| Integral Experiment Request 554 CED-1 Summary Report M Dupont, WBJ Marshall, MT Pigni, D Ames, G Harms Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2022 | 13 | 2022 |
| Evaluation of temperature-dependent critical experiments at the Walthousen reactor critical facility for benchmark development MD Eklund, PJ Kowal, MN Dupont, W Ji Annals of Nuclear Energy 180, 109440, 2023 | 11 | 2023 |
| Development of critical experiments to provide validation data for multiphysics coupling codes MN Dupont, MD Eklund, PF Caracappa, W Ji Annals of Nuclear Energy 128, 256-267, 2019 | 11 | 2019 |
| SCALE 6.2. 4 Validation: Radiation Shielding C Celik, DE Peplow, MN Dupont, G Radulescu Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022 | 7 | 2022 |
| Criticality Accident Alarm System Shielding Benchmark: Integral Experiment Request 498, Critical Engineering Decision 2 Report R Cumberland, C Celik, M Dupont, DG Bowen Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2021 | 7 | 2021 |
| Development of critical experiments to benchmark moderator temperature reactivity worth M Dupont, MD Eklund, W Ji, PF Caracappa ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, 2016 | 6 | 2016 |
| Experimental measurements of isothermal reactivity coefficient and temperature-dependent reactivity changes with associated uncertainty evaluations MN Dupont, MD Eklund, PF Caracappa, W Ji Progress in Nuclear Energy 118, 103131, 2020 | 5 | 2020 |
| Validation studies for high burnup and extended enrichment fuels in burnup credit criticality safety analyses W Metwally, M Dupont, WJ Marshall, A Lang, V Karriem, C Celik, KL Reed, ... NUREG, prepared for the US Nuclear Regulatory Commission by Oak Ridge …, 2025 | 4 | 2025 |
| Proposed Subcritical Assembly for Nuclear Criticality Safety Training at the Oak Ridge National Laboratory DG Bowen, M Dupont, A Lang, AM Holcomb, S Hart Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022 | 4 | 2022 |
| KENO-VI Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS6) with Fulcrum KB Bekar, JB Clarity, M Dupont, RA Lefebvre, WBJ Marshall, EM Saylor Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 4 | 2020 |
| Unstructured mesh unification for MCNP6. 2 and PROTEUS in NEAMS workbench PJ Kowal, KA Dominesey, MN Dupont, JA Eugenio, W Ji Transactions of the American Nuclear Society 121, 1541-1544, 2019 | 4 | 2019 |
| Current State of Benchmark Applicability for Commercial-Scale HALEU Fuel Transport L Fassino, MN Dupont, I Al-Qasir, WA Wieselquist, WB Marshall ORNL/TM, ORNL, forthcoming, 2024 | 3 | 2024 |
| Current Progress of the Final Design of a Subcritical Assembly at the Oak Ridge National Laboratory MN Dupont, A Lang, DG Bowen Transactions of the American Nuclear Society 127 (1), 2022 | 3 | 2022 |
| Sulfur Pellets Responses to a Bare and Steel Reflected Pulse of the Oak Ridge National Laboratory Health Physics Research Reactor MN Dupont, EM Saylor Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 3 | 2020 |
| Neutronics modeling and simulation of temperature-dependent experiments performed at the walthousen reactor critical facility (RCF) using proteus-SN MD Eklund, M Dupont, PF Caracappa, W Ji, V Mahadevan 2018 International Conference on Physics of Reactors: Reactor Physics Paving …, 2018 | 3 | 2018 |
| Neutronics simulations of the RPI walthousen reactor critical facility (RCF) using proteus-SN MD Eklund, M Dupont, PF Caracappa, W Ji Transactions of the American Nuclear Society 117, 114-115, 2017 | 3 | 2017 |
| Computational modeling, simulation and analysis of the RPI walthousen reactor critical facility (RCF) MD Eklund, M Dupont, PF Caracappa, W Ji Transactions of the American Nuclear Society 115, 2016 | 3 | 2016 |
| Inversion Point of the Isothermal Reactivity Coefficient with Increasing System Temperature in a Heterogeneous Core Lattice of a Light Water Reactor MN Dupont, MD Eklund, PF Caracappa, W Ji Nuclear Science and Engineering 197 (11), 2884-2901, 2023 | 2 | 2023 |
| Horizontal Split-Table Conceptual Design to Support Advanced Reactor Validation Needs MN Dupont, DJ Siefman, JB Clarity, CM Percher Nuclear Science and Engineering 197 (8), 1972-1990, 2023 | 2 | 2023 |
| Evaluation of Oak Ridge National Laboratory Health Physics Research Reactor Operation Data for Criticality Accident Alarm System Benchmark Creation MN Dupont, C Celik Transactions of the American Nuclear Society 125 (1), 2021 | 2 | 2021 |
