Items where authors include "Gausse, C."
Article
Smith, H., Cordara, T., Gausse, C. et al. (2 more authors) (2023) Oxidative dissolution of Cr-doped UO2 nuclear fuel. npj Materials Degradation, 7. 25. ISSN 2397-2106
Dixon Wilkins, M.C.J., Gausse, C., Townsend, L.T. orcid.org/0000-0002-7991-9444 et al. (2 more authors) (2022) Characterisation of a complex CaZr0.9Ce0.1Ti2O7 glass–ceramic produced by hot isostatic pressing. Ceramics, 5 (4). pp. 1035-1050. ISSN 2571-6131
Paraskevoulakos, C., Forna-Kreutzer, J.P., Hallam, K.R. et al. (7 more authors) (2022) Investigating the mechanical behaviour of Fukushima MCCI using synchrotron Xray tomography and digital volume correlation. npj Materials Degradation, 6 (1). 55.
Ding, H., Gausse, C., Dixon Wilkins, M.C. et al. (10 more authors) (2022) Chemical characterisation of degraded nuclear fuel analogues simulating the Fukushima Daiichi nuclear accident. npj Materials Degradation, 6 (1). 10.
Ding, H., Dixon Wilkins, M.C. orcid.org/0000-0003-1520-7672, Gausse, C. et al. (8 more authors) (2021) Safely probing the chemistry of Chernobyl nuclear fuel using micro-focus X-ray analysis. Journal of Materials Chemistry A, 9 (21). pp. 12612-12622. ISSN 2050-7488
Blackburn, L., Crawford, R., Walling, S. et al. (9 more authors) (2021) Influence of accessory phases and surrogate type on accelerated leaching of zirconolite wasteforms. npj Materials Degradation, 5. 24. ISSN 2397-2106
Paraskevoulakos, C., Forna-Kreutzer, J.P., Hallam, K.R. et al. (9 more authors) (2021) Investigating the microstructure and mechanical behaviour of simulant “lava-like” fuel containing materials from the Chernobyl reactor unit 4 meltdown. Materials & Design, 201. 109502. ISSN 0264-1275
Fisher, A.J., Imran, M.N.B., Mann, C. orcid.org/0000-0002-8781-1652 et al. (4 more authors) (2020) Short communication : the dissolution of UK simulant vitrified high-level-waste in groundwater solutions. Journal of Nuclear Materials, 538. 152245. ISSN 0022-3115
Barlow, S.T., Bailey, D.J., Fisher, A.J. et al. (7 more authors) (2020) Synthesis, characterisation and corrosion behaviour of simulant Chernobyl nuclear meltdown materials. npj Materials Degradation, 4 (1). 3.
Gausse, C. orcid.org/0000-0002-7392-7507, Dunlop, C.W., Friskney, A.A. et al. (3 more authors) (2020) Synthesis, characterisation and preliminary corrosion behaviour assessment of simulant Fukushima nuclear accident fuel debris. MRS Advances, 5 (1-2). pp. 65-72. ISSN 2059-8521