NSUF - Nuclear Science User Facilities

Jacob Gorton

Profile Information
Name
Dr. Jacob Gorton
Institution
Oak Ridge National Laboratory
Position
R&D Staff Member
h-Index
8
ORCID
0000-0002-6980-6083
Expertise
Fuel Performance
Additional Publications:
"Characterization of Fuel-to-Coolant Heat Transfer During Reactivity-Initiated Accidents Using Tightly Coupled Thermal Hydraulics and Fuel Thermomechanics" Jacob P. Gorton, Charles P. Folsom, Nicholas R. Brown, Mason A. Fox, [2025] Nuclear Technology · DOI: 10.1080/00295450.2025.2497108
"Swelling and Fission Gas Release of U-10Mo and U-17Mo Following Neutron Irradiation at 250 – 500°C" Jacob Gorton, Kara Godsey, Annabelle Le Coq, Jason Harp, Matthew Jones, Stephanie Curlin, Andrew Nelson, Peter Doyle, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2025.155851
"Identifying high-impact and high-uncertainty parameters in MiniFuel model predictions" Jacob P. Gorton, Nathan A. Capps, Nicholas R. Brown, Nicholas A. Meehan, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2025.155745
"Modeling and design of a separate effects irradiation test targeting fission gas release from Cr-doped UO2" Annabelle G. Le Coq, Zane G. Wallen, Christian M. Petrie, Joshua T. White, John T. Dunwoody, Shane Mann, Nathan A. Capps, Andrew T. Nelson, Jacob P. Gorton, [2024] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2024.113571
"ROADRUNNER MiniFuel Experiment: Irradiation Target Design and Sample Characterization" Adrian Schrell, Jose Salcedo Perez, Zain Karriem, Denise Adorno Lopes, Grant Helmreich, Zane Wallen, Jacob Gorton, Nathan Capps, Jason Harp, Kory Linton, Joshua T. White, Elizabeth Sooby, Annabelle Le Coq, [2024] · DOI: 10.2172/2441067
"Design and Assembly of MiniFuel Targets for Characterization of High Burnup UO2 Specimens Irradiated in the High Flux Isotope Reactor" Amber Telles, Andrew Kercher, Christopher Hobbs, Tash Ulrich, Jonathan Chappell, Jacob Gorton, Kara Godsey, Christian Petrie, Nathan Capps, Annabelle Le Coq, [2024] · DOI: 10.2172/2394725
"Heat transfer optimization of uo2-mo fuel using genetic algorithms" Joel L. McDuffee, Patrick L. Snarr, Christian M. Petrie, Andrew T. Nelson, Jacob P. Gorton, [2024] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2023.112861
"Heat transfer optimization of uo2-mo fuel using genetic algorithms" Joel L. McDuffee, Patrick L. Snarr, Christian M. Petrie, Andrew T. Nelson, Jacob P. Gorton, [2024] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2023.112861
"Accelerated Fuel Concept Screening via Neutronics and Thermal Hydraulics Modeling" [2024] Transactions of the American Nuclear Society · DOI: 10.13182/t130-44311 · EID: 2-s2.0-85205781954 · ISSN: 0003-018X
"Reactivity-initiated accidents in two pressurized water reactor high burnup core designs" Isabelle O. Lindsay, Jacob P. Gorton, Nicholas R. Brown, Mason A. Fox, [2023] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2023.112745
"Differences In High Burnup Fuel Management Strategies to Minimize FFRD and Increase Economic Viability" William Gurecky, Dave Kropaczek, Nathan Capps, Jacob Gorton, [2023] · DOI: 10.2172/2006918
"A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification" Christian M. Petrie, Andrew T. Nelson, Jacob P. Gorton, [2023] Progress in Nuclear Energy · DOI: 10.1016/j.pnucene.2023.104737
"Design of a MiniFuel Irradiation Experiment to Study Fuel Performance Phenomena in Ceramic Fuels" [2023]
"Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification" Ryan C. Gallagher, Zane G. Wallen, Annabelle G. Le Coq, Grant W. Helmreich, Christian M. Petrie, Kory D. Linton, Ryan Latta, Tyler J. Gerczak, Jacob P. Gorton, [2023] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2023.112177
"Sensitivity Analysis of TRISO Fuel Configuration in a MiniFuel Irradiation Experiment" [2022]
"Thermal Optimization of UO2-Mo Fuel Using Sensitivity Analysis and Genetic Algorithms" Daniel Schappel, Joel McDuffee, Christian Petrie, Andrew Nelson, Jacob Gorton, [2022] · DOI: 10.13182/topfuel22-38980
"Irradiation of MiniFuel Targets Bearing TRISO Fuel Compacts (Status Report)" Jacob Gorton, Zane Wallen, Tyler Gerczak, Kory Linton, Annabelle Le Coq, [2022] · DOI: 10.2172/1874642
"MiniFuel Experimental Capability at Oak Ridge National Laboratory" [2022]
"Testing and Simulation of an Updated Cartridge Loop Vehicle" A. Chapel, David Felde, Daniel Sweeney, Joel McDuffee, Jacob Gorton, [2022] · DOI: 10.2172/1874649
"Simulation of natural circulation cartridge loop experiments and application to molten salt reactors" Daniel C. Sweeney, Christian M. Petrie, Joel L. McDuffee, Jacob P. Gorton, [2022] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2022.111767
"A Neutronics and Thermal Hydraulics–Based Approach for Accelerating the Screening and Qualification of Novel Nuclear Fuel Concepts☆" Christian Petrie, Andrew T. Nelson, Jacob P. Gorton, [2022] SSRN · DOI: 10.2139/ssrn.4082627 · EID: 2-s2.0-85178532673 · ISSN: 1556-5068
"Design and Control of a Fueled Molten Salt Cartridge Experiment for the Versatile Test Reactor" Rich Christensen, Daniel Eichel, Mike Simpson, Supathorn Phongikaroon, Xiaodong Sun, John Baird, Adam Burak, Shay Chapel, Joonhyung Choi, Jacob Gorton, D. Ethan Hamilton, Dimitris Killinger, Sam Miller, Jason Palmer, Christian Petrie, Daniel Sweeney, Adrian Schrell, James Vollmer, Joel McDuffee, [2022] Nuclear Science and Engineering · DOI: 10.1080/00295639.2021.2017663 · EID: 2-s2.0-85125303163 · ISSN: 1943-748X
"Pre-conceptual high temperature gas cooled microreactor design utilizing two-phase composite moderators. Part II: Design space and safety characteristics" Veronica Karriem, Khian Skidmore, Jacob P. Gorton, Lance L. Snead, Jason R. Trelewicz, Nicholas R. Brown, Edward M. Duchnowski, [2022] Progress in Nuclear Energy · DOI: 10.1016/j.pnucene.2022.104258 · EID: 2-s2.0-85130596908 · ISSN: 0149-1970
"Initial Design of High-Temperature MiniFuel Irradiation Experiments in the High Flux Isotope Reactor Removable Beryllium Region" [2021]
"Modifications to MiniFuel Vehicle Needed to Enable Higher Temperature UO2 Irradiation Capabilities (Summarizing Issue Report)" Zane Wallen, Christian Petrie, Jacob Gorton, [2021] · DOI: 10.2172/1814282
"Pre-conceptual design of a gas-cooled microreactor with two-phase composite moderators" [2021] Transactions of the American Nuclear Society · DOI: 10.13182/t124-35294 · EID: 2-s2.0-85117941993 · ISSN: 0003-018X
"Defining the performance envelope of reactivity-initiated accidents in a high-temperature gas-cooled reactor" Nicholas R. Brown, Jacob P. Gorton, [2020] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2020.110865
"Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety" Daniel Schappel, Andrew T. Nelson, Nicholas R. Brown, Jacob P. Gorton, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152492
"Assessment of CASL VERA for BWR analysis and application to accident tolerant SiC/SiC channel box" Benjamin S. Collins, Aaron J. Wysocki, Nicholas R. Brown, Jacob P. Gorton, [2020] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2020.110732
"Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT" Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen, John D. Bess, Jacob P. Gorton, Nicholas R. Brown, Richard Hernandez, [2020] Progress in Nuclear Energy · DOI: 10.1016/j.pnucene.2020.103303
"Impact of control blade insertion on the deformation behavior of SiC-SiC channel boxes in BWRs" J.P. Gorton, D. Schappel, B.S. Collins, Y. Katoh, N.R. Brown, B.D. Wirth, G. Singh, [2020] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2020.110621 · EID: 2-s2.0-85082688229 · ISSN: 0029-5493
"Impact of Control Blade Insertion on the Deformation Behavior of SiC-SiC Channel Boxes in Boiling Water Reactors" Jacob Gorton, Danny Schappel, Benjamin Collins, Nicholas Brown, Brian Wirth, Gyanender Singh, [2019] · DOI: 10.2172/1615808
"Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties" Soon K. Lee, Youho Lee, Nicholas R. Brown, Jacob P. Gorton, [2019] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2019.110295
"A demonstration of BWR coupled analysis and potential ATF applications using CASL's MPACT/CTF" [2019] Transactions of the American Nuclear Society · EID: 2-s2.0-85092202653 · ISSN: 0003-018X
"Deformation analysis of SiC-SiC channel box for BWR applications" J. Gorton, D. Schappel, N.R. Brown, Y. Katoh, B.D. Wirth, K.A. Terrani, G. Singh, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.10.045 · EID: 2-s2.0-85055997380 · ISSN: 0022-3115
"Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR" Benjamin S. Collins, Andrew T. Nelson, Nicholas R. Brown, Jacob P. Gorton, [2019] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2019.110317 · EID: 2-s2.0-85071521503 · ISSN: 0029-5493
"Sensitivity of critical heat flux for ATF FeCrAl alloy using RELAP5-3D and RAVEN" [2019] Transactions of the American Nuclear Society · EID: 2-s2.0-85092200394 · ISSN: 0003-018X
"Sensitivity studies of heater rod design for transient critical heat flux experiments in treat" [2019] 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 · EID: 2-s2.0-85073755258
"Preliminary Analysis of SiC BWR Channel Box Performance under Normal Operation" Gyanender Singh, Jacob Gorton, Daniel Schappel, N. Brown, Yutai Katoh, Kurt Terrani, Brian Wirth, [2018] · DOI: 10.2172/1439933
"Comparison of experimental and simulated low-pressure CHF tests using CTF and RELAP5-3D" [2018] International Topical Meeting on Advances in Thermal Hydraulics, ATH 2018 - Embedded Topical Meeting · EID: 2-s2.0-85060158555
"Evaluating accident tolerant fuel concepts in light water reactors using CASL CTF" [2018] Transactions of the American Nuclear Society · EID: 2-s2.0-85063011610 · ISSN: 0003-018X
"Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys" Jacob P. Gorton, Nicholas R. Brown, Kurt A. Terrani, Colby B. Jensen, Youho Lee, Edward D. Blandford, Amir F. Ali, [2018] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2018.08.024 · EID: 2-s2.0-85052324027 · ISSN: 0029-5493
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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