| Three-dimensional moderator circulation experimental program for validation of CFD code MODTURC_CLAS HF Khartabil, WW Inch, J Szymanski, D Novog, V Tavasoli, J Mackinnon 21th CNS Nuclear Simulation Symposium, 2000 | 46 | 2000 |
| Radiation shielding properties of modified concrete mixes and their suitability in dry storage cask MG El-Samrah, MAA Zamora, DR Novog, SE Chidiac Progress in Nuclear Energy 148, 104195, 2022 | 31 | 2022 |
| A blind, numerical benchmark study on supercritical water heat transfer experiments in a 7-rod bundle M Rohde, JWR Peeters, A Pucciarelli, A Kiss, YF Rao, EN Onder, ... Journal of Nuclear Engineering and Radiation Science 2 (2), 021012, 2016 | 28 | 2016 |
| Coupled 3D neutron kinetics and thermalhydraulic characteristics of the Canadian supercritical water reactor DW Hummel, DR Novog Nuclear Engineering and Design 298, 78-89, 2016 | 25 | 2016 |
| Design and optimization of nanowire betavoltaic generators DL Wagner, DR Novog, RR LaPierre Journal of Applied Physics 127 (24), 2020 | 24 | 2020 |
| Assessment of new modeling in RELAPS/SCDAPSIM using experimental results from the Quench program JH Spencer, D Novog, JK Hohorst, CM Allison | 22 | 2011 |
| Analysis of implicit and explicit lattice sensitivities using DRAGON MR Ball, DR Novog, JC Luxat Nuclear Engineering and Design 265, 1-12, 2013 | 17 | 2013 |
| CFD study of convective heat transfer to carbon dioxide and water at supercritical pressures in vertical circular pipes F Zhou | 16 | 2014 |
| Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3. 6 code F Zhou, DR Novog Nuclear Engineering and Design 335, 71-93, 2018 | 15 | 2018 |
| RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators F Zhou, DR Novog Nuclear Engineering and Design 318, 35-53, 2017 | 15 | 2017 |
| Behavior of Transuranic Mixed-Oxide Fuel in a CANDU-900 Reactor AC Morreale, MR Ball, DR Novog, JC Luxat Nuclear Technology 183 (1), 30-44, 2013 | 15 | 2013 |
| Safety concepts and systems of the Canadian SCWR D Novog, G McGee, D Rhodes, M Yetisir The 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors …, 2012 | 15 | 2012 |
| Demonstration of combined reduced order model and deep neural network for emulation of a time-dependent reactor transient B Foad, R Elzohery, DR Novog Annals of Nuclear Energy 171, 109017, 2022 | 14 | 2022 |
| Determination of the optimal few-energy group structure for the Canadian Super Critical Water-cooled Reactor A Moghrabi, DR Novog Annals of Nuclear Energy 115, 27-38, 2018 | 14 | 2018 |
| A Benchmark Comparison of the Canadian Supercritical Water-Cooled Reactor (SCWR) 64-Element Fuel Lattice Cell Parameters Using Various Computer Codes J Sharpe, F Salaun, D Hummel, A Moghrabi, M Nowak, J Pencer, ... | 14 | 2015 |
| A strategy for intensive production of molybdenum-99 isotopes for nuclear medicine using CANDU reactors AC Morreale, DR Novog, JC Luxat Applied Radiation and Isotopes 70 (1), 20-34, 2012 | 14 | 2012 |
| Validation of fluent for prediction of flow distribution and pressure gradients in a multi-branch header under low flow conditions A Muhana, DR Novog International Conference on Nuclear Engineering 48159, 221-226, 2008 | 14 | 2008 |
| Development and benchmarking of mechanistic channel deformation models in RELAP/SCDAPSIM/MOD3. 6 for CANDU severe accident analysis F Zhou, DR Novog, LJ Siefken, CM Allison Nuclear Science and Engineering 190 (3), 209-237, 2018 | 13 | 2018 |
| Critical heat flux measurement and visualization in R-134a on a vertical single rod with and without mixing-vanes spacer: The characteristics and phenomenon of critical heat flux Y Liu, W Liu, J Shan, DR Novog, B Zhang, M Gui, J Guo Annals of Nuclear Energy 160, 108399, 2021 | 12 | 2021 |
| Measurement, simulation and uncertainty quantification of the neutron flux at the McMaster Nuclear Reactor EL MacConnachie, DR Novog Annals of Nuclear Energy 151, 107879, 2021 | 12 | 2021 |
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