selected scholarly activity
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conferences
- Thermal-hydraulics comparison of integral molten salt reactor (IMSR) and nuscale power reactor. The Nuclear Future: Challenges and Innovaion - 38th Annual CNS Conference and 42nd CNS/CNA Student Conference. 2018
- Safety and Licensing Aspects of Power Reactor Reactivity Coefficients. Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Co. 221-230. 2013
- Licensing Challenges for New Countries Entering a Nuclear Power Program. Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Co. 231-240. 2012
- ACR-1000® pre-project regulatory review progress. Canadian Nuclear Society - 30th Annual Canadian Nuclear Society Conference and 33rd CNS/CNA Student Conference 2009. 2102-2110. 2009
- Computer Code Applicability Assessment for the Advanced CANDU Reactor. 12th International Conference on Nuclear Engineering, Volume 3. 397-404. 2008
- Large-Break Loss-of-Coolant Accident Phenomena Identification and Ranking Table (PIRT) for the Advanced CANDU Reactor. 12th International Conference on Nuclear Engineering, Volume 3. 415-424. 2008
- Development of Phenomena Identification and Ranking Tables for the Advanced CANDU Reactor. Nuclear Technology. 2-17. 2007
- ACR-1000 design provisions for severe accidents. 27th Annual Conference of the Canadian Nuclear Society and 30th Canadian Nuclear Society - Nuclear Energy A World of Service to Humanity. 2006
- Development of Phenomena Identification and Ranking Tables (PIRTs) for the advanced CANDU reactor. Proceedings - International Meeting on Updates in Best Estimate Methods in Nuclear Installation Safety Analysis, BE-2004. 231-245. 2004
- Evaluation model for ACR-700 large break LOCA. Transactions of the American Nuclear Society. 363-364. 2004
- PIRT efforts in support of ACR-700 computer code validation. Annual Canadian Nuclear Society Conference. 1377-1390. 2004
- Validation of Physics and Thermalhydraulics Computer Codes for Advanced CANDU Reactor Applications. 12th International Conference on Nuclear Engineering, Volume 3. 405-413. 2004
- Computer Code Qualification Program for the Advanced CANDU Reactor. Transactions of the American Nuclear Society. 90. 2003
- The role of a nuclear power station in a small electric power generating system. Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy. 693-694. 2003
- The Application of Best Estimate and Uncertainty Analysis Methodology to Large LOCA Power Pulse in a CANDU 6 Reactor. 10th International Conference on Nuclear Engineering, Volume 2. 341-348. 2002
- Post-test analysis of the BTF-104 severe-fuel-damage experiment using the CATHENA thermalhydraulics code. Proceedings of the ASME/JSME International Conference on Nuclear Engineering, ICONE. 205-213. 1996
- Post-test simulations of BTF-107: an in-reactor loss-of-coolant test with flow blockage and rewet. Annual International Conference - Canadian Nuclear Association. 1992
- Analysis of blowdown and refill phenomena observed in RD-14 loca experiments. American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD. 73-83. 1990
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journal articles
- PARTRIDGE-II - an international research program for developing a probabilistic tool for risk-informed decision making. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS/CNA Student Conference. 2017
- UNENE: an integrated network for knowledge management for the long-term. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS/CNA Student Conference. 2017
- Power electronics solution to dust emissions from thermal power plants. Serbian Journal of Electrical Engineering. 7:231-252. 2010
- ICONE15-10806 THE MANAGEMENT OF SEVERE ACCIDENTS IN MODERN PRESSURE TUBE REACTORS. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2007.15:_ICONE1510-_ICONE1510. 2007
- Pre-licensing of the Advanced CANDU Reactor. 27th Annual Conference of the Canadian Nuclear Society and 30th Canadian Nuclear Society - Nuclear Energy A World of Service to Humanity. 2006. 2006
- Advanced CANDU reactor pre-licensing progress. 26th Annual Canadian Nuclear Society Conference and 29th CNS/CNA Student Conference. 1219-1227. 2005
- Licensing the ACR-700 in Canada: progress on the pre-licensing review. Annual Canadian Nuclear Society Conference. 1265-1274. 2004
- Single channel flow blockage accident phenomena identification and ranking table (PIRT) for the advanced Candu reactor. Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP’04. 1682-1693. 2004
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other
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reports
- Post-Test simulations of BTF-107: an in-reactor loss-of-coolant test with flow blockage and rewet. Atomic Energy of Canada Limited, AECL (Report). 1-23. 1993