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Sobhan Patnaik
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Year
Comparative analysis of temperature dependent properties of commercial nuclear fuel pellet and surrogates undergoing cracking: A review
S Patnaik
Ceramics International 46 (16, Part A), 24765-24778, 2020
102020
Experimental System for Studying Temperature Gradient Driven Fracture of Oxide Nuclear Fuel Out of Reactor
S Patnaik, DA Lopes, TM Besmann, B Spencer, TW Knight
Review of Scientific Instruments 91 (3), 2020
102020
Separate Effects Tests for Studying Temperature-Gradient-Driven Cracking in UO2 Pellets
S Patnaik, BW Spencer, E Roberts, TM Besmann, TW Knight
Nuclear Science and Engineering, 10.1080/00295639.2021.1932223, 2021
92021
Separate-Effects Validation Experiments for Models of Fracture in Ceramic Nuclear Fuel
BW Spencer, NE Woolstenhulme, LA Emerson, J Yeh, DD Imholte, ...
Global TopFuel 2019, Seattle, Washington, 2019
82019
Potential Accident Tolerant Fuel Candidate: Investigation of Physical Properties of the Ternary Phase U2CrN3
Y Mishchenko, S Patnaik, E Charatsidou, J Wallenius, DA Lopes
Journal of Nuclear Materials 568 (153851), 2022
62022
Evaluation of Ceria as a Surrogate Material for UO2 in Experiments on Fuel Cracking Driven by Resistive Heating
S Patnaik, DA Lopes, B Spencer, E Roberts, TM Besmann, TW Knight
Nuclear Engineering and Design 384, 2021
42021
Coupled Physics Simulation of Fracture in Nuclear Fuel Pellets Induced by Resistive Heating
Ju-Yuan Yeh, B.W. Spencer, Sobhan Patnaik, Travis W. Knight, M.L. Dunzik-Gougar
Journal of Nuclear Materials 553, 2021
42021
Framework for structural online health monitoring of aging and degradation of secondary systems due to some aspects of erosion
A Gribok, S Patnaik, C Williams, M Pattanaik, R Kanakala
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2016
32016
Separate Effects Tests for Studying Thermal Gradient Driven Cracking in UO2 Pellets Undergoing Resistive Heating
S Patnaik
University of South Carolina, 2021
22021
Crystallographic characterization of U2CrN3: A neutron diffraction and transmission electron microscopy approach
S Patnaik, Y Mischenko, J Stansby, A Fazi, VK Peterson, D Jädernäs, ...
Journal of Nuclear Materials and Energy 35, 101441, 2023
12023
Thermophysical properties and oxidation behaviour of the U0. 8Zr0. 2N solid solution
Y Mishchenko, S Patnaik, J Wallenius, DA Lopes
Nuclear Materials and Energy 35, 101459, 2023
12023
Enhanced steam oxidation resistance of uranium nitride nuclear fuel pellets
JH Stansby, Y Mischenko, S Patnaik, V Peterson, C Baldwin, P Burr, ...
Corrosion Science 230 (111877), 2024
2024
Fission Accelerated Steady-State Testing Irradiations and Post Irradiation Examination
S Patnaik, G Beausoleil, L Capriotti
Materials in Nuclear Energy Systems (MiNES 2023), 2023
2023
Evaluation of Irradiation Creep Effects in HT9 Cladding for FAST Experiments
AL Swearingen, B Beausoleil, KM Paaren, S Patnaik, L Capriotti
Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023
2023
Experimental set-up for studying temperature gradient driven cracking
T Knight, S Patnaik, T Besmann, E Roberts
US Patent App. 17/506,928, 2022
2022
Design and Assembly of Worm Gear Reducer
S Patnaik
Global Journal for Research Analysis 4 (4), 2015
2015
Material Characterization of Advanced Aluminium Alloys
S Patnaik
International Journal of Recent Scientific Research 6, 2961-2967, 2015
2015
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Articles 1–17