• Shubeita, Samir De Moraes
• Preuss, M.
• Bowden, David
• Bowden, D.
• Lambrinou, K.
• Shubeita, S. De Moraes
• Frankel, Philipp
• Middleburgh, S.
• Zapata-Solvas, E.
• Lee, W. E.
• Frankel, P.
• Ward, J.
• Vleugels, J.
• Vleugels, Jozef
• Lapauw, T.
• Middleburgh, S. C.

Abstract

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.

Topics

• density
• impedance spectroscopy
• compound
• corrosion
• phase
• x-ray diffraction
• theory
• carbide
• defect
• density functional theory
• ceramic