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Joshua Ferrigno
Joshua Ferrigno
Nuclear Engineering Ph.D. Student, The Ohio State University
Verified email at buckeyemail.osu.edu - Homepage
Title
Cited by
Cited by
Year
A combined theoretical-experimental investigation of thermal transport in low-dose irradiated thorium dioxide
WR Deskins, A Khanolkar, S Mazumder, CA Dennett, K Bawane, Z Hua, ...
Acta Materialia 241, 118379, 2022
92022
Influence of point defect accumulation on in-pile thermal conductivity degradation: Fuel rod defect distribution and deviation between in-pile and post irradiation thermal …
J Ferrigno, S Adnan, M Khafizov
Journal of Nuclear Materials 573, 154108, 2023
52023
Thermal conductivity evaluation of ion irradiated Si3N4 and ZrN ceramics using spatial domain thermoreflectance
AJ Terricabras, J Ferrigno, L Wang, M Khafizov, AT Nelson, SJ Zinkle
Journal of Applied Physics 132 (7), 2022
42022
Comprehensive characterization of irradiation induced defects in ceria: Impact of point defects on vibrational and optical properties
VS Chauhan, J Ferrigno, S Adnan, J Pakarinen, L He, DH Hurley, ...
Journal of Applied Physics 132 (8), 2022
32022
Evolution of extended defects in UO2 during high temperature annealing
CY Hung, J Ferrigno, RO Gentile, M Khafizov, L He
Journal of Nuclear Materials, 154997, 2024
12024
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, 155090, 2024
2024
Analysis of Radially Resolved Thermal Conductivity in High Burnup Mixed Oxide Fuel
J Ferrigno, T Pavlov, PC Simon, F Cappia, M Khafizov
Materials in Nuclear Energy Systems (MiNES 2023), 2023
2023
Comprehensive Characterization of Microstructure Evolution and its Impact on Thermal Conductivity of Nuclear Fuel Surrogates
M Khafizov, A Khanolkar, K Bawane, M Jin, J Ferrigno, S Adnan, ...
Materials in Nuclear Energy Systems (MiNES 2023), 2023
2023
Impact of Irradiation-induced Lattice Defects and Dopants on Thermal Transport in Oxide Nuclear Fuels
AR Khanolkar, Z Hua, KK Bawane, L He, C Jiang, DH Hurley, S Adnan, ...
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2022
2022
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