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Dangosydd eitem ddigidol (DOI)

  • David Bowden
    University of Manchester
  • J. Ward
    University of Manchester
  • Simon Middleburgh
  • S. de Moraes Shubeita
    University of Manchester
  • E. Zapata-Solvas
    Grand Challenges in Ecosystem and the Environment Initiative, Imperial College London, Silwood Park Campus, Ascot, Berkshire SL5 7PY, UK alexander.papadopulos@plants.ox.ac.uk.
  • T. Lapauw
    KU Leuven
  • J. Vleugels
    KU Leuven
  • K. Lambrinou
    University of Huddersfield
  • Bill Lee
  • Michael Preuss
    University of Manchester
  • Philipp Frankel
    University of Manchester
This work is a first assessment of the radiation tolerance of the nanolayered ternary carbides (MAX phases), Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2, using proton irradiation followed by post-irradiation examination based primarily on x-ray diffraction analysis. These specific MAX phase compounds are being evaluated as candidate coating materials for fuel cladding applications in advanced nuclear reactor systems. The aim of using a MAX phase coating is to protect the substrate fuel cladding material from corrosion damage during its exposure to the primary coolant. Proton irradiation was used in this study as a surrogate for neutron irradiation in order to introduce radiation damage into these ceramics at reactor-relevant temperatures. The post-irradiation examination of these materials revealed that the Zr-based 312-MAX phases, Zr3AlC2 and (Zr0.5,Ti0.5)3AlC2 have a superior ability for defect-recovery above 400 °C, whilst the Nb4AlC3 does not demonstrate any appreciable defect recovery below 600 °C. Density functional theory calculations have demonstrated that the structural differences between the 312 and 413-MAX phase structures govern the variation of the irradiation tolerance of these materials.

Allweddeiriau

Iaith wreiddiolSaesneg
Tudalennau (o-i)24-35
CyfnodolynActa Materialia
Cyfrol183
Dyddiad ar-lein cynnar25 Hyd 2019
Dynodwyr Gwrthrych Digidol (DOIs)
StatwsCyhoeddwyd - 15 Ion 2020

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