| Pore pressure estimation in irradiated UMo D Salvato, A Leenaers, S Van den Berghe, C Detavernier Journal of Nuclear Materials 510, 472-483, 2018 | 24 | 2018 |
| The initial formation stages of a nanobubble lattice in neutron irradiated U (Mo) D Salvato, A Leenaers, W Van Renterghem, S Van den Berghe, ... Journal of Nuclear Materials 529, 151947, 2020 | 20 | 2020 |
| Spark plasma sintering of fine uranium carbide powder D Salvato, JF Vigier, M Cologna, L Luzzi, J Somers, V Tyrpekl Ceramics International 43 (1), 866-869, 2017 | 19 | 2017 |
| Innovative preparation route for uranium carbide using citric acid as a carbon source D Salvato, JF Vigier, OD Blanco, L Martel, L Luzzi, J Somers, V Tyrpekl Ceramics International 42 (15), 16710-16717, 2016 | 18 | 2016 |
| Transmission electron microscopy study of a high burnup U-10Zr metallic fuel D Salvato, X Liu, DJ Murray, KM Paaren, F Xu, T Pavlov, MT Benson, ... Journal of Nuclear Materials 570, 153963, 2022 | 10 | 2022 |
| Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels F Xu, L Cai, D Salvato, L Capriotti, T Yao Scientific Reports 13 (1), 10616, 2023 | 5 | 2023 |
| U (Mo) grain refinement induced by irradiation with high energy iodine D Salvato, J Shi, H Breitkreutz, W Van Renterghem, B Baumeister, ... Journal of Nuclear Materials 548, 152850, 2021 | 5 | 2021 |
| Temperature effects on interdiffusion of Al and U-Mo under irradiation B Ye, Y Miao, J Shi, D Salvato, K Mo, L Jamison, A Bergeron, GL Hofman, ... Journal of Nuclear Materials 544, 152684, 2021 | 5 | 2021 |
| Early self-organization of fission gas bubble superlattice formation in neutron-irradiated monolithic U-10Mo fuels C Smith, K Bawane, D Salvato, M Bachhav, D Keiser, B Miller, J Gan, ... Journal of Nuclear Materials 578, 154358, 2023 | 4 | 2023 |
| Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel D Salvato, CA Smith, B Ye, ZG Mei, AM Yacout, J Van Eyken, BD Miller, ... Nuclear Materials and Energy 36, 101469, 2023 | 3 | 2023 |
| Microstructural and phase changes in alpha uranium investigated via in-situ studies and molecular dynamics FG Di Lemma, T Yao, D Salvato, L Capriotti, F Teng, AM Jokisaari, ... Journal of Nuclear Materials 577, 154341, 2023 | 3 | 2023 |
| Understanding fission gas bubble distribution and zirconium redistribution in neutron-irradiated U-Zr metallic fuel using machine learning F Xu, L Cai, D Salvato, JJ Giglio, M Benson, DJ Murray, CA Adkins, ... Microscopy and Microanalysis 28 (S1), 82-83, 2022 | 3 | 2022 |
| Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel Y Wang, BD Miller, JM Harp, D Salvato, L Capriotti, T Yao Journal of Nuclear Materials 572, 153990, 2022 | 2 | 2022 |
| Advanced Characterization-Informed Framework and Quantitative Insight to Irradiated Annular U-10Zr Metallic Fuels F Xu, L Cai, D Salvato, L Capriotti, T Yao arXiv preprint arXiv:2210.09104, 2022 | 2 | 2022 |
| Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel D Salvato, CA Smith, TR Pavlov, WA Hanson, KK Bawane, MN Bachhav, ... Journal of Nuclear Materials 588, 154789, 2024 | 1 | 2024 |
| Microstructure and phase evolution in the U-10Zr fuel investigated by in situ TEM heating experiments. FG Di Lemma, D Salvato, L Capriotti, WJ Williams, F Teng, Y Zhang, ... Journal of Nuclear Materials 583, 154475, 2023 | 1 | 2023 |
| The role of UC inclusions in the development of fission gas bubble superlattice neutron-irradiated monolithic U-10Mo fuels C Smith, K Bawane, J Gan, D Keiser, D Salvato, M Bachhav, JF Jue Journal of Nuclear Materials 581, 154474, 2023 | 1 | 2023 |
| Corrigendum to “Pore pressure estimation in irradiated UMo”[J. Nucl. Mater. 510 (2018) 472–483](Journal of Nuclear Materials (2018) 510 (472–483),(S0022311518305749),(10.1016/j … D Salvato, A Leenaers, S Van den Berghe, C Detavernier Journal of Nuclear Materials 538, 152393, 2020 | 1 | 2020 |
| Temperature dependence of irradiation-induced U-Mo-Al interdiffusion B Ye, GL Hofman, A Bergeron, Y Miao, D Salvato, A Leenaers, ... Proc. Int. Meeting on Research Reactor Fuel Management (RRFM), Munich, Germany, 2018 | 1 | 2018 |
| Analysis of radially resolved thermal conductivity in high burnup mixed oxide fuel and comparison to thermal conductivity correlations implemented in fuel performance codes J Ferrigno, T Pavlov, N Poudel, D Salvato, C Tsai, B Merritt, A Hansen, ... Journal of Nuclear Materials 596, 155090, 2024 | | 2024 |
