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. The Nuclear Future: Challenges and Innovaion - 38th Annual CNS Conference and 42nd CNS/CNA Student Conference. 2018
- A simplified core model of the SCWR. The 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. The 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