Al–Cr–O thin films as an efficient hydrogen barrier

Levchuk, D.; Bolt, H.; Döbeli, M.; Eggenberger, Simon; Widrig, Beno; Ramm, J.

doi:10.1016/j.surfcoat.2008.05.012

Cited by 56 publications

(19 citation statements)

References 21 publications

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“…In general, the oxidation of Cr 2 AlC coatings result in the formation of an alumina-rich scale at relatively low temperature or a dense continuous oxide scale consisting of alumina on Cr carbides at high temperature [20,21]. Alumina, particularly the α-phase of aluminium oxide (corundum) and chromia are robust hydrogen permeation barriers that can reduce the permeation rate by three orders of magnitude in laboratory experiments [22,23]. Thus, it can be expected that both pre-oxidized MAX phase coatings can serve as satisfactory barriers for limiting hydrogen isotope permeation.…”

Section: No / H 2 Permeation Behavior Of Coated Zircaloy-4 By Neutromentioning

confidence: 99%

H2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHY

et al. 2018

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Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during design basis and severe accidents beyond design basis has a high safety relevance because hydrogen degrade the mechanical properties of the zirconium alloys applied as cladding material. Currently, claddings with enhanced accident tolerance are under development. One group of such accident tolerant fuel (ATF) claddings are zirconium alloys with surface coatings reducing corrosion and high-temperature oxidation rate, as well as the chemical heat and hydrogen release during hypothetical accidents. The hydrogen permeation through the coating is an important parameter ensuring material safety. In this work, the hydrogen permeation of Ti2AlC and Cr2AlC MAX phase coatings on Zircaloy-4 is investigated by means of neutron radiography. Both coatings are robust hydrogen diffusion barriers that effectively suppress hydrogen permeation into the matrix.

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Section: No / H 2 Permeation Behavior Of Coated Zircaloy-4 By Neutromentioning

confidence: 99%

H2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHY

et al. 2018

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“…A thin alumina layer (Figs. 4 and 9) in the ID of the cladding will significantly reduce the hydrogen permeation from the fuel to the coolant [25]. It has been shown that not only alumina would reduce permeation of tritium from the fuel to the coolant, other oxides will also reduce hydrogen or tritium permeation [26,27].…”

Section: Mitigation Measures To Neutron Absorption and Tritium Releasementioning

confidence: 99%

Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants

Rebak

2017

EPJ Nuclear Sci. Technol.

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Abstract. After a tsunami caused plant black out at Fukushima, followed by hydrogen explosions, the US Department of Energy partnered with fuel vendors to study safer alternatives to the current UO 2 -zirconium alloy system. This accident tolerant fuel alternative should better tolerate loss of cooling in the core for a considerably longer time while maintaining or improving the fuel performance during normal operation conditions. General electric, Oak ridge national laboratory, and their partners are proposing to replace zirconium alloy cladding in current commercial light water power reactors with an iron-chromium-aluminum (FeCrAl) cladding such as APMT or C26M. Extensive testing and evaluation is being conducted to determine the suitability of FeCrAl under normal operation conditions and under severe accident conditions. Results show that FeCrAl has excellent corrosion resistance under normal operation conditions and FeCrAl is several orders of magnitude more resistant than zirconium alloys to degradation by superheated steam under accident conditions, generating less heat of oxidation and lower amount of combustible hydrogen gas. Higher neutron absorption and tritium release effects can be minimized by design changes. The implementation of FeCrAl cladding is a near term solution to enhance the safety of the current fleet of commercial light water power reactors.

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“…Alumina thin films and coatings have been in industrial use for a long time [5,6]. Recent research focuses on physical vapor deposition (PVD) synthesis and development of advanced solid solution oxide thin films such as (Al,Cr) 2 O 3 and related nitrogen containing materials [3,[7][8][9][10][11][12][13][14][15][16][17]. To realize such materials, an important fact is utilized: both α-Al 2 O 3 (corundum) and Cr 2 O 3 are isostructural and offer a solid solubility over a wide range of compositions of the quasi-binary phase diagram at high temperatures [18].…”

Section: Introductionmentioning

confidence: 99%

Microstructure and hardness of reactively r.f. magnetron sputtered Cr-V-O thin films in dependence on composition and substrate bias

Spitz

Stüber

Leiste

et al. 2014

Surface and Coatings Technology

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Al–Cr–O thin films as an efficient hydrogen barrier

Cited by 56 publications

References 21 publications

H2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHY

H2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHY

Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants

Microstructure and hardness of reactively r.f. magnetron sputtered Cr-V-O thin films in dependence on composition and substrate bias

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