"Fission product distribution analysis in Zr lined U-Mo fuels using transmission electron microscopy and atom probe tomography" Nicole Rodriguez Perez, Sobhan Patnaik, shehab shousha, Mukesh Bachhav, Luca Capriotti, Benjamin Beeler, Geoffrey Beausoleil, Maria Okuniewski, TMS 2025 Annual Meeting March 23-27, (2025) |
"Accelerated and heterogeneous corrosion of Cr-doped uranium nitride fuel pellets" Yulia Mishchenko, Sobhan Patnaik, Vanessa K. Peterson, Patrick A. Burr, Denise Adorno Lopes, Edward G. Obbard, Jennifer H. Stansby, [2025] Corrosion Science · DOI: 10.1016/j.corsci.2025.113175 | |
"Corrigendum to “Fission accelerated steady-state post irradiation examinations - Part II” Nucl. Eng. Technol. 56 (2024) 4158-4168 (Nuclear Engineering and Technology (2024) 56(10) (4158–4168), (S173857332400233X), (10.1016/j.net.2024.05.019))" Geoffrey L. Beausoleil, Luca Capriotti, Sobhan Patnaik, [2025] Nuclear Engineering and Technology · DOI: 10.1016/j.net.2025.103500 · EID: 2-s2.0-85215866206 · ISSN: 2234-358X | |
"Enhanced steam oxidation resistance of uranium nitride nuclear fuel pellets" Yulia Mishchenko, Sobhan Patnaik, Vanessa K. Peterson, Christopher Baldwin, Patrick A. Burr, Denise Adorno Lopes, Edward G. Obbard, Jennifer H. Stansby, [2024] Corrosion Science · DOI: 10.1016/j.corsci.2024.111877 · EID: 2-s2.0-85184892299 · ISSN: 0010-938X | |
"Evaluating the diffusion of Kr in UO2 and ADOPTTM using time-of-flight elastic recoil detection analysis (ToF-erda)" Denise A. Lopes, Kyle D. Johnson, Sobhan Patnaik, Johan Oscarsson, Mauricio Sortica, Per Petersson, Daniel Primetzhofer, Robert J. W. Frost, [2024] Journal of Nuclear Science and Technology · DOI: 10.1080/00223131.2024.2423639 · EID: 2-s2.0-85209906379 · ISSN: 0022-3131 | |
"Fission Accelerated Steady-state Post Irradiation Examinations of U-10Zr Metallic Fuel" [2024] Transactions of the American Nuclear Society · DOI: 10.13182/t130-44705 · EID: 2-s2.0-85205789673 · ISSN: 0003-018X | |
"Fission accelerated steady-state post irradiation examinations - Part II" Geoffrey L. Beausoleil II, Luca Capriotti, Sobhan Patnaik, [2024] Nuclear Engineering and Technology · DOI: 10.1016/j.net.2024.05.019 · EID: 2-s2.0-85193974413 · ISSN: 2234-358X | |
"Parallel Irradiation Testing to Support Accelerated Down-Selection of Advanced Fuels" [2024] Transactions of the American Nuclear Society · DOI: 10.13182/t130-44808 · EID: 2-s2.0-85205827081 · ISSN: 0003-018X | |
"Crystallographic characterization of U2CrN3: A neutron diffraction and transmission electron microscopy approach" Yulia Mishchenko, Jennifer H. Stansby, Andrea Fazi, Vanessa K. Peterson, Daniel Jädernäs, Mattias Thuvander, Kyle D. Johnson, Edward G. Obbard, Denise A. Lopes, Sobhan Patnaik, [2023] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2023.101441 · EID: 2-s2.0-85159089610 · ISSN: 2352-1791 | |
"Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution" Sobhan Patnaik, Janne Wallenius, Denise Adorno Lopes, Yulia Mishchenko, [2023] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2023.101459 · EID: 2-s2.0-85162888115 · ISSN: 2352-1791 | |
"Experimental set-up for studying temperature gradient driven cracking" [2022] | |
"Potential accident tolerant fuel candidate: Investigation of physical properties of the ternary phase U2CrN3" Sobhan Patnaik, Elina Charatsidou, Janne Wallenius, Denise Adorno Lopes, Yulia Mishchenko, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153851 · EID: 2-s2.0-85132727972 · ISSN: 0022-3115 | |
"Potential accident tolerant fuel candidate: Investigation of physical properties of the ternary phase U2CrN3" Sobhan Patnaik, Elina Charatsidou, Janne Wallenius, Denise Adorno Lopes, Yulia Mishchenko, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153851 | |
"Rational design of advanced nuclear fuel materials: new path ways from in situ neutron diffraction" [2022] ANBUG-AINSE Neutron Scattering Symposium (AANSS 2022), Lucas Heights, NSW (Australia), 9-11 Nov 2022 | |
"Coupled physics simulation of fracture in nuclear fuel pellets induced by resistive heating" Benjamin W. Spencer, Sobhan Patnaik, Travis W. Knight, Mary Lou Dunzik-Gougar, Ju-Yuan Yeh, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153004 · EID: 2-s2.0-85110312596 · ISSN: 0022-3115 | |
"Evaluation of ceria as a surrogate material for UO2 in experiments on fuel cracking driven by resistive heating" D.A. Lopes, B.W. Spencer, T.M. Besmann, E. Roberts, T.W. Knight, S. Patnaik, [2021] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2021.111482 · EID: 2-s2.0-85116352991 · ISSN: 0029-5493 | |
"Separate-Effects Tests for Studying Temperature-Gradient-Driven Cracking in UO2 Pellets" B. W. Spencer, E. Roberts, T. M. Besmann, T. W. Knight, S. Patnaik, [2021] Nuclear Science and Engineering · DOI: 10.1080/00295639.2021.1932223 · EID: 2-s2.0-85111690602 · ISSN: 1943-748X | |
"Separate-Effects Tests for Studying Temperature-Gradient-Driven Cracking in UO2 Pellets" B. W. Spencer, E. Roberts, T. M. Besmann, T. W. Knight, S. Patnaik, [2021] Nuclear Science and Engineering · DOI: 10.1080/00295639.2021.1932223 | |
"Comparative analysis of temperature dependent properties of commercial nuclear fuel pellet and surrogates undergoing cracking: A review" Sobhan Patnaik, [2020] Ceramics International · DOI: 10.1016/j.ceramint.2020.06.266 · EID: 2-s2.0-85087418871 · ISSN: 0272-8842 | |
"Experimental system for studying temperature gradient-driven fracture of oxide nuclear fuel out of reactor"
D. A. Lopes, T. M. Besmann, B. W. Spencer, T. W. Knight, S. Patnaik,
[2020]
Review of Scientific Instruments
· DOI: 10.1063/1.5119361
· EID: 2-s2.0-85081129962
· ISSN: 1089-7623
Temperature gradients in ceramic light water reactor (LWR) uranium dioxide (UO2) nuclear fuel pellets generate thermal stresses that cause fractures in the fuel, which begins early in the life of fresh fuel. The combination of heating due to fission and forced convective cooling on the exterior of LWR fuel rods generates a temperature profile that is difficult to replicate outside the reactor environment. In this study, a state-of-the-art experimental setup using electrical heating to study certain aspects of temperature driven fracture was built, and surrogate fuel materials such as ceria (CeO2) were used to validate the system. Cracking experiments were conducted on these surrogates by inducing reactivity-initiated-accident like temperature gradients in the pellets via induction and direct resistance heating. Induction heating was done using copper coils and molybdenum susceptors, which heated the surrogates to a threshold temperature that is sufficiently high for the fuel material to conduct current. Thereafter, direct resistance heating was achieved by passing current through the specimen using a DC power supply to introduce volumetric heating to replicate LWR operating conditions. The pellets were held against nickel electrodes and mounted on a boron nitride test-stand. All the tests were carried out in a stainless-steel vacuum chamber. Simultaneous real-time dual imaging of the surrogate pellet surface was implemented using an optical and infrared camera system that was mounted along axial and perpendicular directions to the pellet surface, respectively. A beam-splitter was used to split the incoming radiation from the sample into two halves. While one of the beams was transmitted from the splitter through a bandpass filter to obtain optical images, the other beam was reflected from the splitter to the thermal camera to capture full-field temperature gradients of the as-fabricated pellet surface during cracking. Some initial tests were conducted with a 2-color pyrometer that was later substituted with a forward-looking infrared thermal camera to capture the temperature profiles. A LabVIEW data acquisition system was set up for collecting useful data during experiments. |
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"Separate-effects validation experiments for models of fracture in ceramic nuclear fuel" [2020] GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference · EID: 2-s2.0-85081079868 | |
"Framework for structural online health monitoring of aging and degradation of secondary systems due to some aspects of erosion" [2016] Idaho National Lab.(INL), Idaho Falls, ID (United States) | |
Source: ORCID/CrossRef using DOI |
Advanced characterization of irradiated FAST aLEU U-Mo rodlets using Transmission Electron Microscopy and Atom Probe Tomography - FY 2024 RTE 2nd Call, #24-4952
Advanced characterization of irradiated FAST rodlets using Transmission Electron Microscopy and Atom Probe Tomography - FY 2024 RTE 1st Call, #24-4848
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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