H2 permeation behavior of cr2alc and ti2alc max phase coated zircaloy-4 by neutron radiography

Chongchong Tang, Mirco Karl Grosse, Pavel Trtik, Martin Steinbrück, Michael Stüber, Hans Jürgen Seifert

H2 permeation behavior of cr2alc and ti2alc max phase coated zircaloy-4 by neutron radiography

Číslo: 1/2018
Periodikum: Acta Polytechnica
DOI: 10.14311/AP.2018.58.0069

Klíčová slova: MAX phase coating; Zircaloy; ATF; hydrogen permeation; neutron radiography, MAX fáze; Zircaloy; ATF; propustnost vodíku; neutronová radiografie

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Anotace: 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.