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

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The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX phase-based ceramics. / Lambrinou, Konstantza; David, Bowden; Joseph, Ward; Simon, Middleburgh; S., de Moraes Shubeita; E., Zapata-Solvas; Lapauw, Thomas; Vleugels, Jozef; LEE, W.E.; Preuss, M.; Frankel, Philipp.

In: Acta Materialia, Vol. 183, 183, 07.11.2019.

Research output: Contribution to journalArticle

Harvard

Lambrinou, K, David, B, Joseph, W, Simon, M, S., DMS, E., Z-S, Lapauw, T, Vleugels, J, LEE, WE, Preuss, M & Frankel, P 2019, 'The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX phase-based ceramics' Acta Materialia, vol 183, 183. DOI: doi.org/10.1016/j.actamat.2019.10.049

APA

Lambrinou, K., David, B., Joseph, W., Simon, M., S., D. M. S., E., Z-S., ... Frankel, P. (2019). The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX phase-based ceramics. Acta Materialia, 183, [183]. DOI: doi.org/10.1016/j.actamat.2019.10.049

Vancouver

Lambrinou K, David B, Joseph W, Simon M, S. DMS, E. Z-S et al. The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX phase-based ceramics. Acta Materialia. 2019 Nov 7;183. 183. Available from, DOI: doi.org/10.1016/j.actamat.2019.10.049

Author

Lambrinou, Konstantza; David, Bowden; Joseph, Ward; Simon, Middleburgh; S., de Moraes Shubeita; E., Zapata-Solvas; Lapauw, Thomas; Vleugels, Jozef; LEE, W.E.; Preuss, M.; Frankel, Philipp / The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX phase-based ceramics.

In: Acta Materialia, Vol. 183, 183, 07.11.2019.

Research output: Contribution to journalArticle

Bibtex - Download

@article{8b42456ab3bd4e738edd052f441f0854,
title = "The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX phase-based ceramics",
keywords = "The University of Manchester, School of Materials, Ceramics, Density functional theory (DFT), x-ray diffraction (XRD), Lattice strains",
author = "Konstantza Lambrinou and Bowden David and Ward Joseph and Middleburgh Simon and S., {de Moraes Shubeita} and Zapata-Solvas E. and Thomas Lapauw and Jozef Vleugels and W.E. LEE and M. Preuss and Philipp Frankel",
note = "Score=10",
year = "2019",
month = "11",
doi = "doi.org/10.1016/j.actamat.2019.10.049",
volume = "183",
journal = "Acta Materialia",
issn = "1359-6454",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX phase-based ceramics

AU - Lambrinou,Konstantza

AU - David,Bowden

AU - Joseph,Ward

AU - Simon,Middleburgh

AU - S.,de Moraes Shubeita

AU - E.,Zapata-Solvas

AU - Lapauw,Thomas

AU - Vleugels,Jozef

AU - LEE,W.E.

AU - Preuss,M.

AU - Frankel,Philipp

N1 - Score=10

PY - 2019/11/7

Y1 - 2019/11/7

N2 - 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.

AB - 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.

KW - The University of Manchester, School of Materials

KW - Ceramics

KW - Density functional theory (DFT)

KW - x-ray diffraction (XRD)

KW - Lattice strains

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/36183698

U2 - doi.org/10.1016/j.actamat.2019.10.049

DO - doi.org/10.1016/j.actamat.2019.10.049

M3 - Article

VL - 183

JO - Acta Materialia

T2 - Acta Materialia

JF - Acta Materialia

SN - 1359-6454

M1 - 183

ER -

ID: 5743095