selected scholarly activity
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books
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chapters
- Heavy Water Reactors. 141-196. 2009
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conferences
- Energetic Liquid Droplet Boiling on High-Temperature Metal Surfaces. Nuclear Technology. 104-118. 2019
- A simplified core model of the Canadian supercritical water-cooled reactors. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- A simplified core model of the SCWR. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Investigation of different methods to design the start-up core of the canadian SCWR. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- CORE ELEMENTS IMPROVEMENTS FOR OPTIMIZATION OF RADIOISOTOPES PRODUCTION IN AN MTR-TYPE CORE. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Literature review of cladding for corrosion protection of structural alloys in Molten fluoride salts. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- 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
- Developments Toward Mechanistic Modeling of Critical Heat Flux on a CANDU Calandria Tube Following Pressure Tube Contact. Nuclear Technology. 157-169. 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
- 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
- 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
- Thermal-Hydraulic Aspects of Progression to Severe Accidents in CANDU Reactors. Nuclear Technology. 187-210. 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
- Comparison of LOCA power transient uncertainty analysis methods. Transactions of the American Nuclear Society. 657-659. 2008
- Dynamic Sensitivity Analysis of Thermal-Mechanical Deformation of a CANDU Fuel Channel. Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance. 229-238. 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
- TUF VERIFICATION AGAINST SELECTED RD-14 EXPERIMENTS. 10TH ANNUAL CONFERENCE 1989 - CANADIAN NUCLEAR SOCIETY, PROCEEDINGS, VOL 2. F1-F9. 1989
- Candu spatial neutron kinetics. Transactions of the American Nuclear Society. 599-601. 1982
- CANDU REACTOR BENCHMARK PROBLEMS. Transactions of the American Nuclear Society. 481-482. 1981
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journal articles
- Simulation of a loss of flow transient of a small Lead-Cooled reactor using a CFD-Based model. Nuclear Engineering and Design. 412:112462-112462. 2023
- Assessment of the material attractiveness and reactivity feedback coefficients of various fuel cycles for the Canadian concept of Super-Critical Water Reactors. Nuclear Engineering and Technology. 54:2660-2669. 2022
- Evaluation of the canister spacing and criticality safety of spent plutonium-thorium nuclear fuel. Annals of Nuclear Energy. 172:109056-109056. 2022
- Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor. Nuclear Engineering and Design. 392:111773-111773. 2022
- Assessment of the occupational dose rate during fuel handling and storage of various fuel cycles used in the super-critical water reactor and the impact on deep geological repository performance. Progress in Nuclear Energy. 147:104178-104178. 2022
- Rewetting Delay Time During Jet Impingement Quench Cooling of Hot Curved Surfaces. Nuclear Technology. 208:520-538. 2022
- Dynamic sensitivity and uncertainty analysis of a small lead cooled reactor. Annals of Nuclear Energy. 144:107512-107512. 2020
- Foreword: Selected papers from the 2018 International Topical Meeting on Advances in Thermal Hydraulics (ATH 2018). Nuclear Technology. 206:III-IV. 2020
- Critical heat flux for downward-facing pool boiling on CANDU calandria vessel. Annals of Nuclear Energy. 110:768-778. 2017
- Critical heat flux for downward-facing pool boiling on CANDU calandria tube surface. Nuclear Engineering and Design. 315:104-116. 2017
- Experimental investigation of quench and re-wetting temperatures of hot horizontal tubes well above the limiting temperature for solid–liquid contact. Nuclear Engineering and Design. 311:167-183. 2017
- Measurement and analysis of the re-wetting front velocity during quench cooling of hot horizontal tubes. Nuclear Engineering and Design. 311:184-198. 2017
- Power distribution control of CANDU reactors based on modal representation of reactor kinetics. Nuclear Engineering and Design. 278:323-332. 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
- Performance evaluation of a 3-D kinetic model for CANDU reactors in a closed-loop environment. Nuclear Engineering and Design. 243:76-86. 2012
- A strategy for intensive production of molybdenum-99 isotopes for nuclear medicine using CANDU reactors. Applied Radiation and Isotopes. 70:20-34. 2012
- Preliminary fault tree analysis and FMEA of high efficiency channel in a CANDU-SCWR. Transactions of the American Nuclear Society. 104:597-599. 2011
- A STUDY OF FLOW AND TEMPERATURE DISTRIBUTION AROUND A SINGLE CHANNEL IN CANDU MODERATOR 2009
- Reference model parameter identification of space–time dependent reactivity in a CANDU-PHWR. Annals of Nuclear Energy. 35:228-237. 2008
- Clarification of a recent comparison of natural circulation flows in “code validation and uncertainties in system thermal hydraulics” by F. D'Auria and G.M. Galassi. Progress in Nuclear Energy. 36:231-233. 2000
- Global warming and sustainable energy supply with CANDU nuclear power systems. Progress in Nuclear Energy. 32:297-304. 1998
- STGEN computer program methodology and application to the steam line break tests in the RD-12 steam generator. Nuclear Engineering and Design. 126:151-173. 1991
- Authors. Nuclear Technology. 46:379-390. 1979
- Space-Time Neutronic Analysis of Postulated Loss-of-Coolant Accidents in CANDU Reactors. Nuclear Technology. 46:507-516. 1979
- CANDU reactor kinetics benchmark activity. Nuclear Science and Engineering. 64:1:95-105. 1977
- Design and Analysis of an Electronic Peak-Holding Controller. IEEE Transactions on Industrial Electronics and Control Instrumentation. IECI-21:173-179. 1974
- A Dynamic Electroheat Model for an AC Plasma Torch. IEEE Transactions on Industry Applications. IA-10:360-367. 1974
- Suboptimal adaptive control of a class of non-linear systems†. International Journal of Control. 17:965-975. 1973
- Modeling the Thermal Characteristics of an AC Plasma Torch. IEEE Transactions on Industry & Gen Applications. IGA-7:525-530. 1971
- Stability of Peak-Holding Control Systems. IEEE Transactions on Industrial Electronics and Control Instrumentation. IECI-18:11-15. 1971
- Requirements for stable a.c. electric-arc discharges. Electronics Letters. 6:285-285. 1970
- 2D Modeling of moderator flow and temperature distribution around a single channel after pressure tube/calandria tube contact. Canadian Nuclear Society - 30th Annual Canadian Nuclear Society Conference and 33rd CNS/CNA Student Conference 2009. 2:959-971.
- Analytical criteria for fuel failure modes observed in reactivity initiated accidents. 26th Annual Canadian Nuclear Society Conference and 29th CNS/CNA Student Conference. 1309-1325.
- Assessment of advanced fuel cycle options in CANDU. International Nuclear Fuel Cycle Conference Global 2013 Nuclear Energy at A Crossroads. 1:509-520.
- CANDU response to loss of all heat sinks
- Critical heat flux on a downward facing surface with a shallow cavity obstruction. Transactions of the American Nuclear Society. 109:1557-1560.
- Heat transfer modelling of CANDU pressure tube under localized high temperature condition. Canadian Nuclear Society - 30th Annual Canadian Nuclear Society Conference and 33rd CNS/CNA Student Conference 2009. 2:932-944.
- Multi-step approach to code-coupling for progression induced severe occidents in CANDU NPPs (MACPISA-CANDU)
- Parametric analysis of fuel cooling in LOCA with ECCS impairments in CANDU reactors
- Reactivity initiated accidents and loss of shutdown - 20 years later
- Safety Analysis Technology: Evolution, Revolution and the Drive to Re-Establish Margins
- Simulation of Bruce phw nuclear generating station for control studies
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preprints
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theses