| Reactor physics methods and analysis capabilities in SCALE MD DeHart, SM Bowman Nuclear Technology 174 (2), 196-213, 2011 | 131 | 2011 |
| NEWT: a new transport algorithm for two-dimensional discrete ordinates analysis in non-orthogonal geometries MD DeHart, MD Jessee ORNL/TM-2005/39, Oak Ridge National Laboratory, 2005 | 126 | 2005 |
| Triton: a two-dimensional transport and depletion module for characterization of spent nuclear fuel MD DeHart ORNL/TM-2005/39, Version 6, 2009 | 102 | 2009 |
| Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages JJ Lichtenwalter, SM Bowman, MD DeHart, CM Hopper Nuclear Regulatory Commission, Washington, DC (United States). Office of …, 1997 | 95 | 1997 |
| Sensitivity and parametric evaluations of significant aspects of burnup credit for PWR spent fuel packages MD DeHart Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 1993 | 90 | 1993 |
| Rattlesnake: A MOOSE-based multiphysics multischeme radiation transport application Y Wang, S Schunert, J Ortensi, V Laboure, M DeHart, Z Prince, F Kong, ... Nuclear Technology 207 (7), 1047-1072, 2021 | 83 | 2021 |
| OECD/NEA burnup credit calculational criticality benchmark phase IB results MD DeHart Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 1993 | 79 | 1993 |
| Coupled multiphysics simulations of heat pipe microreactors using DireWolf C Matthews, V Laboure, M DeHart, J Hansel, D Andrs, Y Wang, J Ortensi, ... Nuclear Technology 207 (7), 1142-1162, 2021 | 77 | 2021 |
| Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel CV Parks, MD DeHart, JC Wagner Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2000 | 68 | 2000 |
| Review of Axial Burnup Distribtion Considerations for Burnup Credit Calculations JC Wagner Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2000 | 64 | 2000 |
| Baseline Assessment of TREAT for Modeling and Analysis Needs JD Bess, MD DeHart Idaho National Lab.(INL), Idaho Falls, ID (United States), 2015 | 60 | 2015 |
| An extension of the validation of SCALE (SAS2H) isotopic predictions for PWR spent fuel MD DeHart Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 1993 | 60 | 1993 |
| TRITON: a multipurpose transport, depletion, and sensitivity and uncertainty analysis module MA Jessee, MD DeHart ORNL/TM-2005/39, Version 6, 2011 | 54 | 2011 |
| Burnable absorbers in nuclear reactors–a review JA Evans, MD DeHart, KD Weaver, DD Keiser Jr Nuclear Engineering and Design 391, 111726, 2022 | 51 | 2022 |
| A Newton solution for the Superhomogenization method: The PJFNK-SPH J Ortensi, Y Wang, A Laurier, S Schunert, A Hébert, M DeHart Annals of Nuclear Energy 111, 579-594, 2018 | 51 | 2018 |
| Design and assessment of a molten chloride fast reactor Z Mausolff, M DeHart, S Goluoglu Nuclear Engineering and Design 379, 111181, 2021 | 49 | 2021 |
| Validation of the SCALE Broad Structure 44-Group ENDF/BV Cross-Section Library for Use in Criticality Safety Analyses MD DeHart, SM Bowman US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div …, 1994 | 45 | 1994 |
| Implementation of two-level coarse-mesh finite difference acceleration in an arbitrary geometry, two-dimensional discrete ordinates transport method Z Zhong, TJ Downar, Y Xu, MD DeHart, KT Clarno Nuclear science and engineering 158 (3), 289-298, 2008 | 44 | 2008 |
| TRITON: a two-dimensional depletion sequence for characterization of spent nuclear fuel MD DeHart ORNL/TM-2005/39, Oak Ridge National Laboratory, 2005 | 44 | 2005 |
| Hybrid PN-SN with Lagrange multiplier and upwinding for the multiscale transport capability in Rattlesnake Y Wang, S Schunert, M DeHart, R Martineau, W Zheng Progress in Nuclear Energy 101, 381-393, 2017 | 39 | 2017 |
