1. Cyhoeddwyd

   Experimental synthesis and density functional theory investigation of radiation tolerance of Zr-3(Al1-xSix)C-2 MAX phases

   Zapata-Solvas, E., Christopoulos, S-R. G., Ni, N., Parfitt, D. C., Horlait, D., Fitzpatrick, M. E., Chroneos, A. & Lee, W. E., 1 Ebr 2017, Yn: Journal of American Ceramic Society. 100, 4, t. 1377-1387

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2. HfB2 ceramic polycrystals: A low-temperature metal-like ceramic at high temperatures?

   Zapata-Solvas, E., Moshtaghioun, B. M., Gómez-García, D., Domínguez-Rodríguez, A. & Lee, W. E., Hyd 2021, Yn: Scripta Materialia. 203, 114037.

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3. Effect of La2O3 addition on long-term oxidation kinetics of ZrB2–SiC and HfB2–SiC ultra-high temperature ceramics

   Zapata-Solvas, E., Jayaseelan, D. D., Brown, P. M. & Lee, B., Rhag 2014, Yn: Journal of the European Ceramic Society. 34, 15, t. 3535-3548

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4. 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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5. 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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6. 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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7. 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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8. 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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9. 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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10. 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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11. Cyhoeddwyd

    Temperature dependent volatilisation behaviour of Cs from two commercial adsorbents used at Fukushima measured using novel experimental apparatus

    Pletser, D., Ohashi, T., Yoshii, Y. & Lee, W. E., 1 Tach 2018, Yn: Progress in Nuclear Energy. 109, t. 214-222

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12. Cyhoeddwyd

    Diffusion in doped and undoped amorphous zirconia

    Owen, M., Rushton, M., Evitts, L. J., Claisse, A., Puide, M., Lee, B. & Middleburgh, S., Tach 2021, Yn: Journal of Nuclear Materials. 555, 153108.

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13. Cyhoeddwyd

    Modelling the impact of configurational entropy on the stability of amorphous SiO2

    Owen, M., Rushton, M., Cooper, M. W., Ghardi, M., Claisse, A., Lee, B. & Middleburgh, S., 1 Awst 2023, Yn: Scripta Materialia. 233, 115507.

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14. Cyhoeddwyd

    Diffusion in undoped and Cr-doped amorphous UO2

    Owen, M., Cooper, M. W. D., Rushton, M., Claisse, A., Lee, B. & Middleburgh, S., 1 Ebr 2023, Yn: Journal of Nuclear Materials. 576, 154270.

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15. Radiation-induced microcrystal shape change as a mechanism of wasteform degradation

    Ojovan, M. I., Burakov, B. E. & Lee, W. E., 1 Ebr 2018, Yn: Journal of Nuclear Materials. 501, t. 162-171

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16. Cyhoeddwyd

    Hydrogen Accommodation in the TiZrNbHfTa High Entropy Alloy

    Moore, C., Wilson, J., Rushton, M., Lee, B., Astbury, J. & Middleburgh, S., 1 Mai 2022, Yn: Acta Materialia. 229, 117832.

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17. Cyhoeddwyd

    Evidence of excess oxygen accommodation in yttria partially-stabilized zirconia

    Middleburgh, S. C., Ipatova, I., Evitts, L. J., Rushton, M. J. D., Assinder, B., Grimes, R. W. & Lee, W. E., 15 Ion 2020, Yn: Scripta Materialia. 175, t. 7-10

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18. Cyhoeddwyd

    Structure and properties of amorphous uranium dioxide

    Middleburgh, S., Lee, B. & Rushton, M., 1 Ion 2021, Yn: Acta Materialia. 202, t. 366-375

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19. Cyhoeddwyd

    Enrichment of Chromium at Grain Boundaries in Chromia Doped UO2

    Middleburgh, S., Dumbill, S., Qaisar, A., Vatter, I., Owen, M., Vallely, S., Goddard, D., Eaves, D., Puide, M., Limback, M. & Lee, B., Maw 2023, Yn: Journal of Nuclear Materials. 575, 154250.

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20. Cyhoeddwyd

    Addressing high processing temperatures in reactive melt infiltration for multiphase ceramic composites

    Makurunje, P., Middleburgh, S. & Lee, B., 1 Chwef 2023, Yn: Journal of the European Ceramic Society. 43, 2, t. 283-197

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21. Cyhoeddwyd

    Defect Behaviour in the MoNbTaVW High Entropy Alloy (HEA)

    Lin-Vines, A., Wilson, J., Fraile, A., Evitts, L. J., Rushton, M., Astbury, J., Lee, W. E. & Middleburgh, S. C., Medi 2022, Yn: Results In Materials. 15, 100320.

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22. Cyhoeddwyd

    Interface properties of Ti3SiC2/Al2O3 ceramics: Combined experiments and first-principles calculations

    Ji, J., Yu, J., Lee, B., Middleburgh, S., Li, D., Wang, X., Li, Q., Wang, Z., Shi, G., Chen, F. & Zhang, L., 1 Maw 2021, Yn: Ceramics International. 47, 5, t. 6409-6417

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23. Cyhoeddwyd

    Tungsten carbide is more oxidation resistant than tungsten when processed to full density

    Humphry-Baker, S. A. & Lee, W. E., 15 Ebr 2016, Yn: Scripta Materialia. 116, t. 67-70

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24. Cyhoeddwyd

    A candidate fusion engineering material, WC-FeCr

    Humphry-Baker, S. A., Harrison, R. W., Greaves, G., Knowles, A. J., Smith, G. D. W., Donnelly, S. E. & Lee, W. E., Hyd 2018, Yn: Scripta Materialia. 155, t. 129-133

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25. Synthesis and DFT investigation of new bismuth-containing MAX phases

    Horlait, D., Middleburgh, S. C., Chroneos, A. & Lee, W. E., 7 Ion 2016, Yn: Scientific Reports. 6

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