Open AccessH2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHY
Author(s) -
Chongchong Tang,
Pavel Trtik,
M. Steinbrück,
Michael Stüber,
Hans Jürgen Seifert
Publication year - 2018
Publication title -
acta polytechnica
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.207
H-Index - 15
eISSN - 1805-2363
pISSN - 1210-2709
DOI - 10.14311/ap.2018.58.0069
Subject(s) - zirconium alloy , hydrogen , materials science , cladding (metalworking) , permeation , coating , zirconium , neutron imaging , coolant , corrosion , forensic engineering , composite material , metallurgy , nuclear engineering , neutron , chemistry , nuclear physics , organic chemistry , biochemistry , physics , membrane , engineering
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.