selected scholarly activity
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conferences
- Thermal Pyrolysis Of Used Tires: The Effect of Plasma Torch Power and Plasma Gases. Proceeding of Progress in Plasma Processing of Materials 1997. 403-410. 2023
- Implementation of Solar Salt as Fluid in ASYST4.1 and Validation for a Natural Circulation Loop. Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics. 2021
- PRELIMINARY RESULTS OF THE NEA FHR BENCHMARK PHASE I-A AND I-B (FUEL ELEMENT 2-D BENCHMARK). Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering M and C 2021. 1924-1933. 2021
- Comparison of the Subchannel Code CTF to Steady-State and Transient Heat Transfer Experiments at Intermediate Pressures in Water. Nuclear Technology. 364-376. 2019
- Important issues in validation of computational fluid dynamics codes against CFD grade experimental results. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Nureth 2019. 3978-3988. 2019
- Preliminary results on the development of a fast-neutron tomography system for void fraction distribution measurements. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Nureth 2019. 3989-4003. 2019
- Axial Flux Wire Measurements at the McMaster Nuclear Reactor. Volume 9: Student Paper Competition. V009T16A086-V009T16A086. 2018
- A review of CHF in tube bundles for future experiments. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Development of a time average candu-9 diffusion model using the PARCS diffusion code. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Fast neutron computed tomography early results. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Fast neutron computed tomography for phase distribution visualization. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Impact of nuclear data uncertainty on time-average CANDU-9 core models. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Impact of nuclear data uncertainty on time-average models of CANDU-9. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Non-stereoscopic PIV measurement sensitivity to experimental parameters. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Verification of optimum energy group structure for the Canadian PT-SCWR with PARCS diffusion analysis. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Benchmarking of thetransient reactor physics simulation code: G4-Stork. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Comparative reactor physics study on accident-tolerant fuel for the Candu reactor. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Investigation of the lattice physics phenomena in the Canadian PT-SCWR within some perturbed scenarios. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Measurement and simulation of dividing manifolds for moderator flow test facility. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Measurement and simulation of manifold flow distributions in nuclear reactor applications. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Nureth 2017. 2017
- Optimization approach of energy group structure for the Canadian pressure tube supercritical water reactor. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Preliminary flux measurements at the mcmaster nuclear reactor. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Reactivity initiated accident for the Canadian SCWR. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Sensitivity studies for the station blackout accident with crash-cooldown at a generic 900MW CANDU reactor. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Test facility design for the measurement and modelling of candu reactor moderator flow and temperature distributions. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Nureth 2017. 2017
- COUPLING RELAP5 AND PRESSURE TUBE DEFORMATION MODELS TO ANALYZE THE THERMAL-MECHANICAL PHENOMENA IN CANDU SEVERE ACCIDENTS. 36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role. 2016
- Equilibrium cycle of the Canadian SCWR with bulk and spatial reactivity control. 36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role. 2016
- Importance of coolant densities in TRITON self-shielding calculations for the Canadian SCWR. 36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role. 2016
- Loss of coolant accident simulation with RELAP5/SCDAPSIM/MOD4 for the Canadian supercritical water-cooled reactor. 36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role. 2016
- Measurement of transient critical heat flux in a heated tube at intermediate pressures in water. 36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role. 2016
- Mechanistic modelling of station blackout accidents for a generic 900MW CANDU plant using the modified SCDAP/RELAP5 code. 36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role. 2016
- The effect of dancoff equivalent pitch on voided CANDU and SCWR lattice cells. 36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role. 2016
- A Benchmark Comparison of the Canadian Supercritical Water-cooled Reactor (SCWR) 64-Element Fuel Lattice Cell Parameters using Various Computer Codes. Canadian Nuclear Society 35th Annual Conference of the Canadian Nuclear Society and 38th CNS Cna Student Conference 2015. 422-441. 2015
- Control blade pattern optimization using evolutionary algorithm for the Canadian SCWR. Canadian Nuclear Society 35th Annual Conference of the Canadian Nuclear Society and 38th CNS Cna Student Conference 2015. 1200-1206. 2015
- INuclear data sensitivity and uncertainty analysis for the Canadian supercritical water-cooled reactor (SCWR) 64 - Element fresh fuel lattice cell. Canadian Nuclear Society 35th Annual Conference of the Canadian Nuclear Society and 38th CNS Cna Student Conference 2015. 1207-1212. 2015
- CFD STUDY OF CONVECTIVE HEAT TRANSFER TO CARBON DIOXIDE AND WATER AT SUPERCRITICAL PRESSURES IN VERTICAL CIRCULAR PIPES 2014
- Prediction of response of the Canadian super critical water reactor to potential loss of forced flow scenarios 2014
- Assessment of a transuranic mixed oxide fuelled CANDU reactor. Canadian Nuclear Society 34th Annual Conference of the Canadian Nuclear Society and 37th CNS Cna Student Conference 2013. 341-359. 2013
- Description and Results of a Two-Dimensional Lattice Physics Code Benchmark for the Canadian Pressure Tube Supercritical Water-cooled Reactor (PT-SCWR). Canadian Nuclear Society 34th Annual Conference of the Canadian Nuclear Society and 37th CNS Cna Student Conference 2013. 131-145. 2013
- Lessons Learned for Participation in Recent OECD-NEA Reactor Physics and Thermalhydraulic Benchmarks. Canadian Nuclear Society 34th Annual Conference of the Canadian Nuclear Society and 37th CNS Cna Student Conference 2013. 585-595. 2013
- Uncertainty in Reactor Lattice Physics Calculations The Effect of Dilution on the Covariance of Multigroup Cross Sections. Canadian Nuclear Society 34th Annual Conference of the Canadian Nuclear Society and 37th CNS Cna Student Conference 2013. 1095-1099. 2013
- Uncertainty in Reactor lattice physics calculations the effect of dilution on the covariance of multigroup cross sections. Canadian Nuclear Society 34th Annual Conference of the Canadian Nuclear Society and 37th CNS Cna Student Conference 2013. 943-953. 2013
- The behaviour of transuranic mixed oxide fuel in a Candu-900 reactor. International Conference on the Physics of Reactors 2012 Physor 2012 Advances in Reactor Physics. 1710-1725. 2012
- Analysis of the impact of coolant density variations in the high efficiency channel of a pressure tube super critical water reactor. Canadian Nuclear Society 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS Cna Student Conference 2012 Building on Our Past Building for the Future. 1392-1397. 2012
- CANDU Lattice Uncertainties During Burnup. Canadian Nuclear Society 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS Cna Student Conference 2012 Building on Our Past Building for the Future. 430-448. 2012
- FUEL COMPOSITION OPTIMIZATION IN A 78-ELEMENT FUEL BUNDLE FOR USE IN A PRESSURE TUBE TYPE SUPERCRITICAL WATER-COOLED REACTOR. Canadian Nuclear Society 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS Cna Student Conference 2012 Building on Our Past Building for the Future. 1430-1434. 2012
- MONTE CARLO SIMULATION OF A BURNUP-AVERAGED 78-ELEMENT CANADIAN SCWR AND SIMILARITY STUDY WITH THE ZED-2 TEST REACTOR. Canadian Nuclear Society 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS Cna Student Conference 2012 Building on Our Past Building for the Future. 1425-1429. 2012
- Preliminary results for validation of Computational Fluid Dynamics for prediction of flow through a split vane spacer grid. Canadian Nuclear Society 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS Cna Student Conference 2012 Building on Our Past Building for the Future. 1202-1213. 2012
- The effects of fuel burnup on incremental cross sections in actinide fuels in CANDU reactors. Canadian Nuclear Society 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS Cna Student Conference 2012 Building on Our Past Building for the Future. 1374-1380. 2012
- The effects of fuel burnup on incremental cross sections in actinide fuels in CANDU reactors. Canadian Nuclear Society 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS Cna Student Conference 2012 Building on Our Past Building for the Future. 449-464. 2012
- Special address: Fukushima Dai-Ichi Nuclear Power Station update. Canadian Nuclear Society 32nd Annual Conference of the Canadian Nuclear Society and 35th CNS can Student Conference 2011. 1068-1080. 2011
- The potential production of molybdenum 99 in CANDU reactors. Canadian Nuclear Society 32nd Annual Conference of the Canadian Nuclear Society and 35th CNS can Student Conference 2011. 154-169. 2011
- A generalized failure map for fuel elements subject to a power pulse. Nuclear Engineering and Design. 590-598. 2011
- CROSS-SECTION COVARIANCE PROPAGATION FOR LWR FUEL CELLS IN ONE AND TWO DIMENSIONS. International Conference on the Physics of Reactors 2010 Physor 2010. 3387-3399. 2010
- Evaluation of ASSERT-PV V3R1 void fraction predictions against the OECD/NEA benchmark data. Canadian Nuclear Society 30th Annual Canadian Nuclear Society Conference and 33rd CNS Cna Student Conference 2009. 2069-2081. 2009
- Validation of Computational Fluid Dynamic Tools for Prediction of Single-Phase Flow Distribution in CANDU Headers 2009
- DETERMINATION OF REALISTIC MARGINS TO FUEL HEATUP FOR SLOW LOSS OF REGULATION ACCIDENTS IN A CANDU REACTOR. Canadian Nuclear Society 29th Annual Conference of the Canadian Nuclear Society and 32nd CNS Cna Student Conference 2008. 419-430. 2008
- Heat transfer limitation during rapid depressurization. Canadian Nuclear Society 29th Annual Conference of the Canadian Nuclear Society and 32nd CNS Cna Student Conference 2008. 751-765. 2008
- Probabilistic analysis of safety acceptance criteria for loss of regulation accidents in a CANDU reactor. Transactions of the American Nuclear Society. 476. 2008
- Validation of fluent software for prediction of flow distribution and pressure gradients in a multi-branch flow header. Canadian Nuclear Society 29th Annual Conference of the Canadian Nuclear Society and 32nd CNS Cna Student Conference 2008. 390-403. 2008
- Treatment of Epistemic and Aleatory Uncertainties in the Statistical Analysis of the Neutronic Protection System in CANDU Reactors. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. 211-220. 2008
- Validation of FLUENT for Prediction of Flow Distribution and Pressure Gradients in a Multi-Branch Header Under Low Flow Conditions. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. 221-226. 2008
- BEST ESTIMATE ANALYSIS OF LOSS OF FLOW EVENTS AT CANDU NUCLEAR POWER PLANTS. Canadian Nuclear Society 28th Annual Conference of the Canadian Nuclear Society and 31st CNS Cna Student Conference 2007 Embracing the Future Canada S Nuclear Renewal and Growth. 808-819. 2007
- Phenomena identification and ranking for loss of forced circulation accidents in a candu reactor. Proceedings 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Nureth 12. 2007
- Safety Benefits of Low Void Reactivity Fuel in Bruce B. Annual Canadian Nuclear Society Conference. 763-772. 2004
- Thermal Plasma Generated High Heat Flux Heat Transfer and Two-Phase Flow. MULTIPHASE FLOW 1995. 529-537. 1995
- A blind, numerical benchmark study on supercritical water heat transfer experiments in a 7-rod bundle
- ANALYSING SUPERCRITICAL WATER REACTOR’S (SCWR’S) SPECIAL SAFETY SYSTEMS USING PROBABILISTIC TOOLS
- ASSESSING ACCIDENT RISKS AND RESPONSES IN CANADA’S SUPERCRITICAL WATER REACTOR
- Assessment of New Modeling in RELAP/SCDAPSIM Using Experimental Results from the Quench Program
- Canadian Participation in OECD/NEA-KAERI Rod Bundle Benchmark for CFD codes
- Code to Code Comparison of the Predicted Response of the Canadian SCWR to a Loss of Flow Accident
- Coupled 3D Neutron Kinetics and Thermalhydraulic Characteristics of the Canadian SCWR
- Covariance in Lattice Physics Simulations
- Development of a Two-Dimensional Monte-Carlo Simulation for the Uncertainty Analysis of Dryout Power
- Experimental Characterization of a Turbulent Round Jet In Support Of Validating The CFD Code MODTURC_CLAS
- High Heat Flux Heat Transfer and Pressure Drop Correlations for Reactor Thermalhydraulic Simulations
- Monte Carlo computation of neutron overpower protection trip set-points using extreme value statistics
- Optimal Sizing of Flow Orifices for the Canadian SCWR Design
- Pickering Header Gradient Modelling
- Safety concepts and systems of the Canadian SCWR
- Simulations of Single Pin Cell and CANDU-SCWR Lattice Cell Using 2D Transport Codes WIMS and NEWT
- Study of TRACE Depressurization Predictions Against Experimental Data Across Different Scales
- THE IMPACT OF THE RADIAL REFLECTOR ON THE 8-GROUP CELL-AVERAGED CROSS-SECTIONS FOR THE SCWR 62-ELEMENT LATTICE CELL
- TRACE code application to Low Operating Pressure Research Reactor safety analysis
- The Role of Microscopic and Macroscopic Treatment of Error Sources in Best Estimate and Uncertainty Analysis
- Three-dimensional moderator circulation experimental program for validation of CFD code MODTURC-CLAS
- Uncertainty in Physics Calculations due to Resonance Cross Section Uncertainty
- Void Distribution Measurement of Swirl-Flow Boiling Freon By Real Time Neutron Radiography and High Speed X-Ray Computed Tomography
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journal articles
- Convolutional neural network use in fast neutron computed tomography for void fraction measurements. Nuclear Engineering and Design. 436:113975. 2025
- Applying Shapley Effect for Sensitivity Analysis During Reactor Transient. Nuclear Technology. ahead-of-print. 2025
- CANDU Station Blackout D-PSA with RAVEN and TRACE Software. Nuclear Science and Engineering. ahead-of-print. 2025
- Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN. Nuclear Science and Engineering. ahead-of-print:1-17. 2025
- CFD Simulations of a Loss of Heat Sink Experiment in the McMaster Nuclear Reactor. Energies. 17. 2024
- Uncertainty propagation in the simulation of a nuclear power plant operational transient. Nuclear Engineering and Design. 417:112821-112821. 2024
- ASYST4.1 validation for gas cooled SMR applications using the HTTF experiment. Nuclear Engineering and Design. 414:112643-112643. 2023
- Uncertainty Propagation in UAM Time-Dependent Neutronics PWR Studies. Nuclear Science and Engineering. 197:1305-1330. 2023
- BEPU analysis of a CANDU LBLOCA RD-14M experiment using RELAP/SCDAPSIM. Nuclear Engineering and Technology. 55:1448-1459. 2023
- Flow regime transitions for Aiding flow around a heated cylinder: A numerical and experimental investigation. Nuclear Engineering and Design. 405:112206-112206. 2023
- Modelling and Validation of CANDU Shim Operation Using Coupled TRACE/PARCS with Regulating System Response. Science and Technology of Nuclear Installations. 2023:1-21. 2023
- Mixed convection around two vertically aligned horizontal cylinders: A numerical, experimental, and modeling investigation on the effect of local conditions on heat transfer. Nuclear Engineering and Design. 394:111823-111823. 2022
- Demonstration of combined reduced order model and deep neural network for emulation of a time-dependent reactor transient. Annals of Nuclear Energy. 171:109017-109017. 2022
- Radiation shielding properties of modified concrete mixes and their suitability in dry storage cask. Progress in Nuclear Energy. 148:104195-104195. 2022
- Application of Bayesian methods to neutron spectrum measurements. Annals of Nuclear Energy. 169:108972-108972. 2022
- Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response. Science and Technology of Nuclear Installations. 2022:1-31. 2022
- Implementation and testing of unscented transformation and low rank approximation to enhance SCALE code uncertainty calculations. Annals of Nuclear Energy. 167:108816-108816. 2022
- Incorporation and testing of refrigerant fluids (R-134a) in the subchannel analysis code CTF (COBRA-TF). Progress in Nuclear Energy. 142:104028-104028. 2021
- 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. Annals of Nuclear Energy. 160:108399-108399. 2021
- Determination of lattice physics properties and uncertainties in a solid fuel molten salt cooled assembly using OpenMC. Progress in Nuclear Energy. 139:103890-103890. 2021
- Measurement, simulation and uncertainty quantification of the neutron flux at the McMaster Nuclear Reactor. Annals of Nuclear Energy. 151:107879-107879. 2021
- VALIDATION OF THE POLARIS CANDU EXTENSION FOR LATTICE PHYSICS. EPJ Web of Conferences. 247:02009-02009. 2021
- An experimental and numerical investigation into scaling considerations for moderator circulation experiments. Nuclear Engineering and Design. 369:110829-110829. 2020
- Genetic Algorithm Optimization of Core-Shell Nanowire Betavoltaic Generators. Nanotechnology. 31:455403-455403. 2020
- The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors. Journal of Nuclear Engineering and Radiation Science. 6. 2020
- Design and optimization of nanowire betavoltaic generators. Journal of Applied Physics. 127. 2020
- Extension and preliminary validation of the Polaris lattice physics code for CANDU analysis. Nuclear Engineering and Design. 361:110540-110540. 2020
- Quantification of system uncertainties in activation experiments at nuclear research reactors. Annals of Nuclear Energy. 134:432-440. 2019
- Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics. Journal of Nuclear Engineering and Radiation Science. 5. 2019
- Simulation and optimization of current generation in gallium phosphide nanowire betavoltaic devices. Journal of Applied Physics. 125. 2019
- GaP nanowire betavoltaic device. Nanotechnology. 30:075401-075401. 2019
- Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3.6 code. Nuclear Engineering and Design. 335:71-93. 2018
- Development and Benchmarking of Mechanistic Channel Deformation Models in RELAP/SCDAPSIM/MOD3.6 for CANDU Severe Accident Analysis. Nuclear Science and Engineering. 190:209-237. 2018
- Determination of the optimal few-energy group structure for the Canadian Super Critical Water-cooled Reactor. Annals of Nuclear Energy. 115:27-38. 2018
- Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations. Journal of Nuclear Engineering and Radiation Science. 4. 2018
- Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics. Science and Technology of Nuclear Installations. 2018:1-17. 2018
- Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors. Science and Technology of Nuclear Installations. 2018:1-17. 2018
- Investigation of Fuel Burnup Impacts on Nuclear Reactor Safety Parameters in the Canadian Pressure Tube Supercritical Water-Cool Reactor. Journal of Nuclear Engineering and Radiation Science. 4. 2018
- RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators. Nuclear Engineering and Design. 318:35-53. 2017
- The effects of transient conditions on the onset of intermittent dryout during blowdown. Nuclear Engineering and Design. 317:118-132. 2017
- INVESTIGATION OF REACTOR PHYSICS PHENOMENA IN THE CANADIAN PRESSURE TUBE SUPERCRITICAL-WATER REACTOR. CNL NUCLEAR REVIEW. 5:1-16. 2016
- A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7-Rod Bundle. Journal of Nuclear Engineering and Radiation Science. 2. 2016
- Coupled 3D neutron kinetics and thermalhydraulic characteristics of the Canadian supercritical water reactor. Nuclear Engineering and Design. 298:78-89. 2016
- Examination of Separate-Effect and Integral Phenomena Within a Grid Spacer with Mixing Vanes: Results for the MATiS-H OECD/NEA Benchmark Exercise. Nuclear Science and Engineering. 177:141-155. 2014
- Selected Papers from OECD-NEA PSBT Benchmark. Science and Technology of Nuclear Installations. 2014:1-3. 2014
- The Dilution Dependency of Multigroup Uncertainties. Science and Technology of Nuclear Installations. 2014:1-14. 2014
- Analysis of implicit and explicit lattice sensitivities using DRAGON. Nuclear Engineering and Design. 265:1-12. 2013
- Behavior of Transuranic Mixed-Oxide Fuel in a CANDU-900 Reactor. Nuclear Technology. 183:30-44. 2013
- Summary on the depressurization from supercritical pressure conditions. International Congress on Advances in Nuclear Power Plants 2012 Icapp 2012. 1:170-178. 2012
- A strategy for intensive production of molybdenum-99 isotopes for nuclear medicine using CANDU reactors. Applied Radiation and Isotopes. 70:20-34. 2012
- Evaluation of ASSERT-PV V3R1 against the PSBT Benchmark. Science and Technology of Nuclear Installations. 2012:1-21. 2012
- Non-parametric study on the optimization of thorium content in a 54-element fuel bundle for use in a CANDU-SCWR. Canadian Nuclear Society 32nd Annual Conference of the Canadian Nuclear Society and 35th CNS can Student Conference 2011. 1:553-562. 2011
- Preliminary fault tree analysis and FMEA of high efficiency channel in a CANDU-SCWR. Transactions of the American Nuclear Society. 104:597-599. 2011
- The reactor physics characteristics of a transuranic mixed oxide fuel in a heavy water moderated reactor. Nuclear Engineering and Design. 241:3768-3776. 2011
- Determination of Operator Action Times during a Loss-of-Feedwater Event Using Extreme Value Statistics. Nuclear Science and Engineering. 164:151-161. 2010
- An engineering primer on extreme value statistics. Canadian Nuclear Society 30th Annual Canadian Nuclear Society Conference and 33rd CNS Cna Student Conference 2009. 3:2164-2176. 2009
- PREDICTION OF VOID FRACTION UNCERTAINTY BANDS IN BWR FUEL BUNDLES USING THE CIAU METHODOLOGY. American Nuclear Society International Conference on Mathematics Computational Methods and Reactor Physics 2009 M and C 2009. 5:3183-3193. 2009
- A Statistical Methodology for Determination of Safety Systems Actuation Setpoints Based on Extreme Value Statistics. Science and Technology of Nuclear Installations. 2008:1-10. 2008
- Recent Advances in High Heat Flux Smooth and Swirl Flow Boiling of Water. Fusion Science and Technology. 52:880-884. 2007
- A study of flow boiling phenomena using real time neutron radiography / 2000
- Visualization of Boiling Freon Swirl Flow. Transactions of Visualization Society of Japan. 20:365-368. 2000
- Visualization of Boiling Freon Swirl Flow. Transactions of Visualization Society of Japan. 20:365-368. 2000
- Development and Design Considerations for a Suite of New Post-Irradiation Examination Hot Cells to be Constructed at McMaster University. HOT CELL POST-IRRADIATION EXAMINATION AND POOLSIDE INSPECTION OF NUCLEAR FUEL. 139.
- Evaluation of Ash Toxicity Generated From the Thermal Plasma Pyrolysis of Used Automobile Tires