Porth Ymchwil

Professor Bill Lee

Ser Cymru Professor in Materials for Extreme Environments

Aelodaeth

1 - 40 o blith 40Maint y tudalen: 50
Trefnu yn ôl: Primeiro autor

  1. Thermal Properties of Rare-Earth Monosilicates for EBC on Si-Based Ceramic Composites

    Al Nasiri, N., Patra, N., Horlait, D., Jayaseelan, D. D. & Lee, B., Chwef 2016, Yn: Journal of the American Ceramic Society. 99, 2

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  2. Cyhoeddwyd

    In-reactor behaviour and economic assessment of enriched gadolinia burnable absorbers

    Bolukbasi, M., Middleburgh, S. & Lee, B., Hyd 2023, Yn: Progress in Nuclear Energy. 164, 104873.

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  3. Cyhoeddwyd

    Effect of ZrB2 and UB2 Discrete Burnable Absorber Pins on Fuel Reactivity

    Bolukbasi, M., Middleburgh, S., Vrtiska, S. & Lee, B., 1 Awst 2022, Yn: Progress in Nuclear Energy. 150, 104295.

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  4. Cyhoeddwyd

    Performance and economic assessment of enriched gadolinia burnable absorbers

    Bolukbasi, M., Middleburgh, S., Dahlfors, M. & Lee, B., Gorff 2021, Yn: Progress in Nuclear Energy. 137, 103752.

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  5. Cyhoeddwyd

    The Stability of Irradiation-Induced Defects in Zr3AlC2, Nb4AlC3 and (Zr0.5,Ti0.5)3AlC2 MAX Phase-Based Ceramics

    Bowden, D., Ward, J., Middleburgh, S., de Moraes Shubeita, S., Zapata-Solvas, E., Lapauw, T., Vleugels, J., Lambrinou, K., Lee, B., Preuss, M. & Frankel, P., 15 Ion 2020, Yn: Acta Materialia. 183, t. 24-35

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  6. Investigating the highest melting temperature materials: A laser melting study of the TaC-HfC system

    Cedillos-Barraza, O., Manara, D., Boboridis, K., Watkins, T., Grasso, S., Jayaseelan, D. D., Konings, R. J. M., Reece, M. J. & Lee, B., 1 Rhag 2016, Yn: Scientific Reports. 6, 37962.

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  7. Degradation of partially immersed glass: A new perspective

    Chinnam, R. K., Fossati, P. C. M. & Lee, W. E., Mai 2018, Yn: Journal of Nuclear Materials. 503, t. 56-65

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  8. Cyhoeddwyd

    The UK National Thermal-Hydraulics Facility: Motivations, Design and Planning Status

    Dahlfors, M., Joannou, J., Brummitt, A., Rushton, M., Middleburgh, S. & Lee, B., 2021, EPJ Web of Conferences. EDP Sciences, Cyfrol 247. 11 t. 20006

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  9. Cyhoeddwyd

    Utilizing neutronics modelling to predict changing Pu ratios in UO2 in the presence of Th

    Evitts, L., Gilbert, M. R., Middleburgh, S., Lee, B. & Dahlfors, M., 1 Gorff 2021, Yn: Progress in Nuclear Energy. 137, 103762.

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  10. Cyhoeddwyd

    Influence of boron isotope ratio on the thermal conductivity of uranium diboride (UB2) and zirconium diboride (ZrB2)

    Evitts, L., Middleburgh, S., Kardoulaki, E., Ipatova, I., Rushton, M. & Lee, B., Ion 2020, Yn: Journal of Nuclear Materials. 528, 151892.

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  11. Cyhoeddwyd

    The future of medical radioisotope production in the UK -- Part Two

    Evitts, L. J., Pearce, F., Middleburgh, S., Rushton, M. & Lee, B., 1 Tach 2021, Nuclear Future, 17, 6, t. 17-19 3 t.

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  12. Cyhoeddwyd

    The future of medical radioisotope production in the UK: An introduction to nuclear medicine

    Evitts, L. J., Pearce, F., Middleburgh, S., Rushton, M. & Lee, B., 1 Awst 2021, Nuclear Future, 17, 4, t. 18-20 3 t.

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  13. Cyhoeddwyd

    Atomic-scale description of interfaces in rutile/sodium silicate glass–crystal composites

    Fossati, P. C. M., Rushton, M. & Lee, W., 21 Meh 2018, Yn: Physical Chemistry Chemical Physics. 20, t. 17624-17636

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  14. 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., Hyd 2017, Yn: Journal of Nuclear Materials. 494, t. 127-137

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  15. Cyhoeddwyd

    Uranium carbide oxidation from 873 K to 1173 K

    Gasparrini, C., Podor, R., Fiquet, O., Horlait, D., May, S., Wenman, M. R. & Lee, W. E., 1 Mai 2019, Yn: Corrosion Science. 151, t. 44-56

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  16. Cyhoeddwyd

    On the stoichiometry of zirconium carbide

    Gasparrini, C., Rana, D., Le Brun, N., Horlait, D., Markides, C. N., Farnan, I. & Lee, W. E., 14 Ebr 2020, Yn: Scientific Reports. 10, 1, t. 6347

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  17. 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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  18. 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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  19. 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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  20. 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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  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

    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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  23. 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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  24. 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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  25. 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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  26. 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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  27. 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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  28. 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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  29. 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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  30. 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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  31. 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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  32. 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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  33. 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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  34. 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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  35. 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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  36. 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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  37. 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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  38. 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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  39. 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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  40. 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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