Article

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

D. BowdenThe University of Manchester, School of Materials, Oxford Road, Manchester M13 9PL, United KingdomJ. WardRolls-Royce plc, Derby, Derbyshire DE24 8BJ, United KingdomSimon C. MiddleburghNuclear Futures: Materials, Bangor University, Bangor, Gwynedd LL57 2DG, United KingdomSamir de Moraes ShubeitaThe University of Manchester, Dalton Cumbrian Facility, Moor Row, CA24 3HA, United KingdomEugenio Zapata‐SolvasCentre for Nuclear Engineering (CNE) & Department of Materials, Imperial College London, London, United KingdomThomas LapauwKU Leuven, Department of Materials Engineering, Kasteelpark Arenberg 44, Leuven 3001, BelgiumJef VleugelsKU Leuven, Department of Materials Engineering, Kasteelpark Arenberg 44, Leuven 3001, BelgiumKonstantina LambrinouSCK CEN, Boeretang 200, Mol 2400, BelgiumWilliam LeeCentre for Nuclear Engineering (CNE) & Department of Materials, Imperial College London, London, United KingdomMichael PreußThe University of Manchester, School of Materials, Oxford Road, Manchester M13 9PL, United KingdomPhilipp FrankelThe University of Manchester, School of Materials, Oxford Road, Manchester M13 9PL, United Kingdom

2019en

ABI

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.

Identifiers

DOI: 10.1016/j.actamat.2019.10.049

Citations and references

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