1. Cyhoeddwyd

   Predicting the thermal expansion of body-centred cubic (BCC) high entropy alloys in the Mo-Nb-Ta-Ti-W system

   Wilson, J., Evitts, L. J., Fraile, A., Wilson, R., Rushton, M., Goddard, D., Lee, B. & Middleburgh, S., 1 Gorff 2022, Yn: Journal of Physics: Energy. 4, 3, 034002.

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2. Cyhoeddwyd

   The accommodation of lithium in bulk ZrO2

   Stephens, G. F., Than, Y. R., Nelson, W., Evitts, L. J., Wenman, M., Murphy, S., Grimes, R. W., Cole-Baker, A., Ortner, S., Gotham, N., Rushton, M., Lee, B. & Middleburgh, S., 15 Rhag 2021, Yn: Solid State Ionics. 373, 115813.

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3. E-gyhoeddi cyn argraffu

   Lithium stabilization of amorphous ZrO2

   Stephens, G. F., Wilson, J., Curling, S., He, G., Thomas, P. J., Williams, D., Ortner, S., Grovenor, C., Rushton, M., Cole-Baker, A. & Middleburgh, S., 6 Mai 2024, Yn: Progress in Nuclear Energy. 171, 105165.

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4. Cyhoeddwyd

   Assessing Li accommodation at amorphous ZrO2 grain boundaries

   Stephens, G. F., London, I., Ghardi, M., Fraile, A., Rushton, M., Lee, B., Cole-Baker, A. & Middleburgh, S., 1 Ion 2024, Yn: Journal of Nuclear Materials. 154780.

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5. Predicted structure, thermo-mechanical properties and Li ion transport in LiAlF4 glass

   Stechert, T. R., Rushton, M. J. D., Grimes, R. W. & Dillon, A. C., 15 Awst 2012, Yn: Journal of Non-Crystalline Solids. 358, 16, t. 1917-1923 7 t.

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6. Predicted Mechanism for Enhanced Durability of Zinc Containing Silicate Glasses

   Stechert, T. R., Rushton, M. J. D. & Grimes, R. W., 1 Mai 2013, Yn: Journal of American Ceramic Society. 96, 5, t. 1450-1455 6 t.

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7. Surface dependent segregation of Y2O3 in t-ZrO2

   Stanek, CR., Grimes, RW., Rushton, MJD., McClellan, KJ. & Rawlings, RD., 1 Medi 2005, Yn: Philosophical Magazine Letters. 85, 9, t. 445-453 9 t.

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8. Effect of A-site cation disorder on oxygen diffusion in perovskite-type Ba0.5Sr0.5Co1-xFexO2.5

   Shiiba, H., Bishop, C. L., Rushton, M. J. D., Nakayama, M., Nogami, M., Kilner, J. A. & Grimes, R. W., 2013, Yn: Journal of Materials Chemistry A. 1, 35, t. 10345-10352 8 t.

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9. Effect of strain on the oxygen diffusion in yttria and gadolinia co-doped ceria

   Rushton, M. J. D., Chroneos, A., Skinner, S. J., Kilner, J. A. & Grimes, R. W., 10 Ion 2013, Yn: Solid State Ionics. 230, SI, t. 37-42 6 t.

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10. Simulation of defects and defect processes in fluorite and fluorite related oxides: Implications for radiation tolerance

    Rushton, M. J. D., Stanek, C. R., Cleave, A. R., Uberuaga, B. P., Sickafus, K. E. & Grimes, R. W., 1 Chwef 2007, Yn: Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 255, 1, SI, t. 151-157 7 t.

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11. Cyhoeddwyd

    Stoichiometry deviation in amorphous zirconium dioxide

    Rushton, M. J. D., Ipatova, I., Evitts, L. J., Lee, W. E. & Middleburgh, S. C., 28 Mai 2019, Yn: RSC Advances. 9, 29, t. 16320-16327

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12. Cyhoeddwyd

    Impact of uniaxial strain and doping on oxygen diffusion in CeO2

    Rushton, M. J. D. & Chroneos, A., 14 Awst 2014, Yn: Scientific Reports. 4

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13. Cyhoeddwyd

    Co-generation in the early days of nuclear power: Part 2: Metal production

    Rushton, M. J. D. & Lee, W. E., 1 Chwef 2021, Yn: Nuclear Future. 17, 1, t. 40-44

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14. Predicted changes to alkali concentration adjacent to glass-crystal interfaces

    Rushton, M. J. D., Grimes, R. W. & Owens, S. L., 1 Mai 2008, Yn: Journal of American Ceramic Society. 91, 5, t. 1659-1664 6 t.

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15. Cyhoeddwyd

    Co-Generation in the Early Days of Nuclear Power: Part 1: Calder Hall and Chapelcross

    Rushton, M. J. D. & Lee, W. E., 1 Tach 2020, Yn: Nuclear Future. 16, 6, t. 51-54

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16. Cyhoeddwyd

    Exploring small nuclear to plug the energy gaps

    Rushton, M., 8 Medi 2022, Yn: Nature. 609, 7926, t. S8 1 t.

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17. Predicted pyrochlore to fluorite disorder temperature for A(2)Zr(2)O(7) compositions

    Rushton, MJD., Grimes, RW., Stanek, CR. & Owens, S., 1 Meh 2004, Yn: Journal of Materials Research. 19, 6, t. 1603-1604 2 t.

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18. Changes to alkali ion content adjacent to crystal-glass interfaces

    Rushton, M. J. D., Grimes, R. W. & Owens, S. L., 2008, Scientific Basis for Nuclear Waste Management XXXI. Lee, WE., Roberts, JW., Hyatt, NC. & Grimes, RW. (gol.). Cyfrol 1107. t. 207+ (Materials Research Society Symposium Proceedings).

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19. A critical assessment of interatomic potentials for ceria with application to its elastic properties revisited

    Rushton, M. J. D. & Chroneos, A., Tach 2013, Yn: Journal of Materials Science: Materials in Electronics. 24, 11, t. 4590-4592 3 t.

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20. Cyhoeddwyd

    Doing more with nuclear

    Rushton, M. & Lee, B., Mai 2021, Yn: Energy World. May 2021, t. 22-24 3 t.

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21. Partial ordering of glass networks adjacent to simulated glass-crystal interfaces

    Rushton, M. J. D., Grimes, R. W. & Owens, S. L., 1 Awst 2011, Yn: Journal of Non-Crystalline Solids. 357, 16-17, t. 3278-3287 10 t.

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22. Effect of trivalent dopants on local coordination and electronic structure in crystalline and amorphous ZnO

    Ramo, D. M., Chroneos, A., Rushton, M. J. D. & Bristowe, P. D., 31 Maw 2014, Yn: Thin Solid Films. 555, t. 117-121 5 t.

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23. Cyhoeddwyd

    Thermal conductivity variation in uranium dioxide with gadolinia additions

    Qin, M., Middleburgh, S., Cooper, M. W. D., Rushton, M., Puide, M., Kuo, E. Y., Grimes, R. W. & Lumpkin, G. R., Tach 2020, Yn: Journal of Nuclear Materials. 540, 152258.

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24. Thermal conductivity and energetic recoils in UO2 using a many-body potential model

    Qin, M. J., Cooper, M. W. D., Kuo, E. Y., Rushton, M. J. D., Grimes, R. W., Lumpkin, G. R. & Middleburgh, S. C., 10 Rhag 2014, Yn: Journal of Physics: Condensed Matter. 26, 49

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25. Thermodynamic calculations of oxygen self-diffusion in mixed-oxide nuclear fuels

    Parfitt, D. C., Cooper, M. W. D., Rushton, M. J. D., Christopoulos, S. -R. G., Fitzpatricka, M. E. & Chroneos, A., 29 Gorff 2016, Yn: RSC Advances. 6, 78, t. 74018-74027 10 t.

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