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H₂ permeation behavior of Cr₂AlC and Ti₂AlC max phase coated zircaloy-4 by neutron radiography

Tang, Chongchong; Grosse, Mirco; Trtik, Pavel; Steinbrueck, Martin; Stueber, Michael; Seifert, Hans Jürgen

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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Verlagsausgabe §
DOI: 10.5445/IR/1000081205
Veröffentlicht am 19.03.2018
DOI: 10.14311/AP.2018.58.0069
Zitationen: 2
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien - Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2018
Sprache Englisch
Identifikator ISSN: 1210-2709
KITopen-ID: 1000081205
HGF-Programm 34.13.01 (POF III, LK 01) Material f.therm.,mechan.u.Umweltbelast.
Erschienen in Acta polytechnica
Verlag CTU Central Library
Band 58
Heft 1
Seiten 69-76
Schlagwörter MAX phase coating, Zircaloy, ATF, hydrogen permeation, neutron radiography
Nachgewiesen in Scopus
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