NSUF - Nuclear Science User Facilities

Ryan Sweet

Profile Information
Name
Dr. Ryan Sweet
Institution
Idaho National Laboratory
Position
Senior Modeling and Simulation Engineer
h-Index
10
ORCID
0000-0002-7919-4623
Biography

Dr. Ryan Sweet is a Senior Modeling and Simulation Engineer in the Computational Mechanics and Materials Department and the Research and Development Lead for the BISON fuel performance code at Idaho National Laboratory. His work focuses on the development of advanced models in order to assess the thermomechanical performance and behavior of fuels and components under irradiation for a variety of reactor designs and scenarios (ATF fuel concepts, LOCA analysis, and TRISO compact modeling, in particular).

Prior to his tenure at INL, Dr. Sweet served as R&D Staff at Oak Ridge National Laboratory in the Advanced Reactor Systems Engineering Group.


Expertise
Accelerated Fuel Qualification (AFQ), Accident Tolerant Fuel (ATF) Cladding, Advanced Gas-cooled Reactor (AGR), ATF, BISON, Creep, Diffusion, Doped Fuel, FeCrAl, Fission Gas Release (FGR), Fuel Cladding Chemical Interaction (FCCI), Fuel Performance, Fuels, High Burnup Fuel, High Burnup Structure (HBS), Modeling, Plasticity, Sodium Fast Reactor, Swelling, Thermomechanics
Additional Publications:
"Development and demonstration of a BISON–Griffin modeling framework for the design of targeted TRISO transient experiments in the Transient Reactor Test Facility" Mustafa K. Jaradat, Ryan T. Sweet, Paul A. Demkowicz, Paolo Balestra, Gerhard Strydom, Jacob A. Hirschhorn, [2025] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2024.113720 · EID: 2-s2.0-85210124462 · ISSN: 0029-5493
"Wrought FeCrAl alloy (C26M) cladding behavior and burst under simulated loss-of-coolant accident conditions" C.P. Massey, J.A. Hirschhorn, S.B. Bell, K.A. Kane, R.T. Sweet, [2025] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2024.113712 · EID: 2-s2.0-85209375687 · ISSN: 0029-5493
"Bayesian uncertainty quantification of tristructural isotropic particle fuel silver release: Decomposing model inadequacy plus experimental noise and parametric uncertainties" Aysenur Toptan, Yifeng Che, Daniel Schwen, Ryan T. Sweet, Jason D. Hales, Stephen R. Novascone, Somayajulu L.N. Dhulipala, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154790 · EID: 2-s2.0-85174727885 · ISSN: 0022-3115
"Development and Demonstration of a Bison-Griffin Modeling Framework for the Design of Targeted Triso Transient Experiments in the Transient Reactor Test Facility" Mustafa Jaradat, Ryan Sweet, Paul Demkowicz, Paolo Balestra, Gerhard Strydom, Jake Hirschhorn, [2024] SSRN · DOI: 10.2139/ssrn.4970576 · EID: 2-s2.0-85205778895 · ISSN: 1556-5068
"Diffusional Creep Model in Uo2 Informed by Lower-Length Scale Simulations" Anders David Ragnar Andersson, Ryan Sweet, Laurent Capolungo, Michael William Donald Cooper, Conor Galvin, [2024] SSRN · DOI: 10.2139/ssrn.4808180 · EID: 2-s2.0-85192080223 · ISSN: 1556-5068
"Improved simulation of UO2 fuel creep deformation in LWR fuel elements" [2024] Transactions of the American Nuclear Society · DOI: 10.13182/t130-44902 · EID: 2-s2.0-85205776904 · ISSN: 0003-018X
"Uranium-zirconium hydride nuclear fuel performance in the NaK-cooled MARVEL microreactor" Ryan T. Sweet, Pavel G. Medvedev, Adrian R. Wagner, Carlo Parisi, Travis L. Lange, Emmanuel Perez, Francine Rice, Jan-Fong Jue, Eric Woolstenhulme, Dennis D. Keiser, Yasir Arafat, Jordan A. Evans, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155145 · EID: 2-s2.0-85192860631 · ISSN: 0022-3115
"Analysis of FeCrAl cladding performance under loss-of-coolant accident conditions" G. Pastore, B.D. Wirth, R.T. Sweet, [2023] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2023.112556 · EID: 2-s2.0-85169786594 · ISSN: 0029-5493
"Assessing UN Neutronic and Fuel Performance for Extended Cycle Lengths" [2023] Transactions of the American Nuclear Society · DOI: 10.13182/t128-41557 · EID: 2-s2.0-85180628675 · ISSN: 0003-018X
"Coupled Neutronics, Thermal Hydraulics, and Fuel Performance Simulations of a Natural Circulation Based SMR" [2023] Transactions of the American Nuclear Society · DOI: 10.13182/t128-42179 · EID: 2-s2.0-85180628994 · ISSN: 0003-018X
"Fuel performance evaluation of two high burnup PWR core designs during normal operation, control rod withdrawal, and control rod ejection scenarios" Mason Fox, Ryan T. Sweet, Nathan Capps, Nicholas R. Brown, Isabelle O. Lindsay, [2023] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2023.112730 · EID: 2-s2.0-85176228460 · ISSN: 0029-5493
"Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding" Kenneth A. Kane, Ryan T. Sweet, Samuel B. Bell, Sebastien N. Dryepondt, James Burns, Andrew T. Nelson, Caleb P. Massey, [2023] Materials and Design · DOI: 10.1016/j.matdes.2023.112307 · EID: 2-s2.0-85171421044 · ISSN: 1873-4197
"Model for determining rupture area in Zircaloy cladding under LOCA conditions" Ryan Sweet, Nathan Capps, [2023] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2022.112096 · EID: 2-s2.0-85143656748 · ISSN: 0029-5493
"Pressurized Water Reactor Control Rod Ejection Analysis Using PARCS, RELAP5-3D, and BISON for High Burnup Fuel" [2023] Transactions of the American Nuclear Society · DOI: 10.13182/t128-42044 · EID: 2-s2.0-85180631078 · ISSN: 0003-018X
"Sensitivity of UO2 fuel performance to microstructural evolutions driven by dilute additives" Ryan T. Sweet, Andrew T. Nelson, Brandon A. Wilson, Ashley E. Shields, Amani Cheniour, [2023] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2023.112383 · EID: 2-s2.0-85162234989 · ISSN: 0029-5493
"Chromium-coated cladding analysis under simulated LOCA burst conditions" Peter Mouche, Samuel Bell, Kenneth Kane, Nathan Capps, Ryan Sweet, [2022] Annals of Nuclear Energy · DOI: 10.1016/j.anucene.2022.109275 · ISSN: 0306-4549
"Accelerated Fuel Qualification: BISON Validation to In-Situ Cladding Burst Test" Ryan Sweet, Kenneth Kane, Samuel Bell, Nathan Capps, [2022] Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference · DOI: 10.13182/topfuel22-38880 · EID: 2-s2.0-85184958817
"Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications" Ryan Sweet, Nathan Capps, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153621 · EID: 2-s2.0-85125433120 · ISSN: 0022-3115
"Fuel Performance Analysis of Chromium-Coated Cladding Under Burst Conditions" Ryan Sweet, Peter Mouche, Sam Bell, Kenneth Kane, Nathan Capps, [2022] SSRN · DOI: 10.2139/ssrn.4102499 · EID: 2-s2.0-85176978758 · ISSN: 1556-5068
"In-situ thermomechanical measurements during burst testing of Zr claddings using digital image correlation and infrared thermography techniques" Benton Garrison, Ryan Sweet, Mackenzie Ridley, Kenneth Kane, Nathan Capps, Samuel Bell, [2022] Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference · DOI: 10.13182/topfuel22-38896 · EID: 2-s2.0-85184961077
"Metallic Fuel Performance Benchmarks for Versatile Test Reactor Applications" Jeffrey J. Powers, Ian Greenquist, Ryan T. Sweet, Jianwei Hu, Douglas L. Porter, Douglas C. Crawford, Jacob A. Hirschhorn, [2022] Nuclear Science and Engineering · DOI: 10.1080/00295639.2022.2043539 · EID: 2-s2.0-85127177731 · ISSN: 1943-748X
"Model for Determining Rupture Area in Zircaloy Cladding Under Loca" Ryan Sweet, Nathan Capps, [2022] SSRN · DOI: 10.2139/ssrn.4103228 · EID: 2-s2.0-85178528056 · ISSN: 1556-5068
"On the Role of Microstructure on the Burst Properties of Oxide Dispersion Strengthened FeCrAl Alloys During Simulated Loss-of-Coolant Accident Conditions" Kenneth Kane, Ryan Sweet, Samuel Bell, Andrew Nelson, Caleb Massey, [2022] Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference · DOI: 10.13182/topfuel22-38992 · EID: 2-s2.0-85153574153
"Wrought FeCrAl alloy (C26M) cladding behavior during burst experiments and performance under LOCA conditions" C.P. Massey, S.B. Bell, K.A. Kane, R.T. Sweet, [2022] Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference · DOI: 10.13182/topfuel22-39008 · EID: 2-s2.0-85184963457
"Full core LOCA safety analysis for a PWR containing high burnup fuel" Aaron Wysocki, Andrew Godfrey, Benjamin Collins, Ryan Sweet, Nicholas Brown, Soon Lee, Nicholas Szewczyk, Susan Hoxie-Key, Nathan Capps, [2021] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2021.111194 · EID: 2-s2.0-85103590143 · ISSN: 0029-5493
"High-burnup fuel stress analysis prior to and during a LOCA transient" Ryan Sweet, Jason Harp, Christian M. Petrie, Nathan Capps, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153194 · EID: 2-s2.0-85111066307 · ISSN: 0022-3115
"Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient" Ryan Sweet, Brian D. Wirth, Andrew Nelson, Kurt Terrani, Nathan Capps, [2020] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2020.110744 · EID: 2-s2.0-85087273656 · ISSN: 0029-5493
"Fuel performance analysis of uranium silicide fuel for LWRs during cladding failure" [2020] GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference · EID: 2-s2.0-85081082103
"Performance of U3Si2 in an LWR following a cladding breach during normal operation" Y. Yang, K.A. Terrani, B.D. Wirth, A.T. Nelson, R.T. Sweet, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152263 · EID: 2-s2.0-85087328157 · ISSN: 0022-3115
"Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors" Ryan T. Sweet, Jeffrey J. Powers, Andrew Worrall, Kurt A. Terrani, Brian D. Wirth, G. Ivan Maldonado, Nathan M. George, [2019] Annals of Nuclear Energy · DOI: 10.1016/j.anucene.2019.04.025 · EID: 2-s2.0-85065524473 · ISSN: 1873-2100
"Fuel performance analysis of iron-chromium-aluminum cladding under simulated loss-of-coolant conditions" [2018] Transactions of the American Nuclear Society · EID: 2-s2.0-85062948445 · ISSN: 0003-018X
"Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation" N.M. George, G.I. Maldonado, K.A. Terrani, B.D. Wirth, R.T. Sweet, [2018] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2017.11.043 · EID: 2-s2.0-85039797201 · ISSN: 0029-5493
"Parametric Evaluation of SiC/SiC Composite Cladding with UO2 Fuel for LWR Applications: Fuel Rod Interactions and Impact of Nonuniform Power Profile in Fuel Rod" R. Sweet, N.R. Brown, B.D. Wirth, Y. Katoh, K. Terrani, G. Singh, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.10.059 · EID: 2-s2.0-85034818547 · ISSN: 0022-3115
"Parametric analysis of single fecral rod and assembly within a full core PWR environment" [2018] International Conference on Physics of Reactors, PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems · EID: 2-s2.0-85106000361
"Fuel performance analysis of FeCrAl cladding during LWR operation" [2016] Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance · EID: 2-s2.0-85019016359
"Fuel performance simulation of iron-chrome-aluminum cladding during steady-state LWR operation" [2016] Transactions of the American Nuclear Society · EID: 2-s2.0-85117914511 · ISSN: 0003-018X
"In-pile creep and swelling of fecral alloys and impact on fuel pin behavior" [2016] International Congress on Advances in Nuclear Power Plants, ICAPP 2016 · EID: 2-s2.0-84986237880
"Fuel performance calculations for FeCrAl cladding in BWRs" [2015] Transactions of the American Nuclear Society · EID: 2-s2.0-85019028366 · ISSN: 0003-018X
Source: ORCID/CrossRef using DOI

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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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