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

Authors

  • Chongchong Tang Karlsruhe Institute Of Technology
  • Mirco Karl Grosse Karlsruhe Institute of Technology http://orcid.org/0000-0001-7481-3184
  • Pavel Trtik Paul Scherrer Institut Villigen
  • Martin Steinbrück Karlsruhe Institute Of Technology
  • Michael Stüber Karlsruhe Institute Of Technology
  • Hans Jürgen Seifert Karlsruhe Institute Of Technology

DOI:

https://doi.org/10.14311/AP.2018.58.0069

Keywords:

MAX phase coating, Zircaloy, ATF, hydrogen permeation, neutron radiography

Abstract

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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Published

2018-02-28

Issue

Vol. 58 No. 1 (2018)

Section

Articles

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How to Cite

Tang, C., Grosse, M. K., Trtik, P., Steinbrück, M., Stüber, M., & Seifert, H. J. (2018). H2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHY. Acta Polytechnica, 58(1), 69-76. https://doi.org/10.14311/AP.2018.58.0069