Journal Articles
[TEA=Techno-Economic Analysis, FT=Fusion Technology, RA=Reactor Design & Analysis, O=Other]
[RA,FT] Matthew Nyberg, Joseph Eickman, Una Baker, Patrick Shriwise, Ben Lindley. An open source multiphysics workflow for the analysis of subcritical transmutation systems. Annals of Nuclear Energy Volume 229, May 2026, 112072. https://doi.org/10.1016/j.anucene.2025.112072
[TEA] Aidan Rigby, Ryan Spangler, Daniel Mikkelson, Michael Wagner, Ben Lindley. An Analysis of Physics Limited Dispatch of Nuclear Renewable Integrated Energy Systems using Deep Reinforcement Learning and Dynamic Modeling. Progress in Nuclear Energy, Vol. 191, 2026, 106085 https://doi.org/10.1016/j.pnucene.2025.106085
[RA] Ethan Fowler, Ryan Stewart, Paolo Balestra, Benjamin Lindley, Gerhard Strydom. Parameter study of the running-in process for the Generic Pebble Bed Reactor (GPBR-200), Annals of Nuclear Energy, Volume 225, 2026, 111719, ISSN 0306-4549, https://doi.org/10.1016/j.anucene.2025.111719.
[RA,FT] Matthew J. Nyberg, Paul P.H. Wilson, Ben A. Lindley, Neutronics behavior of molten salt dissolved fuel subcritical minor actinide transmutation systems, Progress in Nuclear Energy, Volume 192, 2026, 106146, ISSN 0149-1970, https://doi.org/10.1016/j.pnucene.2025.106146.
[RA] Mohammad Amer Allaf, Grace Ejnik, Emile Zaccomer, Woohyun Jung, Micheal Corradini, Juliana Pacheco Duarte. “Transient Behavior of the NuScale 250-MW(thermal) Power Module with Cr-Coated Zr Cladding During a Severe Accident”, Nuclear Technology, 1–14. 2025, https://doi.org/10.1080/00295450.2025.2503034.
[RA] Mohammad Amer Allaf, Grace Ejnik, Emile Zaccomer, Woohyun Jung, Micheal Corradini, Juliana Pacheco Duarte, “Investigating the Role of Chromium-Coated Clad During Accident Progression for an SMR Using MELCOR”, Nuclear Technology, 1–19, 2025, https://doi.org/10.1080/00295450.2025.2505808.
[RA] Selokar, U.; Lattimer, B.Y.; Salvi, U.; Sahin, E.; Allaf, M.A.; Duarte, J.P. “Quantifying the Influence of Parameters on Heat Release Rate in Electrical Cabinet Fires”, Fire 2025, 8, 256. https://doi.org/10.3390/fire8070256.
[O] Mohammad Amer Allaf, Koji Okamoto, Takuto Owa; “Using high speed visualization to identify variations in the formation and distribution of plasmonic microbubbles”, AIP Advances 1 June 2025; 15 (6): 065109. https://doi.org/10.1063/5.0272623.
[O] Mohammad Amer Allaf, Koji Okamoto, Takuto Owa, “Multi-Microseconds Microbubbles Induced by Nanoseconds Pulsed-Laser Heating of Gold Nano-Particles”, ACS Omega, (2025). 10.1021/acsomega.4c10328. https://doi.org/10.1021/acsomega.4c10328.
[RA] Elvan Sahin, Peter Henkes, Bruno P. Serrao, Mohammad Amer Allaf, Brian Lattimer, Juliana Pacheco Duarte, “Development of HRR Distributions in Electrical Enclosure Fire Scenario Through Machine Learning”, Fire Technology, (2025), https://doi.org/10.1007/s10694-025-01706-0.
[RA] Khaldoon Al-Dawood, Botros Hanna, Sai P. Balla, Rodrigo de Oliveira, Sam Garcia, Dan McCarthy, Chandu Bolisetti, Ben Lindley, Abdalla Abou-Jaoude, Nuclear Engineering and Design, (2025). https://doi.org/10.1016/j.nucengdes.2025.114210
[RA] Dylan J.L. Garofalo, Ben Lindley (2025). Multi-cycle reload analysis of a long cycle gas-cooled fast modular reactor. Nuclear Engineering and Design. https://doi.org/10.1016/j.nucengdes.2025.114362
[RA] Naupa I, Garcia S, Lindley B, Terlizzi S, Kotlyar D Validation and Verification of Serpent-Griffin Computational Sequence using the SNAP 8 Experimental Reactor Dry Experiments. Nuclear Science and Engineering, 1–17 https://doi-org/10.1080/00295639.2025.2483071
[TEA] Rigby A C G, Wagner M J, Mikkelson D, Lindley B (2025). A Reinforcement Learning Approach to Augment Conventional PID Control in Nuclear Power Plant Transient Operation, Nuclear Technology 1-19 https://doi.org/ 10.1080/00295450.2025.2466137
[TEA] Rigby A C G, Alhadhrami S, Lindley B (2024). Co-optimization of Nuclear Reactor Flexible Power Operation and Maintenance Scheduling, Energy 313 134098 https://doi.org/10.1016/j.energy.2024.134098
[TEA] Raymond C, Omitaomu O, Franzese K, Wagner M J, Lindley B (2024). Siting Analysis of a Solar-Nuclear-Desalination Integrated Energy System’, Journal of Nuclear Engineering 2024, 5(3), 402-419; https://doi.org/10.3390/jne5030025
[TEA] Keith E, Lindley B, Wagner M J (2024). ‘Optimized Dispatch and Component Sizing for a Nuclear – Multi-Effect Distillation Integrated Energy System Using Thermal Energy Storage’ Optimization and Engineerin https://link.springer.com/article/10.1007/s11081-024-09920-5
[TEA] Rigby A, Wagner M J, Lindley B (2024). ‘Dynamic modelling of flexible dispatch in a novel nuclear-solar integrated energy system with thermal energy storage’ Annals of Nuclear Energy 204 110534. https://doi.org/10.1016/j.anucene.2024.110534
[RA] Elvan Sahin, Brian Lattimer, Mohammad Amer Allaf, Juliana Pacheco Duarte, “Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks”, Journal of Nuclear Science and Technology, 1–14, (2024). https://doi.org/10.1080/00223131.2024.2310564.
[TEA] Soto G J, Wagner M J, Neises T W, Lindley B (2024) ‘Performance Analysis of Integrated Nuclear-Solar Energy System Sharing Same Molten Salt Thermal Energy Storage’ Progress in Nuclear Energy, Volume 171, June 2024, 105166 https://doi.org/10.1016/j.pnucene.2024.105166
[RA] Baker U, Choi Y-J, Rollins N, Nguyen K, Jung W, Whitmeyer A, Hou J, Lindley B, (2024) ‘Source Term Analysis of FeCrAl Accident Tolerant Fuel using MELCOR’ Annals of Nuclear Energy, Volume 202, July 2024, 110482 https://doi.org/10.1016/j.anucene.2024.110482
[TEA] Dailey R, Lindley B (2024). Locational Variance in Nuclear Microreactor Performance Under Net Zero Microgrid Conditions. Nuclear Science and Engineering Special Issue on Microreactor Challenges, August 2024, 295639 https://doi.org/10.1080/00295639.2024.2372512
[TEA] Rigby A C, Baker U, Lindley B, Wagner M (2024) Generation and validation of comprehensive synthetic weather histories using auto-regressive moving-average models. Renewable Energy Volume 224, April 2024, 120157 https://doi.org/10.1016/j.renene.2024.120157
[RA] Garcia S, Naupa I, Paleen O, Fowler E, Boyd A, Kotlyar D, Lindley B (2024). Reproducible Benchmark for the SNAP 8 Experimental Reactor at Dry Conditions. Annals of Nuclear Energy Volume 198, April 2024, 110331 https://doi.org/10.1016/j.anucene.2023.110331
[RA] Lindley B (2024). Irregular, Backward-compatible PWR Assemblies with More Pins to Facilitate Uprates. Nuclear Technology. https://doi.org/10.1080/00295450.2023.2295164
[FT] Forest C, Anderson J, Endrizzi D, Egedal J, Frank S, Furlong K, Ialovega M, Kirch J, Harvey R, Lindley B, Petrov Y, Pizzo J, Qian T, Sanwalka K, Schmitz O, Wallace J, Yakovlev D, Yu M (2023). Prospects for a high-field, compact Break Even Axisymmetric Mirror (BEAM) and applications. Journal of Plasma Physics. Volume 90 , Issue 1 , February 2024 , 975900101 DOI: https://doi.org/10.1017/S0022377823001290
[RA] Peakman A, Lindley B (2023) A review of nuclear electric fission space reactor technologies for achieving high-power output and operating with HALEU fuel. Progress in Nuclear Energy 163 104815 https://doi.org/10.1016/j.pnucene.2023.104815
[TEA] Alhadhrami S, Soto G J, Lindley B (2023). Dispatch analysis of flexible power operation with multi-unit small modular reactors. Energy 128107 https://doi.org/10.1016/j.energy.2023.128107
[RA,TEA] Baker U, Garrouste M, Choi S, Snuggerud R, Soto G J, Kochunas B, Lindley B (2023) ‘Simulation of the NuScale SMR and Investigation of the Effect of Load-following on Component Lifetimes’ Nuclear Technology https://doi.org/10.1080/00295450.2023.2216973
[FT] Bohm T, Lindley B (2023). Initial Neutronics Investigation of a Chlorine Salt Based Breeder Blanket. Fusion Science and Technology https://doi.org/10.1080/15361055.2022.2136923
[FT,TEA] Lindley B, Roulstone T, Locatelli G, Rooney M (2023). Can fusion energy be cost-competitive and commercially viable? An analysis of magnetically confined reactors. Energy Policy 177 113511 https://doi.org/10.1016/j.enpol.2023.113511
[RA,FT] Ruegsegger J, Moreno C, Nyberg M, Bohm T, Wilson P, Lindley B (2023). Scoping Studies of a Lead Lithium Cooled, Minor Actinide Burning Fission Fusion Hybrid Reactor Design. Nuclear Science and Engineering, 2023. https://doi.org/10.1080/00295639.2022.2154118
[TEA] Rigby A, Lindley B, Cullen J, 2023 An exergy based assessment of the efficiency of nuclear fuel cycles. Energy, Volume 264.
[RA] Lindley B A, Alvarez Velarde F, Bodi J, Charles A, Fiorina C, Fridman E, Krepel J, Lavarenne J, Mikityuk K, Nikitin E, Ponomarev A, Radman S, Shwageraus E, Tollit B. Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European SFR Core Power Distribution. ASME Journal of Nuclear Engineering and Radiation Science, 2023. ASME J of Nuclear Rad Sci. 1-39 NERS-22-1119 https://doi.org/10.1115/1.4056930
[TEA] Soto G J, Lindley B, Neises T, Stansbury C, Wagner M J, 2022. Dispatch Optimization, System Design and Cost Benefit Analysis of a Nuclear Reactor with Molten Salt Thermal Storage. Energies 2022, 15(10), 3599;
[RA,TEA] Lindley B, Wilkinson P, Couet A, Shahrokhi F, 2022. Telescopic Control Rod for Significant Reduction in HTR Height and Cost, Annals of Nuclear Energy 169 108953.Accepted Version Here
[TEA] White B T, Wagner M J, Neises T, Stansbury C, Lindley B, 2021. Modeling of Combined Lead Fast Reactor and Concentrating Solar Power Supercritical Carbon Dioxide Cycles to Demonstrate Feasibility, Efficiency Gains, and Cost Reductions. Sustainability 2021 13(22)
Theses
[MS=Masters, PhD=Doctorate]
[PhD] Nyberg M, 2025. Development of a Chloride Salt Fission-Fusion Hybrid System for the Transmutation of Minor Actinide Waste.
[PhD] Dailey R, 2025. Technoeconomic Design Optimization of Pool-Type Fast Reactors Based on Deployment Scenario.
[PhD] Rigby A, 2025. Design, Control, and Economic Dispatch of a Nuclear-Solar Integrated Energy System.
[MS] Garofalo D, 2025. Deterministic Methods Analysis of a Gas-Cooled Intermediate-Fast Spectrum Reactor.
[MS] Welker L, 2024. Investigating Integrated Project Delivery as a Strategy to Improve Nuclear Power Plant Construction Performance.
[MS] Jung SK, 2024. Identification of Key Safety Design Parameters in the FMR Design Using MELCOR.
[MS] Eickman J, 2023. Multiphysics analysis of a minor actinide burning molten salt reactor.
[MS] Prado I, 2023. Economic and industry considerations for open souce nuclear development.
[MS] Alhadhrami S, 2022. Techno-economic analysis of flexible power operation with multi-unit Small Modular Reactors.
[MS] Ruegsegger J, 2022. Scoping studies for a lead-lithium cooled, minor-actinide burning fission fusion hybrid reactor design.
Conference Papers
[TEA=Techno-Economic Analysis, FT=Fusion Technology, RA=Reactor Design & Analysis, O=Other]
[RA] Nisa, Rahnuma Aziz, Garofalo, D. J., Jung, S. K., Kreuger, D., Moon, J. H., Foley, S. J.,; Lindley, B. (2025). Investigating the neutronic potential of control rod materials for improved accident tolerance using SCALE 6.3.1. Transactions of the American Nuclear Society, 132(1), 954–957. https://doi.org/10.13182/T140-48086
[RA] Chang Hyun Song, Sung Joong Kim, Mohammad Amer Allaf, Koroush Shirvan, “Feasibility Assessment of Uprating the NuScale SMR to 420 MW Using MELCOR”, 2025 ANS Winter Conference and Expo, November 9-12, Washington, DC.
[RA] Samuel Garcia, Mohammad Amer Allaf, Isaac Naupa, Lewis Gross, Dan Kotlyar, Ben Lindley, “Multiphysics framework comparison for a liquid metal microreactor”, 2025 ANS Annual Conference, June 15-18, Chicago, IL.
[TEA] Kochunas B M, Shen Q, Coble J B, Lindley B. Demonstration of Methodology for Advanced Autonomous Control in Flexible Power Operation of Multi-Unit SMRs. Nuclear Plant Instrumentation and Control & Human Machine Interface Technology NPIC & HMIT 2025.
[TEA] Ollennu E N, Lindley B, Guaita N, Qin S. Open Architecture of Cost Savings in Advanced Nuclear Reactors. 2025 ANS Annual Conference. Jun 15-18, Chicago IL.
[TEA] Biwalkar R M, Talabi S, Lindley B. Regimes of Applicability for Nuclear Reactor Cost Estimation Methodologies. 2025 ANS Annual Conference. Jun 15-18, Chicago IL.
[RA] Charles Erickson, Mohammad Amer Allaf, Juliana Pacheco Duarte, “Impact of Chromium-Coated Cladding and Power Uprates on a BWR Station Blackout”, 2025 ANS Annual Conference, June 15-18, Chicago, IL.
[RA] Jung S K, Jentz I, Jung W H, Lindley B, Anderson M, Corradini M, Choi H, Bolin J. Reactor Vessel Cooling System for the GA-EMS Fast Modular Reactor: Scaled Experiments and Analysis. Advances in Thermal Hydraulics 2024, Nov 17-21, Orlando, FL
[RA] Garofalo D, Lindley B. Comparison of Neutronics Modelling Methods for the Fast Modular Reactor. ANS Winter Conference 2024, Nov 17-21, Orlando, FL
[TEA] Bacarro K M, Anderson M, Mastropasqua L, Qin M, Wagner M, Lindley B. Comparison of multi-effect distillation and reverse osmosis for nuclear-coupled ZLD seawater desalination. ANS Winter Conference 2024, Nov 17-21, Orlando, FL
[RA] Jung S K, Jung W H, Corradini M, Lindley B, Bolin JEI, Choi HEI, 2024. Sensitivity Analysis of Depressurized Loss of Forced Cooling of Gas-cooled Fast Modular Reactor using MELCOR. ANS Annual Conference 2024, Las Vegas, NV Jun 16-19 2024
[RA] Garcia S, Bays S E, Lindley B, 2024. Generic Sodium-Potassium-Cooled Thermal Microreactor Reference Design with Sizing-Burnup Tradeoff Study. International Conference in Advances in Nuclear Power Plants (ICAPP 2024, Las Vegas, NV Jun 16-19, 2024.
[TEA] Lindley B, Lamb D, Roulstone T, Prado ILG, Becker TEF, Guaita NES, Qin SES, Foss A WES, Woodhouse IEI, Ingersoll EEI, 2024. Options for Achieving Cost Reduction in Advanced Reactors through Open Architecture. International Conference in Advances in Nuclear Power Plants (ICAPP 2024 Las Vegas, NV Jun 16-19, 2024.
[TEA] Rigby A C, Wagner M J, Mikkelson D, Lindley B, 2024. Physics Constrained Reinforcement Learning for Improved Control of Transient Maneuvers in Nuclear Power Plants. International Conference in Advances in Nuclear Power Plants (ICAPP 2024), Las Vegas, NV Jun 16-19, 2024.
[RA,FT] Nyberg M J, Eickman J T, Shriwise P, Lindley B, 2024. An Open Source Multiphysics Workflow for the Analysis of Fusion Driven Systems. Physics of Reactors (PHYSOR) 2024, Apr 21-24, 2024
[RA] Eickman J, Nyberg M J, Baker U, Lindley B, 2024. Multiphysics Analysis of a Minor Actinide Burning Molten Salt Reactor. Physics of Reactors (PHYSOR) 2024, Apr 21-24, 2024. San Francisco, CA.
[RA] Fowler E P, Paramucchio G, Couet A, Lindley B, 2024. Integral Worth of Telescopic Control Rods in a Pebble Bed Reactor Model. Physics of Reactors (PHYSOR) 2024, Apr 21-24, 2024. San Francisco, CA.
[RA] Gross L I, Shriwise P, Lindley B, Wilson P P H, 2024. Exploring Effects of Homogenization on an OpenMC Depletion Analysis of a TRISO Fueled, Helium Cooled Microreactor. Physics of Reactors (PHYSOR) 2024, Apr 21-24, 2024. San Francisco, CA.
[RA] Mohammad Amer Allaf, Grace Ejnik, Emile Zaccomer, Woohyun Jung, Micheal Corradini, Juliana Pacheco Duarte, “The Fuel-Clad Transient Behavior of Uprated NuScale Using MELCOR”, 2024 ANS Winter Conference and Expo, November 17-21, Orlando, FL.
[RA] Joon Hyuck Moon, Mohammad Amer Allaf, Juliana Pacheco Duarte, “Investigating Post-CHF Heat Transfer Behavior during Dryout/Rewet Cycles”, The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety, August 25-28, 2024, Vancouver, Canada.
[RA] Mohammad Amer Allaf, Grace Ejnik, WooHyun Jung, Micheal Corradini, Koroush Shirvan, Juliana Pacheco Duarte, “Oxidation model of the Accident Tolerant Fuel implemented in NuScale Reactor using MELCOR Code”, ARS-2024 ANS Annual Conference, June 16–19, 2024, Las Vegas, NV.
[RA] Gabriel Dengler-Jeanblanc, WooHyun Jung, Michael Corradini, Benjamin Lindley, “Simulating Radionuclide Retention Experiment in Liquid Sodium Pools Using MELCOR Code”, ARS-2024 ANS Annual Conference, June 16–19, 2024, Las Vegas, NV.
[RA,TEA]Keith E, Lindley B, Wagner M J. Thermodynamic and Technoeconomic Analysis of Desalination with Thermal Energy Storage. ANS Winter Meeting 2023, Nov 12-15, 2023. Washington, DC
[RA] Naupa Aguirre I E, Garcia S, Terlizzi S, Abou-Jaoude A, Lindley B, Kotlyar D. Verification of the Serpent-Griffin Workflow using the SNAP 8 Experimental Reactor. M&C 2023, Niagara Falls, Ontario, Canada, Aug 13-17, 2023
[RA] Alhadhrami S, Prescott S, Agarwal V, Lindley B. Small Modular Reactor Condensate and Feedwater System Maintenance Methods by Utilizing Event Modeling Risk Assessment using Linked Diagram. NPIC&HMIT 2023, July 15-20 2023, Knoxville TN.
[RA] Garcia S, Naupa Aguirre I E, Boyd A, Paleen O, Kotlyar D, Lindley B Detailed Reflector and Drum Modeling of the SNAP8 Criticality Configuration Experiments Using Serpent with ENDF/B-VII.1 and ENDF/B-VIII.0 Libraries. 2023 ANS Annual Meeting June 11-15, 2023
[RA,TEA,FT] Nyberg M, Eickman J, Baker U, Lindley B. Minor Actinide Fueled Chloride Salt Reactor: Economics, Neutronics, and Safety. 2023 ANS Annual Meeting June 11-15, 2023
[RA,TEA] Dailey R, Beckman C, Moneghan D, Lindley B. Feasibility of a Used Nuclear Fuel District Energy System. ANS 2023 Dailey. 2023 ANS Annual Meeting June 11-15, 2023
[RA,TEA] Dailey R, Lindley B. Review of District Energy Technology for Nuclear Power Applications. 2023 ANS Annual Meeting June 11-15, 2023
[RA,TEA] Rigby A C, Lindley B, Mikkelson D. Transient Modelling of HTGR Thermal Load Follow in Modelica. 2023 ANS Annual Meeting June 11-15, 2023
[RA] Baker U, Lindley B, Nguyen K, Hou J, Choi Y-J. Analysis of Accident Tolerant Fuel Design in Light Water Reactors. 2023 ANS Annual Meeting June 11-15, 2023
[RA,TEA] Alhadhrami S, Soto G J, Lindley B. Economic Dispatch Optimization of Multi-Unit SMR Site. ANS Winter Meeting 2022, Nov 13-17, 2022. Phoenix, AZ.
[RA] Garcia S, Naupa Aguirre I E, Boyd A, Paleen O, Kotlyar D, Lindley B. Validation of SNAP8. Criticality Configuration Experiments using SERPENT. ANS Winter Meeting 2022, Nov 13-17, 2022. Phoenix, AZ.
[TEA] Lindley B, Dailey R. Review and Comparison of Existing District Heating Reactor Concepts. ANS Winter Meeting 2022, Nov 13-17, 2022. Phoenix, AZ.
[RA] Baker U, Lindley B. Performance Evaluation of Accident Tolerant Fuel in Recovered LOCA following ECCS Failure. ANS Winter Meeting 2022, Nov 13-17, 2022. Phoenix, AZ.
[RA,TEA] Dailey R, Lindley B. Locational Variance in Nuclear Micro-Reactor Performance Under Microgrid Conditions. ANS 2022 Annual Meeting. June 12-16, Anaheim, CA.
[RA,FT] Ruegsegger J, Moreno C, Nyberg M, Bohm T, Wilson P, Lindley B. Scoping Studies of Subcritical Minor Actinide-Burning Fission-Fusion Hybrid Designs for Nuclear Waste Reduction. PHYSOR 2022, 15-20 May 2022, Pittsburgh, PA
[RA,TEA] Baker U, Garrouste M, Choi S, Soto G J, Lindley B, Kochunas B. Development of a High-fidelity Multi-cycle Model of the NuScale Small Modular Reactor using VERA. PHYSOR 2022, 15-20 May 2022, Pittsburgh, PA
[RA] Lindley B A, Alvarez Velarde F, Bodi J, Charles A, Di-Nora V, Fridman E, Krepel J, Lavarenne J, Mikityuk K, Nikitin E, Ponomarev A, Tollit B. Coupled Neutronic-Thermal-Hydraulic Simulations of the European SFR Core. PHYSOR 2022, 15-20 May 2022, Pittsburgh, PA
[RA,TEA] Soto G J, Baker U, White B, Lindley B, Wagner M, 2021. Modeling a Lead-Cooled Fast Reactor with Thermal Energy Storage using Optimal Dispatch and SAM. ANS Winter Meeting 2021