1. 2020
2. 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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3. 2019
4. 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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5. 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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6. 2018
7. 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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8. 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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9. 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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10. 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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11. 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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12. 2017

13. 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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14. 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

    Allbwn ymchwil: Cyfraniad at gyfnodolyn › Erthygl › adolygiad gan gymheiriaid