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David Novog
David Novog
Verified email at mcmaster.ca
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Year
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
462000
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
262016
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
202016
Design and optimization of nanowire betavoltaic generators
DL Wagner, DR Novog, RR LaPierre
Journal of Applied Physics 127 (24), 2020
192020
Assessment of new modeling in RELAPS/SCDAPSIM using experimental results from the Quench program
JH Spencer, D Novog, JK Hohorst, CM Allison
192011
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
162022
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
152017
Analysis of implicit and explicit lattice sensitivities using DRAGON
MR Ball, DR Novog, JC Luxat
Nuclear Engineering and Design 265, 1-12, 2013
152013
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
152013
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
142012
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
132018
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, ...
132015
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
132008
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
122021
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
112018
Evaluation of ASSERT-PV V3R1 against the PSBT Benchmark
KH Leung, DR Novog
Science and Technology of Nuclear Installations 2012, 2012
112012
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
112012
Monte Carlo computation of neutron overpower protection trip set-points using extreme value statistics
P Sermer, G Balog, D Novog, EA Attia, M Levine
112003
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
102022
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
92021
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