selected scholarly activity
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chapters
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conferences
- A Data-driven Approach to Predict Maintenance Delays for Time-based Maintenance. 2023 IEEE International Conference on Industrial Engineering and Engineering Management (IEEM). 249-253. 2023
- Condition Based Maintenance in Nuclear Power Plants: Limitations & Practicality. IEEE International Conference on Industrial Engineering and Engineering Management. 1137-1141. 2021
- Development of a Selection Tool for Choosing Decontamination Technology for Canadian Applications. Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation. 2020
- Synergy of an SMR for Addressing Remote Communities Non-Nuclear Waste. Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors. 2020
- Community and siting impacts on small modular reactor operability and design. PBNC 2018 - Pacific Basin Nuclear Conference. 493-500. 2019
- Design of a natural circulation loop for molten salt coolant studies. PBNC 2018 - Pacific Basin Nuclear Conference. 529-538. 2019
- Research and development of PVA-KI gel dosimeter. PBNC 2018 - Pacific Basin Nuclear Conference. 326-330. 2019
- Assessment of the Turbulent Prandtl Number Effect on Simulating Heat Transfer Characteristics of Supercritical Water Flow in Bare Tubes. Volume 6: Thermal-Hydraulics. 2017
- Conceptual Design for CHP System for Class III Power. Volume 9: Student Paper Competition. v009t15a049-v009t15a049. 2017
- Design of an Assessment Tool for Site Evaluation of Nuclear Power Plants. Volume 9: Student Paper Competition. 2017
- Development of a Gel Type Dosimeter for X-Ray Fields. Volume 9: Student Paper Competition. 2017
- Molten salt loop heating system design. 36th Annual CNS Conference and 40th CNS-CNA Student Conference - Nuclear in the 21st Century: Global Directions and Canada's Role. 2016
- Small modular reactor emergency energy management model for critical facilities in cities. 36th Annual CNS Conference and 40th CNS-CNA Student Conference - Nuclear in the 21st Century: Global Directions and Canada's Role. 2016
- Emergency Energy Management Model for Durham Region. Volume 2: Photovoltaics; Renewable-Non-Renewable Hybrid Power System; Smart Grid, Micro-Grid Concepts; Energy Storage; Solar Chemistry; Solar Heating and Cooling; Sustainable Cities and Communities, Transportation; Symposium on Integrated/Sustainable Building Equipment and Systems; Thermofluid Analysis of Energy Systems Including Exergy and Thermoeconomics; Wind Energy Systems and Technologies. 2015
- Experimental investigation of the thermal conductivity and viscosity of liquid In-Bi-Sn eutectic alloy (Field's metal) for use in a natural circulation experiental loop. International Conference on Nuclear Engineering, Proceedings, ICONE. 2015
- Graduate diploma program in nuclear engineering design. Conference on Nuclear Training and Education 2015, CONTE 2015. 21-22. 2015
- Innovative approach to correlate heat-transfer data to supecritical carbon dioxide flowing upward in a bare tube. International Conference on Nuclear Engineering, Proceedings, ICONE. 2015
- Investigation of convection heat transfer of supercritical water using ATHLET system code. International Conference on Nuclear Engineering, Proceedings, ICONE. 2015
- Numerical assessment and comparison of heat transfer characteristics of supercritical water in bare tubes and tubes with heat transfer enhancing appendages. International Conference on Nuclear Engineering, Proceedings, ICONE. 2015
- Specifics of forced-convective heat transfer in supercritical carbon dioxide. Canadian Nuclear Society - 35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015. 1092-1099. 2015
- Study on Specifics of Forced-Convective Heat Transfer in Supercritical Carbon Dioxide. Journal of Nuclear Engineering and Radiation Science. 2015
- Investigation of ATHLET System Code for Supercritical Water Applications. Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition. 2014
- Study on Specifics of Forced-Convective Heat Transfer in Supercritical Carbon Dioxide. Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition. v005t17a013-v005t17a013. 2014
- Heat transfer profiles of a vertical, bare, 7-element bundle cooled with supercritical Freon R-12. Nuclear Engineering and Design. 246-256. 2013
- Determination of Specific Heat of Eutectic Indium – Bismuth-Tin Liquid Metal Alloys as a Test Material for Liquid Metal - Cooled Applications. Applied Mechanics and Materials. 185-193. 2013
- Assessment of FLUENT Code as a Tool for SCW Heat Transfer Analysis. Volume 6: Beyond Design Basis Events; Student Paper Competition. 2013
- Effects of Cavitation Damage on the Hydraulic Characteristics of a Gate Valve. Volume 2: Reliability, Availability and Maintainability (RAM); Plant Systems, Structures, Components and Materials Issues; Simple and Combined Cycles; Advanced Energy Systems and Renewables (Wind, Solar and Geothermal); Energy Water Nexus; Thermal Hydraulics and CFD; Nuclear Plant Design, Licensing and Construction; Performance Testing and Performance Test Codes. 2013
- Investigation of Fluid Dynamic Properties of Liquid Field’s Metal. Volume 2: Reliability, Availability and Maintainability (RAM); Plant Systems, Structures, Components and Materials Issues; Simple and Combined Cycles; Advanced Energy Systems and Renewables (Wind, Solar and Geothermal); Energy Water Nexus; Thermal Hydraulics and CFD; Nuclear Plant Design, Licensing and Construction; Performance Testing and Performance Test Codes. v002t11a008-v002t11a008. 2013
- Numerical Analysis of Natural Circulation Phenomena of Supercritical Fluids. Volume 6: Beyond Design Basis Events; Student Paper Competition. v006t16a043-v006t16a043. 2013
- Preliminary Investigation of Heat-Transfer Correlation for Upward Flow of CO2 at Supercritical Pressure. Volume 6: Beyond Design Basis Events; Student Paper Competition. 2013
- Study on Primary and Secondary Heat-Transport Systems for Sodium-Cooled Fast Reactor. Volume 6: Beyond Design Basis Events; Student Paper Competition. 2013
- Power-conversion cycles for sodium-cooled fast reactors. Canadian Nuclear Society - 34th Annual Conference of the Canadian Nuclear Society and 37th CNS/CNA Student Conference 2013. 1089-1094. 2013
- Sensitivity analysis of CFD code FLUENT-12 for supercritical water in vertical bare tubes. 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. 1505-1510. 2012
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Variable axial power profile heat-loss analysis of a co
2 gas insulated re-entrant SCWR fuel-channel. 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. 1534-1539. 2012 - Experimental study of heat transfer in a 7-element bundle cooled with supercritical Freon-12. International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012. 2320-2327. 2012
- Experimental Study of Heat Transfer in a 7-Element Bundle Cooled With Supercritical Freon-12. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles. 263-+. 2012
- Sensitivity Analysis of CFD Code FLUENT-12 for Supercritical Water Heat Transfer in Vertical Bare Tubes. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles. 425-433. 2012
- Suitability of Eutectic Field’s Metal for Use in an Electromagnetohydrodynamically-Enhanced Experimental Two-Phase Flow Loop. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles. 51-58. 2012
- An advanced engineering test reactor for Canada. Canadian Nuclear Society - 32nd Annual Conference of the Canadian Nuclear Society and 35th CNS/Can Student Conference 2011. 680-690. 2011
- Effects of orientation with respect to gravity for a wire-plate convergent angle electrohydrodynamic gas pump. Annual Report - Conference on Electrical Insulation and Dielectric Phenomena, CEIDP. 567-570. 2011
- Three-Dimension Deposited Soot Distribution Measurement in Silicon Carbide Diesel Particulate Filters by Dynamic Neutron Radiography. SAE Technical Papers. 2011
- Reforming of diesel fuel by a recirculation type pulsed voltage electrohydrodynamic atomization. Proceedings - IEEE International Conference on Dielectric Liquids. 2011
- Three-dimension deposited soot distribution measurement in silicon carbide diesel particulate filters by dynamic neutron radiography. SAE Technical Papers. 2011
- Characterization of electrohydrodynamic heat transport components in a space-type nuclear reactor. Canadian Nuclear Society - 31st Annual Conference of the Canadian Nuclear Society and 34th CNS/CNA Student Conference 2010. 584-594. 2010
- A Comparison of Different Communication Tools for Distance Learning in Nuclear Education. 18th International Conference on Nuclear Engineering: Volume 2. 391-401. 2010
- Design Concept and Heat Transfer Analysis for a Double Pipe Channel for SCWR Type Reactors. 18th International Conference on Nuclear Engineering: Volume 2. 747-754. 2010
- Narrow-Flow-Channel-Driven EHD Gas Pump for an Advanced Thermal Management of Microelectronics. IEEE Transactions on Industry Applications. 1151-1158. 2010
- SuperCritical Water-Cooled Nuclear Reactor With Intermediate Heat Exchangers. 18th International Conference on Nuclear Engineering: Volume 2. 845-854. 2010
- Heat Transfer Assessment of Calandria Tube Enhancement Design Options. Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition. 557-563. 2009
- Measurement of Multi-Dimension Soot Distribution in Diesel Particulate Filters by a Dynamic Neutron Radiography. SAE Technical Papers. 2009
- Measurement of Natural Circulation Two-Phase Flow by Hybrid Doppler Contrapropagating and Pulse Echo Ultrasonic Techniques. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. 529-537. 2009
- Structural and Neutronic Assessment of Calandria Tube Enhancement Design Options. Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition. 481-488. 2009
- Capillary/Narrow Flow Channel Driven EHD Gas Pump for an Advanced Thermal Management of Micro-Electronics. Conference Record - IAS Annual Meeting (IEEE Industry Applications Society). 1855-+. 2008
- Flow Regime Observations in a Vertical Annulus With an Inner Roughened Tube. Volume 10: Heat Transfer, Fluid Flows, and Thermal Systems, Parts A, B, and C. 1845-1852. 2008
- Fundamental Characteristics of a Plasma Electrohydrodynamic Atomization. Proceedings of the 6th International Conference on Applied Electrostatics. 80-83. 2008
- Investigation of Combined Neutron Scattering and Neutron Radiography Techniques for Measurement of Gas-Liquid Two-Phase Flow. Volume 3: Thermal Hydraulics; Instrumentation and Controls. 253-260. 2008
- Pipe Diameter Effect on the Two-Phase Flow Separator for Removal of Liquid in Horizontal Pipes. Volume 3: Thermal Hydraulics; Instrumentation and Controls. 261-268. 2008
- Polarity Effect and Flow Characteristics of Wire-Rod Type Electrohydrodynamic Gas Pump. Annual Report - Conference on Electrical Insulation and Dielectric Phenomena, CEIDP. 182-185. 2006
- Characteristics of magneto-dielectric-barrier discharge trench reactors for oxidation and reduction of gaseous pollutants. Progress of Green Oxidation/Reduction Technologies. 306-310. 2006
- Neutron Transport Characteristics of a Nuclear Reactor Based Dynamic Neutron Imaging System. Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. 409-417. 2006
- Observation of electrohydrodynamically atomized dielectric liquids by realtime and high speed infra-red thermal images. IEEE International Conference on Dielectric Liquids, 2005. ICDL 2005.. 229-232. 2005
- Neutron transport analysis of McMaster nuclear reactor advanced dynamic neutron imaging facility. 26th Annual Canadian Nuclear Society Conference and 29th CNS/CNA Student Conference. 1353-1367. 2005
- CHARACTERIZATION OF PARTICLE EMISSION FROM NATURAL GAS COMBUSTION. Journal of Aerosol Science. S877-S878. 2004
- An Advanced Ultrasonic Technique for Flow and Void Fraction Measurements of Two-Phase Flow. 12th International Conference on Nuclear Engineering, Volume 3. 485-489. 2004
- Visualization of a gas-liquid metal two-phase natural circulation flow by a real-time neutron radiography technique. Proceedings of the ASME/JSME International Conference on Nuclear Engineering, ICONE. 343-346. 1996
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journal articles
- A comparison of thermo-oxidation kinetic measurements of Zircaloy-4 in light and heavy water steam. Journal of Nuclear Materials. 573:154111-154111. 2023
- Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste. Journal of Nuclear Engineering and Radiation Science. 8. 2022
- Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant. Journal of Nuclear Engineering and Radiation Science. 8. 2022
- Development of a Selection Tool for Choosing Decontamination Technology for Canadian Applications 2021
- Effects of Operating Frequency on Electric Field and Neutralizing Current Density of a Corona Discharge Air Ionizer. International Journal of Plasma Environmental Science and Technology. 12:120-124. 2019
- Recovery of radioactive iodine from nuclear power plants using a microwave based plasma technique. International Journal of Plasma Environmental Science and Technology. 11:122-127. 2018
- Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes. Journal of Nuclear Engineering and Radiation Science. 2:031016. 2016
- ICONE23-1731 NUMERICAL ASSESSMENT AND COMPARISON OF HEAT TRANSFER CHARACTERISTICS OF SUPERCRITICAL WATER IN BARE TUBES AND TUBES WITH HEAT TRANSFER ENHANCING APPENDAGES. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2015.23:_icone23-1-_icone23-1. 2015
- ICONE23-1797 INVESTIGATION OF CONVECTION HEAT TRANSFER OF SUPERCRITICAL WATER USING ATHLET SYSTEM CODE. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2015.23:_icone23-1-_icone23-1. 2015
- ICONE23-1936 EXPERIMENTAL INVESTIGATION OF THE THERMAL CONDUCTIVITY AND VISCOSITY OF LIQUID In-Bi-Sn EUTECTIC ALLOY (FIELD'S METAL) FOR USE IN A NATURAL CIRCULATION EXPERIENTAL LOOP. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2015.23:_icone23-1-_icone23-1. 2015
- ICONE23-2018 INNOVATIVE APPROACH TO CORRELATE HEAT-TRANSFER DATA TO SUPECRITICAL CARBON DIOXIDE FLOWING UPWARD IN A BARE TUBE. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2015.23:_icone23-2-_icone23-2. 2015
- 3-D neutron tomography method for measurement of soot deposition in silicon carbide filters. ICIC Express Letters. 8:703-708. 2014
- Performance characteristics of partially covered wire-parallel plate electrodes type electrohydrodynamic gas pumps. International Journal of Plasma Environmental Science and Technology. 7:51-58. 2013
- Performance Characteristics of Partially Covered Wire-Parallel Plate Electrodes Type Electrohydrodynamic Gas Pumps. International Journal of Plasma Environmental Science and Technology. 07:51-58. 2013
- Performance Characteristics of Partially Covered Wire-Parallel Plate Electrodes Type Electrohydrodynamic Gas Pumps. International Journal of Plasma Environmental Science and Technology. 07:51-58. 2013
- Deposited diesel soot oxidation and removal characteristics by nonthermal plasma. International Journal of Plasma Environmental Science and Technology. 5:37-41. 2011
- Fuel reforming characteristics of an electrohydrodynamic atomization - Flow stabilized radical shower hybrid system. International Journal of Plasma Environmental Science and Technology. 5:7-11. 2011
- Scoping assessment of design characteristics for an enhanced calandria tube. Nuclear Engineering and Design. 241:2688-2697. 2011
- Analytical Theory of the Geodesic Acoustic Mode in the Small and Large Orbit Drift Width Limits and its Application in a Study of Plasma Shaping Effect. Plasma Science and Technology. 13:15-20. 2011
- Deposited Diesel Soot Oxidation and Removal Characteristics by Non-thermal Plasma. International Journal of Plasma Environmental Science and Technology. 05:37-41. 2011
- Deposited Diesel Soot Oxidation and Removal Characteristics by Non-thermal Plasma. International Journal of Plasma Environmental Science and Technology. 05:37-41. 2011
- Fuel Reforming Characteristics of an Electrohydrodynamic Atomization - Flow Stabilized Radical Shower Hybrid System. International Journal of Plasma Environmental Science and Technology. 05:7-11. 2011
- Fuel Reforming Characteristics of an Electrohydrodynamic Atomization - Flow Stabilized Radical Shower Hybrid System. International Journal of Plasma Environmental Science and Technology. 05:7-11. 2011
- ICONE19-43184 TRANSIENT TWO-PHASE INTERFACIAL PARAMETER MEASUREMENTS USING ULTRASONIC PULSE-ECHO METHODS IN A NATURAL CIRCULATION LOOP. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2011.19:_ICONE1943-_ICONE1943. 2011
- ICONE19-43492 STUDY OF SELECTED TURBULENT MODELS FOR SUPERCRITICAL WATER HEAT TRANSFER IN VERTICAL BARE TUBES USING CFD CODE FLUENT-12. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2011.19:_ICONE1943-_ICONE1943. 2011
- ICONE19-43635 MODERATOR HEAT-LOSS ANALYSIS OF A CERAMIC-INSULATED RE-ENTRANT SCWR FUEL-CHANNEL. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2011.19:_ICONE1943-_ICONE1943. 2011
- ICONE19-43644 TEMPERATURE PROFILES OF A VERTICAL BARE 7-ELEMENT BUNDLE COOLED WITH SUPERCRITICAL FREON-12. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2011.19:_ICONE1943-_ICONE1943. 2011
- Discharge Characteristics of Ring-Type Flow-Stabilized Pulsed Corona Discharge Radical Shower Systems. IEEE Transactions on Industry Applications. 46:1613-1618. 2010
- Nondestructive Evaluation of Multiply Connected Electrical Arc Furnace Graphite Rod Electrodes. Research in Nondestructive Evaluation. 20:215-229. 2009
- Electrohydrodynamically enhanced capillary evaporator. IEEE Transactions on Dielectrics and Electrical Insulation. 16:456-462. 2009
- Non-Moving Component Pumping of Narrow Gas Flow Channels by an Electrohydrodynamic Gas Pumps. International Journal of Plasma Environmental Science and Technology. 03:151-155. 2009
- Plasma Suppression of Diesel Soot Deposition During Diesel Engine Operations. International Journal of Plasma Environmental Science and Technology. 03:15-21. 2009
- Plasma Suppression of Diesel Soot Deposition During Diesel Engine Operations. International Journal of Plasma Environmental Science and Technology. 03:15-21. 2009
- Flow characteristics of wire-rod type electrohydrodynamic gas pump under negative corona operations. Journal of Electrostatics. 66:342-353. 2008
- Electrohydrodynamic atomization two-phase flow regime map for liquid hydrocarbon under pulsed electric fields with co-gas flow. Journal of Electrostatics. 66:94-98. 2008
- Finned Fuel Element Two-Phase Flow Parameter Measurements Using Real-Time Neutron Radiography. Journal of Power and Energy Systems. 2:662-674. 2008
- Flow characteristics of dc wire-non-parallel plate electrohydrodynamic gas pumps. Journal of Electrostatics. 66:115-121. 2008
- Separated two-phase flow regime parameter measurement by a high speed ultrasonic pulse-echo system. Review of Scientific Instruments. 78:114901. 2007
- Electrohydrodynamically induced flow direction in a wire-non-parallel plate electrode corona discharge. Journal of Physics D: Applied Physics. 40:5109-5111. 2007
- 1651 Flow Characteristics of Wire-Non-Parallel Plate Type dc Electrohydrodynamic Gas Pumps : First report, Effect of corona wire insulating covers. The proceedings of the JSME annual meeting. 2007.2:289-290. 2007
- ICONE15-10675 EFFECT OF INLET TWO-PHASE FLOW PATTERN ON THE ANNULAR FLOW LIQUID SEPARATION PHENOMENA. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2007.15:_ICONE1510-_ICONE1510. 2007
- ICONE15-10676 FINNED FUEL ELEMENT TWO-PHASE FLOW PARAMETER MEASUREMENTS USING REAL-TIME NEUTRON RADIOGRAPHY. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2007.15:_ICONE1510-_ICONE1510. 2007
- Investigation of large amplitude stratified waves in a CANDU-type 37 rod nuclear fuel channel by a real-time neutron radiography technique. Nuclear Engineering and Design. 200:221-231. 2000
- Cross-sectional void fraction distribution measurements in a vertical annulus two-phase flow by high speed X-ray computed tomography and real-time neutron radiography techniques. Flow Measurement and Instrumentation. 10:259-266. 1999
- An image processing approach for two-phase interfaces visualized by a real time neutron radiography technique. Flow Measurement and Instrumentation. 9:203-210. 1998
- A Two-Phase Flow Regime Map for a Maple-Type Nuclear Research Reactor Fuel Channel: Effect of Hexagonal Finned Bundle. Nuclear Technology. 118:151-161. 1997
- Real-time cross-sectional averaged void fraction measurements in vertical annulus gas-liquid two-phase flow by neutron radiography and X-ray tomography techniques. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 371:544-552. 1996
- Determination of Time-Dependent Void Fraction Distribution in Bubbly Two-Phase Flow by A Real-Time Neutron Radiography Technique. Nuclear Technology. 109:132-141. 1995
- Determination of gas-liquid bubble column instantaneous interfacial area and void fraction by a real-time neutron radiography method. Chemical Engineering Science (CES). 47:3639-3646. 1992
- DPF中のPM堆積計測のための3次元中性子トモグラフィ法の開発
- SiCフィルタ中のPM観測のための3次元中性子トモグラフィ法の開発
- TV 法を用いたSiC フィルタのための中性子トモグラフィ法
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theses