Results 21 to 30 of about 324 (179)

Research progress in microstructure and service performance of high-strength and corrosion-resistant ODS−FeCrAl alloy

open access: yes工程科学学报, 2022
The demand for cleaner and more efficient new generation reactors has become increasingly urgent to solve the world’s energy supply and environmental issues such as carbon emissions. The Fukushima nuclear power plant disaster in 2011 prompted researchers
Hao-dong JIA, Zhang-jian ZHOU
doaj   +1 more source

The Formation Mechanism of a Multilayer-Structure Oxide Film during the Oxidation of FeCrAl in Air at 700 °C

open access: yesMetals, 2023
A protective oxide film is the key to the corrosion resistance of the FeCrAl alloy. The mechanism of the formation of the multilayer oxide film of the FeCrAl alloy in 700 °C air was explored by studying the structure evolution of the oxide film and the ...
Zichen Gao   +6 more
doaj   +1 more source

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

open access: yesMaterials & Design, 2022
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 been revealed. Four alloys with different Nb content (0 wt%, 0.5 wt%, 1.0 wt%
Jingjing Liao   +7 more
doaj   +1 more source

Influence of water vapour on the oxidation rate of oxide dispersion strengthened FeCrAl alloys at 1100 °C

open access: yesNuclear Materials and Energy, 2023
The high-temperature oxidation behaviour of oxide dispersion strengthened FeCrAl (ODS-FeCrAl) alloys was studied at 1100 °C in dry and wet atmospheres for use as candidate accident-tolerant fuel (ATF) cladding materials. Electron backscatter diffraction (
Qing Li   +6 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

Corrosion resistance of FeCrAl coatings on Mo–La alloys

open access: yesFenmo yejin jishu, 2023
FeCrAl coatings were deposited on the surface of Mo–La alloys by the non-equilibrium magnetron sputtering process. The corrosion resistance and corrosion mechanism of the FeCrAl coatings were investigated.
XI Sha   +5 more
doaj   +1 more source

Effect of Al mass fraction on the properties of porous FeCrAl alloys

open access: yesFenmo yejin jishu, 2022
The typical heat-resistant FeCrAl alloys have recently been developed as the high-temperature resistant porous materials which are applied widely in the fields of coal-gas purification and high-temperature catalyst carrier. The aluminum mass fraction has
GUO Fei   +4 more
doaj   +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

Crystallographic Orientation Dependence of Mechanical Responses of FeCrAl Micropillars

open access: yesCrystals, 2020
Iron-chromium-aluminum (FeCrAl) alloys are used in automobile exhaust gas purifying systems and nuclear reactors due to its superior high-temperature oxidation and excellent corrosion resistance.
Dongyue Xie   +3 more
doaj   +1 more source

The Effect of Scanning Strategies on FeCrAl Nuclear Thin-Wall Cladding Manufacturing Accuracy by Laser Powder Bed Fusion

open access: yesCrystals, 2022
FeCrAl alloy has been proposed as an alternative material for accident-tolerant fuel (ATF) cladding for nuclear reactors. Thin-wall cladding can be rapidly fabricated by laser powder bed fusion (LPBF). In this paper, a finite element model is established
Fusheng Cao   +9 more
doaj   +1 more source

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