关注
Daniele Salvato
Daniele Salvato
未知所在单位机构
在 inl.gov 的电子邮件经过验证
标题
引用次数
引用次数
年份
Pore pressure estimation in irradiated UMo
D Salvato, A Leenaers, S Van den Berghe, C Detavernier
Journal of Nuclear Materials 510, 472-483, 2018
272018
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
202020
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
192017
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
192016
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
132022
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
52023
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
52023
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
52021
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
52021
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
42023
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
32023
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
32022
The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study
D Salvato, KM Paaren, JA Hirschhorn, LK Aagesen, F Xu, FG Di Lemma, ...
Journal of Nuclear Materials 591, 154928, 2024
22024
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
22022
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
22022
Mechanical Properties of Irradiated U-10 wt.% Mo Alloy Degraded by Porosity Development
JL Schulthess, K Baird, P Petersen, D Salvato, H Ozaltun, WA Hanson, ...
Journal of Nuclear Engineering and Radiation Science 10 (3), 2024
12024
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
12024
A fine pore-preserved deep neural network for porosity analytics of a high burnup U-10Zr metallic fuel
H Wang, F Xu, L Cai, D Salvato, FG Di Lemma, L Capriotti, T Yao, M Xian
Scientific Reports 13 (1), 22274, 2023
12023
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
12023
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
12023
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