Crystallographic evolution of MAX phases in proton irradiating environments

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Crystallographic evolution of MAX phases in proton irradiating environments. / Ward, Joseph; Middleburgh, Simon; Topping, Matthew et al.
Yn: Journal of Nuclear Materials, Cyfrol 502, 15.04.2018, t. 220-227.

Allbwn ymchwil: Cyfraniad at gyfnodolynErthygladolygiad gan gymheiriaid

HarvardHarvard

Ward, J, Middleburgh, S, Topping, M, Garner, A, Stewart, D, Barsoum, MW, Preuss, M & Frankel, P 2018, 'Crystallographic evolution of MAX phases in proton irradiating environments', Journal of Nuclear Materials, cyfrol. 502, tt. 220-227. https://doi.org/10.1016/j.jnucmat.2018.02.008

APA

Ward, J., Middleburgh, S., Topping, M., Garner, A., Stewart, D., Barsoum, M. W., Preuss, M., & Frankel, P. (2018). Crystallographic evolution of MAX phases in proton irradiating environments. Journal of Nuclear Materials, 502, 220-227. https://doi.org/10.1016/j.jnucmat.2018.02.008

CBE

Ward J, Middleburgh S, Topping M, Garner A, Stewart D, Barsoum MW, Preuss M, Frankel P. 2018. Crystallographic evolution of MAX phases in proton irradiating environments. Journal of Nuclear Materials. 502:220-227. https://doi.org/10.1016/j.jnucmat.2018.02.008

MLA

VancouverVancouver

Ward J, Middleburgh S, Topping M, Garner A, Stewart D, Barsoum MW et al. Crystallographic evolution of MAX phases in proton irradiating environments. Journal of Nuclear Materials. 2018 Ebr 15;502:220-227. Epub 2018 Chw 8. doi: 10.1016/j.jnucmat.2018.02.008

Author

Ward, Joseph ; Middleburgh, Simon ; Topping, Matthew et al. / Crystallographic evolution of MAX phases in proton irradiating environments. Yn: Journal of Nuclear Materials. 2018 ; Cyfrol 502. tt. 220-227.

RIS

TY - JOUR

T1 - Crystallographic evolution of MAX phases in proton irradiating environments

AU - Ward, Joseph

AU - Middleburgh, Simon

AU - Topping, Matthew

AU - Garner, Alistair

AU - Stewart, David

AU - Barsoum, Michel W.

AU - Preuss, Michael

AU - Frankel, Philipp

PY - 2018/4/15

Y1 - 2018/4/15

N2 - This work represents the first use of proton irradiation to simulate in-core radiation damage in Ti3SiC2 and Ti3AlC2 MAX phases. Irradiation experiments were performed to 0.1 dpa at 350 degrees C, with a damage rate of 4.57 x 10(-6) dpa s(-1). The MAX phases displayed significant dimensional instabilities at the crystal level during irradiation leading to large anisotropic changes in lattice parameter, even at low damage levels. The instabilities were accompanied by a decomposition of the Ti-based MAX phases to their binary constituents, TiC. Experimentally observed changes in lattice parameter have been correlated with density functional theory modelling. The most energetically favourable and/or most difficult to recombine defects considered were an M-A antisite (M-A: A(M)), and carbon Frenkel (V-C: C-i). It is proposed that antisite defects, M-A: A(M), are the main contributor to the observed changes in lattice parameter. The proposed mechanism reported in this work potentially enables to design MAX phase compositions, which do not favour antisite defect accumulation. In addition, comparison between the experimental results and theoretical calculations shows that a greater amount of residual damage remains in Ti3AlC2 when compared to Ti3SiC2 after the same irradiation treatment. (c) 2018 Elsevier B.V. All rights reserved.

AB - This work represents the first use of proton irradiation to simulate in-core radiation damage in Ti3SiC2 and Ti3AlC2 MAX phases. Irradiation experiments were performed to 0.1 dpa at 350 degrees C, with a damage rate of 4.57 x 10(-6) dpa s(-1). The MAX phases displayed significant dimensional instabilities at the crystal level during irradiation leading to large anisotropic changes in lattice parameter, even at low damage levels. The instabilities were accompanied by a decomposition of the Ti-based MAX phases to their binary constituents, TiC. Experimentally observed changes in lattice parameter have been correlated with density functional theory modelling. The most energetically favourable and/or most difficult to recombine defects considered were an M-A antisite (M-A: A(M)), and carbon Frenkel (V-C: C-i). It is proposed that antisite defects, M-A: A(M), are the main contributor to the observed changes in lattice parameter. The proposed mechanism reported in this work potentially enables to design MAX phase compositions, which do not favour antisite defect accumulation. In addition, comparison between the experimental results and theoretical calculations shows that a greater amount of residual damage remains in Ti3AlC2 when compared to Ti3SiC2 after the same irradiation treatment. (c) 2018 Elsevier B.V. All rights reserved.

U2 - 10.1016/j.jnucmat.2018.02.008

DO - 10.1016/j.jnucmat.2018.02.008

M3 - Article

VL - 502

SP - 220

EP - 227

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -