Journal
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.
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, DOI:10.1080/00295450.2025.2505808.
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.
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.
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.
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), 10.1007/s10694-025-01706-0.
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.
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
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
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
Lindley B (2024). Irregular, Backward-compatible PWR Assemblies with More Pins to Facilitate Uprates. Nuclear Technology. https://doi.org/10.1080/00295450.2023.2295164
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
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
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
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
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
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
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
Rigby A, Lindley B, Cullen J, 2023 An exergy based assessment of the efficiency of nuclear fuel cycles. Energy, Volume 264.
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
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;
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
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)
Conference
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.
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.
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.
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.
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.
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.
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
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
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.
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
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
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
Dailey R, Lindley B. Review of District Energy Technology for Nuclear Power Applications. 2023 ANS Annual Meeting June 11-15, 2023
Rigby A C, Lindley B, Mikkelson D. Transient Modelling of HTGR Thermal Load Follow in Modelica. 2023 ANS Annual Meeting June 11-15, 2023
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
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.
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.
Lindley B, Dailey R. Review and Comparison of Existing District Heating Reactor Concepts. ANS Winter Meeting 2022, Nov 13-17, 2022. Phoenix, AZ.
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.
Dailey R, Lindley B. Locational Variance in Nuclear Micro-Reactor Performance Under Microgrid Conditions. ANS 2022 Annual Meeting. June 12-16, Anaheim, CA.
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
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
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
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
MS Theses
Eickman J, 2023. Multiphysics analysis of a minor actinide burning molten salt reactor.
Prado I, 2023. Economic and industry considerations for open souce nuclear development.
Alhadhrami S, 2022. Techno-economic analysis of flexible power operation with multi-unit Small Modular Reactors.
Ruegsegger J, 2022. Scoping studies for a lead-lithium cooled, minor-actinide burning fission fusion hybrid reactor design.