1. Published

   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 Apr 2017, In: Journal of American Ceramic Society. 100, 4, p. 1377-1387

   Research output: Contribution to journal › Article › peer-review

2. 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., Dec 2014, In: Journal of the European Ceramic Society. 34, 15, p. 3535-3548

   Research output: Contribution to journal › Article › peer-review

3. Published

   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 Jul 2022, In: Journal of Physics: Energy. 4, 3, 034002.

   Research output: Contribution to journal › Article › peer-review

4. Published

   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 Dec 2021, In: Solid State Ionics. 373, 115813.

   Research output: Contribution to journal › Article › peer-review

5. Published

   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 Jan 2024, In: Journal of Nuclear Materials. 154780.

   Research output: Contribution to journal › Article › peer-review

6. Published

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

   Rushton, M. J. D. & Lee, W. E., 1 Feb 2021, In: Nuclear Future. 17, 1, p. 40-44

   Research output: Contribution to journal › Article › peer-review

7. Published

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

   Rushton, M. J. D. & Lee, W. E., 1 Nov 2020, In: Nuclear Future. 16, 6, p. 51-54

   Research output: Contribution to journal › Article › peer-review

8. Published

   Stoichiometry deviation in amorphous zirconium dioxide

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

   Research output: Contribution to journal › Article › peer-review

9. Published

   Doing more with nuclear

   Rushton, M. & Lee, B., May 2021, In: Energy World. May 2021, p. 22-24 3 p.

   Research output: Contribution to journal › Article

10. Published

    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 Nov 2018, In: Progress in Nuclear Energy. 109, p. 214-222

    Research output: Contribution to journal › Article › peer-review

11. Published

    Diffusion in doped and undoped amorphous zirconia

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

    Research output: Contribution to journal › Article › peer-review

12. Published

    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 Aug 2023, In: Scripta Materialia. 233, 115507.

    Research output: Contribution to journal › Article › peer-review

13. Published

    Diffusion in undoped and Cr-doped amorphous UO2

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

    Research output: Contribution to journal › Article › peer-review

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

    Ojovan, M. I., Burakov, B. E. & Lee, W. E., 1 Apr 2018, In: Journal of Nuclear Materials. 501, p. 162-171

    Research output: Contribution to journal › Article › peer-review

15. Published

    Hydrogen Accommodation in the TiZrNbHfTa High Entropy Alloy

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

    Research output: Contribution to journal › Article › peer-review

16. Published

    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 Jan 2020, In: Scripta Materialia. 175, p. 7-10

    Research output: Contribution to journal › Article › peer-review

17. Published

    Structure and properties of amorphous uranium dioxide

    Middleburgh, S., Lee, B. & Rushton, M., 1 Jan 2021, In: Acta Materialia. 202, p. 366-375

    Research output: Contribution to journal › Article › peer-review

18. Published

    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., Mar 2023, In: Journal of Nuclear Materials. 575, 154250.

    Research output: Contribution to journal › Article › peer-review

19. Published

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

    Makurunje, P., Middleburgh, S. & Lee, B., 1 Feb 2023, In: Journal of the European Ceramic Society. 43, 2, p. 283-197

    Research output: Contribution to journal › Article › peer-review

20. Published

    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., Sept 2022, In: Results In Materials. 15, 100320.

    Research output: Contribution to journal › Letter › peer-review

21. Published

    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 Mar 2021, In: Ceramics International. 47, 5, p. 6409-6417

    Research output: Contribution to journal › Article › peer-review

22. Published

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

    Humphry-Baker, S. A. & Lee, W. E., 15 Apr 2016, In: Scripta Materialia. 116, p. 67-70

    Research output: Contribution to journal › Article › peer-review

23. Published

    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., Oct 2018, In: Scripta Materialia. 155, p. 129-133

    Research output: Contribution to journal › Article › peer-review

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

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

    Research output: Contribution to journal › Article › peer-review

25. Oxidation of UC: An in situ high temperature environmental scanning electron microscopy study

    Gasparrini, C., Podor, R., Horlait, D., Rushton, M. J. D., Fiquet, O. & Lee, W. E., Oct 2017, In: Journal of Nuclear Materials. 494, p. 127-137

    Research output: Contribution to journal › Article › peer-review