دنبال کردن
Joshua Ferrigno
عنوان
نقل شده توسط
نقل شده توسط
سال
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
122022
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
92023
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
52022
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
Evolution of extended defects in UO2 during high temperature annealing
CY Hung, J Ferrigno, RO Gentile, M Khafizov, L He
Journal of Nuclear Materials 593, 154997, 2024
32024
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
22024
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, B Merritt, A Hansen, T Munro, ...
JOURNAL OF NUCLEAR MATERIALS 600, 2024
2024
Platform Of Optimal Experiment Management
C Wang, TR Pavlov, PC Simon, JM Ferrigno
Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2024
2024
Radial Evolution of Thermal Conductivity in Actinide Oxide Fuels
JM Ferrigno
The Ohio State University, 2024
2024
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
Implications of Point Defect Accumulation on Uo2 Thermal Conductivity and Fission Gas Release Under Accelerated Fuel Irradiation
M Alshannaq, C Owen, J Ferrigno, M Minaruzzaman, H Abdel-Khalik, ...
Available at SSRN 5099836, 0
Integrated Multiscale Experiment and Model Analysis of Radially Resolved Microstructure and Thermal Conductivity in Mixed Oxide Fuel
J Ferrigno, T Pavlov, PCA Simon, M Goodson, E Hisle, DS Novascone, ...
Available at SSRN 4932760, 0
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مقاله‌ها 1–12