The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX phase-based ceramics

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  • Konstantza Lambrinou
  • Bowden David
  • Ward Joseph
  • Middleburgh Simon
  • de Moraes Shubeita S.
  • Zapata-Solvas E.
  • Thomas Lapauw
  • Jozef Vleugels
  • W.E. LEE
  • M. Preuss
  • Philipp Frankel
  • UNIMAN - The University of Manchester
  • Bangor University
  • DCF - University of Manchester - Dalton Nuclear Institute
  • Imperial College London
  • KUL - Katholieke Universiteit Leuven

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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.


Original languageEnglish
Article number183
Number of pages12
JournalActa Materialia
Publication statusPublished - 7 Nov 2019


  • The University of Manchester, School of Materials, Ceramics, Density functional theory (DFT), x-ray diffraction (XRD), Lattice strains

ID: 5743095