selected scholarly activity
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chapters
- Regulatory and licensing challenges with Generation-IV nuclear energy systems. 837-864. 2023
- 15 Severe accident prevention and mitigation in pressurized heavy water reactors. 477-508. 2022
- Design and aging management for feeder pipe and feeder supports. 171-227. 2022
- Severe accident prevention and mitigation in pressurized heavy water reactors. 477-508. 2022
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conferences
- NUMERICAL ANALYSIS OF IN-VESSEL MELT RETENTION OF CANDU REACTORS DURING A SEVERE ACCIDENT. Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Operation and Safety Nuthos 2024. 1504-1520. 2024
- Applicability of Sub-Modelling Technique for Dynamic Analysis of Concrete Structures With Attached Equipment Under Missile Impact. Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation. 2020
- 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
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journal articles
- THERMAL BEHAVIOUR CORRELATION FOR THERMAL COLUMN IN THE NATIONAL RESEARCH UNIVERSAL (NRU) REACTOR. CNL NUCLEAR REVIEW. 9:1-10. 2020
- 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
- CHARACTERIZING HIGH-TEMPERATURE DEFORMATION OF INTERNALLY HEATED NUCLEAR FUEL ELEMENT SIMULATORS. CNL NUCLEAR REVIEW. 5:67-84. 2016
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TOTAL HEMISPHERICAL EMISSIVITY OF PRE-OXIDIZED AND UN-OXIDIZED ZR-2.5N
b PRESSURE-TUBE MATERIALS AT 600 °C TO 1000 °C UNDER VACUUM. CNL NUCLEAR REVIEW. 5:85-93. 2016 - 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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other
- 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. 1066-1074. 2009