selected scholarly activity
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academic article
- The working group on the analysis and management of accidents (WGAMA): A historical review of major contributions. Progress in Nuclear Energy. 127:103432-103432. 2020
- 3D-thermo-structural simulation of pressure tube–calandria tube behaviour under accident conditions in PHWR using ABAQUS. Nuclear Engineering and Design. 328:188-196. 2018
- Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications. Journal of Nuclear Engineering and Radiation Science. 3. 2017
- Special Section: Pressurized Heavy Water Reactors Safety. Journal of Nuclear Engineering and Radiation Science. 3. 2017
- BACKUP AND ULTIMATE HEAT SINKS IN CANDU REACTORS FOR PROLONGED SBO ACCIDENTS. Nuclear Engineering and Technology. 45:589-596. 2013
- The results from the third high-pressure melt ejection test completed in the molten fuel moderator interaction facility at Chalk River Laboratories. International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010. 2:1062-1071. 2010
- Results from the fourth high-pressure melt ejection test completed in the molten fuel moderator interaction facility at Chalk River Laboratories. Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants - ICAPP ’10. 2006:1332-1340. 2010
- Enhancement of the moderator subcooling margin using glass-peened calandria tubes in CANDU reactors. Canadian Nuclear Society - 30th Annual Canadian Nuclear Society Conference and 33rd CNS/CNA Student Conference 2009. 3:2150-2163. 2009
- The results from the second high-pressure melt ejection test completed in the Molten Fuel Moderator Interaction Facility at Chalk River Laboratories. Canadian Nuclear Society Bulletin. 28:41-49. 2007
- Development of Molten Corium Using An Exothermic Chemical Reaction for the Molten- Fuel Moderator-Interaction Studies at Chalk River Laboratories. Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP’04. 1051-1061. 2004
- Correlation Between the Critical Heat Flux and the Fractal Surface Roughness of Zirconium Alloy Tubes. Journal of Enhanced Heat Transfer. 8:137-146. 2001
- Analysis of the stratified / nonstratified transitional boundary in horizontal and slightly inclined condensing flows. Canadian Journal of Chemical Engineering. 72:26-34. 1994
- Influence of tube inclination on the flow regime boundaries of condensing steam. Canadian Journal of Chemical Engineering. 71:35-41. 1993
- IAEA ICSP on HWR moderator subcooling requirements to demonstrate backup heat sink
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article
- CNSC nuclear power plant accident handbook 2014
- Nuclear power plant accident handbook, a CNSC Emergency Operations Centre tool. International Meeting on Severe Accident Assessment and Management 2012: Lessons Learned from Fukushima Dai-ichi. 195-199. 2014
- The Results From the First High-Pressure Melt Ejection Test Completed in the Molten Fuel Moderator Interaction Facility at Chalk River Laboratories. International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009. 2:1066-1074. 2009
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conference paper
- Experimental study on high emissivity thicker oxide Zr-2.5Nb pressure tube material. PBNC 2018 - Pacific Basin Nuclear Conference. 178-186. 2019
- OECD-WGAMA Contribution to Nuclear Thermal-hydraulics: An Overview of Major Milestones and Present Activities. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017. 2017
- IAEA ICSP on HWR moderator subcooling requirements to demonstrate backup heat sink capabilities of moderator during accidents. Canadian Nuclear Society - 34th Annual Conference of the Canadian Nuclear Society and 37th CNS/CNA Student Conference 2013. 880-889. 2013
- Nuclear Power Plant Accident Handbook a CNSC Emergency Operations Centre tool. 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. 162-171. 2012
- The results from the second high-pressure melt ejection test completed in the molten fuel moderator interaction facility at Chalk River Laboratories. Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". 1905-1915. 2008
- Molten fuel moderator interaction experiments for PHWRs. Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05. 2805-2814. 2005
- A PROPOSED APPROACH FOR CORRELATING HEAT-TRANSFER DURING CONDENSATION INSIDE TUBES. ASHRAE TRANSACTIONS, VOL 96, PT 1, 1990. 230-241. 1990