCrAl (100) Surface: A First-Principle Study

open access: yesFrontiers in Energy Research, 2021
FeCrAl alloys are promising accident-tolerant fuel (ATF) cladding materials for applications in light water reactors (LWRs). Despite the excellent mechanical and antioxidation properties, this series of iron-based alloys has poor hydrogen embrittlement ...
Xiaojing Li   +3 more
doaj   +1 more source

Hydrogen permeation in FeCrAl alloys for LWR cladding application [PDF]

open access: yesJournal of Nuclear Materials, 2015
Abstract FeCrAl, an advanced oxidation-resistant iron-based alloy class, is a highly prevalent candidate as an accident-tolerant fuel cladding material. Compared with traditional zirconium alloy fuel cladding, increased tritium permeation through FeCrAl fuel cladding to the primary coolant is expected, raising potential safety concerns. In this study,
Hu, Xunxiang   +3 more
openaire   +1 more source

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