selected scholarly activity
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books
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chapters
- Asset Integrity Under Extreme and disruptive events. 37-39. 2024
- Integrity Management of Critical Systems. 77-78. 2024
- 23 Elements of thermal hydraulic design of water-cooled nuclear reactors. 379-455. 2024
- Regulatory and licensing challenges with Generation-IV nuclear energy systems. 837-864. 2023
- Atucha II plant description. 1-49. 2022
- Design and aging management for feeder pipe and feeder supports. 171-227. 2022
- Preface to Volume 7: Pressurized Heavy Water Reactors: CANDU. xvii-xviii. 2022
- Preface to Volume 8: Pressurized Heavy Water Reactors: Atucha II. xv-xvi. 2022
- 1 Introduction to steam generators—from Heron of Alexandria to nuclear power plants Brief history and literature survey. 3-33. 2017
- Introduction to steam generators-from Heron of Alexandria to nuclear power plants: Brief history and literature survey. 3-33. 2017
- Introduction to steam generators—from Heron of Alexandria to nuclear power plants. 3-33. 2017
- Steam Generators for Nuclear Power Plants Preface. XIII-XIV. 2017
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conferences
- Geometrical Effect of Tube Array on Prediction of Fluidelastic Instability – Single Phase Air Flow. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. 2023
- Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP. Volume 9: Student Paper Competition. 2018
- Component operational experience, degradation and ageing programme (CODAP): Applications and contributions. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- The component operational experience, degradation, and ageing programme (CODAP) project; Canadian contribution to the CODAP and application to Candu nuclear power plants. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- The nuclear energy agency contribution to nuclear materials performance knowledge preservation. NACE - International Corrosion Conference Series. 1-13. 2018
- Assessment of Choking Flow Models in RELAP5 for Subcooled Choking Flow Through a Small Axial Crack of a Steam Generator Tube. Volume 9: Student Paper Competition. 2017
- The Current Status of CANDU Steam Generators. Volume 9: Student Paper Competition. 2017
- The component operational experience, degradation and ageing programme (CODAP) Project; Canada's contributions and capabilities of the program. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS Cna Student Conference. 2017
- Experimental Investigation of Subcooled Choking Flow in a Steam Generator Tube Crack. Volume 5: Student Paper Competition. 2016
- The component operational experience, degradation and ageing programme (CODAP) project; Canada's contributions and benefits to the Canadian industry. 36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role. 2016
- An Experimental Study of Steam Generator Tube Loading During Blowdown. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. 2015
- Experimental and analytical study of flashing flow through steam generator tube cracks. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015 Nureth 2015. 1116-1129. 2015
- MODELING CRITICAL FLOW THROUGH STEAM GENERATOR TUBE CRACKS. ASME INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2014, VOL 6B. 2015
- Modeling critical flow in crack geometries using trace. International Conference on Nuclear Engineering Proceedings ICONE. 2015
- The component operational experience degradation and ageing program (CODAP): Review and lessons learned (2011-2014). International Conference on Nuclear Engineering Proceedings ICONE. 2015
- Modeling Critical Flow Through Steam Generator Tube Cracks. Volume 6B: Energy. v06bt07a032-v06bt07a032. 2014
- Crack Growth Prediction and Leakage Potential of Steam Generator Tubes Subjected to Flow Induced Vibrations. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. 2014
- Instrumentation Development and Validation for an Experimental Study of Steam Generator Tube Loading During Blowdown. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. 2014
- Choking Flow of Subcooled Liquid in Steam Generator Tube Wall Cracks. Volume 2A: Thermal Hydraulics. 2014
- Experimental and Theoretical Analysis of Subcooled Water Discharge Through Simulated Steam Generator Tube Cracks. Volume 8C: Heat Transfer and Thermal Engineering. 2013
- Assessment of Choking Flow Models in RELAP5 for Flashing Flow Through Small Cracks. Volume 4: Thermal Hydraulics. 2013
- Commissioning Tests for an Experimental Study of Steam Generator Tube Loading During Blowdown. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. 2013
- Probabilistic Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. 2013
- Flashing Flow of Subcooled Liquid through Small Cracks. Procedia Engineering. 454-461. 2013
- OECD-NEA CODAP event data project on passive component degradation & failures in commercial nuclear power plants. International Topical Meeting on Probabilistic Safety Assessment and Analysis 2013 Psa 2013. 663-672. 2013
- A Probabilistic Assessment of Flow-Accelerated Corrosion Rate in Pipe Bends With Unknown Initial Thickness. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles. 435-+. 2012
- Experiments on Choking Flow of Subcooled Liquid Through a Simulated Steam Generator Tube Crack. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles. 41-+. 2012
- Model for Choking of Subcooled Flashing Flow Through a Steam Generator Tube Crack. Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries. 27-36. 2012
- Applicability of Choking Flow Models for Subcooled Flashing Flow Through Tube Cracks. Volume 10: Heat and Mass Transport Processes, Parts A and B. 1199-1207. 2011
- Experimental Investigation of Subcooled Flashing Flow in Simulated Cracks. Volume 10: Heat and Mass Transport Processes, Parts A and B. 1189-1197. 2011
- Consideration of inspection uncertainties in the probabilistic assessment of steam generator tubing. Canadian Nuclear Society 31st Annual Conference of the Canadian Nuclear Society and 34th CNS Cna Student Conference 2010. 1500-1514. 2010
- Material Surveillance Program Regulatory Guidance for Steam Generator Tubes Extracted From Canadian CANDU Reactors. 18th International Conference on Nuclear Engineering: Volume 5. 57-+. 2010
- A Stochastic Model for Piping Failure Frequency Analysis Using OPDE Data. Journal of Engineering for Gas Turbines and Power. 2009
- Bayesian Analysis of Piping Failure Frequency Using OECD/NEA Data. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. 459-467. 2009
- Bayesian Determination of Sample Sizes for Inspections of Feeder Hangers. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. 755-763. 2009
- Crack Growth Model for the Probabilistic Assessment of Inspection Strategies for Steam Generator Tubes. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. 615-621. 2009
- Evaluation of crack opening area, leak rate and probabilistic models in CANTIA. International Conference on Advances in Nuclear Power Plants Icapp 2008. 1725-1734. 2008
- A Point Process Model for Piping Failure Frequency Analysis Using OPDE Data. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. 433-441. 2008
- CANTIA Code for the Probabilistic Assessment of Inspection Strategies for Steam Generator Tubes. Volume 10: Heat Transfer, Fluid Flows, and Thermal Systems, Parts A, B, and C. 1923-1932. 2008
- Assessment of steam generator tube flaw size and leak rate models. Proceedings 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Nureth 12. 2007
- Modeling pitting growth data and predicting degradation trend. Canadian Nuclear Society 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007. 1869-1876. 2007
- The OECD Pipe Failure Data Exchange Project: Validation of Canadian Data. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. 389-400. 2006
- The OECD Pipe Failure Data Exchange Project: Data Validation on Canadian Plants. 12th International Conference on Nuclear Engineering, Volume 1. 65-70. 2004
- Pressure tube ballooning experiments analysis. Proceedings Annual Conference Canadian Nuclear Association. 1997
- Analysis of human error probabilities in nuclear power plants operation. TOPFORM '95 - PROCEEDINGS OF THE SFEN/ENS INTERNATIONAL CONFERENCE. 370-380. 1995
- Strange attractors and chaos in boiling flows. American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD. 81-90. 1994
- Flow regimes classification and spatio-temporal complexities in flashing flow. American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD. 1-9. 1993
- Thermal-hydraulics of hollow geometry reactor fuel element in transient conditions. American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD. 1-5. 1991
- MUNGOS - FULLY INTERACTIVE MODEL FOR SUBCHANNEL ANALYSIS. Proceeding of International Heat Transfer Conference 8. 2411-2416. 1986
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journal articles
- Techno-Economic Comparison of a Large-Scale Nuclear Power Plant, Small Modular Reactors, and Wind and Solar Power Plant Deployment. Energies. 18:2355. 2025
- Investigation of Fluidelastic Instability in Parallel Triangular Tube Arrays Subjected to Air Flow. Journal of Pressure Vessel Technology, Transactions of the ASME. 146. 2024
- What is the future for nuclear fission technology? A technical opinion from the Guest Editors of VSI NFT series and the Editor of the Journal Nuclear Engineering and Design. Nuclear Engineering and Design. 425:113332-113332. 2024
- Effect of Pitch Ratio and Tube Support Conditions on the Dynamic Behavior of a Low Mass-Damping Parameter Parallel Triangular Array. Journal of Pressure Vessel Technology, Transactions of the ASME. 146. 2024
- Investigation of Fluidelastic Instability in Normal Triangular Tube Arrays Subjected to Air Flow. Journal of Pressure Vessel Technology, Transactions of the ASME. 146. 2024
- Nuclear reactor Thermal-Hydraulics Special and prospective topical areas. Nuclear Engineering and Design. 409:112354-112354. 2023
- Handbook of Generation IV Nuclear Reactors Edition 2. Journal of Nuclear Engineering and Radiation Science. 9. 2023
- From NURETH-2013 to NURETH-2019: Non-Critical summary and brief contribution to the history of nuclear reactor thermal hydraulics. Nuclear Engineering and Design. 403:112153-112153. 2023
- On Eight Years of the NERS and Vision of the Nuclear Engineering Division. Journal of Nuclear Engineering and Radiation Science. 9. 2023
- OECD nuclear energy agency CODAP database project on passive component operating experience. An international collaboration in materials research. Nuclear Engineering and Design. 380:111280-111280. 2021
- A Welcome Message from Chikako Iwaki, JSME Conference Chair 2021
- A Welcome Message from Hiroyuki Kawada, JSME President 2021
- A Welcome Message from Wang Shoujun, CNS President 2021
- Opening Reception sponsored by Westinghouse with opening remarks from Jeffrey Bradfute 2021
- Thermal hydraulics aspects of leakage through cracked thin wall tubes 2021
- Welcome Message from the POWER2020 and ICONE Organizing Committee 2021
- Welcome to Day 2 - ASME Virtual POWER2020 and Nuclear Engineering Conference powered by ICONE 2021
- Special Section: Selected Papers from ICONE-27. Journal of Nuclear Engineering and Radiation Science. 6. 2020
- A New Capacitance Sensor for Measuring the Void Fraction of Two-Phase Flow Through Tube Bundles. Sensors. 20:2088-2088. 2020
- Special Section: ICONE-26. Journal of Nuclear Engineering and Radiation Science. 6. 2020
- Special Section: ICONE-26. Journal of Nuclear Engineering and Radiation Science. 6. 2020
- Reviewer's Recognition. Journal of Nuclear Engineering and Radiation Science. 6. 2020
- An experimental investigation of subcooled choked flow in actual steam generator tube cracks. Nuclear Engineering and Design. 354:110144-110144. 2019
- The life and the contribution of B. R. Sehgal, G. Yadigaroglu and G. Hewitt: Remembrance statements. Nuclear Engineering and Design. 354:110252-110252. 2019
- Theoretical and Experimental Investigation of Subcooled Flashing Flow through Simulated Steam Generator Tube Cracks. Heat Transfer Engineering. 40:524-536. 2019
- Some Current and Future Activities (Events). Mechanical Engineering. 141:50-51. 2019
- The Nuclear Renaissance and the International Conference on Nuclear Engineering. Mechanical Engineering. 141:51-51. 2019
- Transient two-phase blowdown: Experiments and analysis. International Journal of Multiphase Flow. 104:307-321. 2018
- Guest editorial. Journal of Nuclear Engineering and Radiation Science. 4. 2018
- Special Section: Selected and Revised Papers From ICONE-24. Journal of Nuclear Engineering and Radiation Science. 4. 2018
- Handbook of Generation-IV Nuclear Reactors. Journal of Nuclear Engineering and Radiation Science. 3. 2017
- 60 Years in Motion: Short History of Nuclear Engineering Division. Journal of Nuclear Engineering and Radiation Science. 3. 2017
- Guest Editorial:Special Issue: ICONE-23. Journal of Nuclear Engineering and Radiation Science. 2. 2016
- An Experimental Model Study of Steam Generator Tube Loading During a Sudden Depressurization. Journal of Pressure Vessel Technology, Transactions of the ASME. 138. 2016
- Instrumentation Development and Validation for an Experimental Two-Phase Blowdown Facility. Journal of Pressure Vessel Technology, Transactions of the ASME. 138. 2016
- A comprehensive flow-induced vibration model to predict crack growth and leakage potential in steam generator tubes. Nuclear Engineering and Design. 292:17-31. 2015
- Special Section: Selected Papers from the 2014 ASME IMECE in Montreal. Journal of Nuclear Engineering and Radiation Science. 1. 2015
- ICONE23-1001 THE COMPONENT OPERATIONAL EXPERIENCE DEGRADATION AND AGEING PROGRAM (CODAP) : REVIEW AND LESSONS LEARNED (2011-2014). The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2015.23:_icone23-1-_icone23-1. 2015
- ICONE23-2115 MODELING CRITICAL FLOW IN CRACK GEOMETRIES USING TRACE. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2015.23:_icone23-2-_icone23-2. 2015
- Material challenges for advanced reactors. Nuclear Engineering and Design. 280:651-651. 2014
- Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations. Journal of Pressure Vessel Technology, Transactions of the ASME. 136. 2014
- A Message From the Chair of the ASME Nuclear Engineering Division. Mechanical Engineering. 136:57-69. 2014
- To the special issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14). Nuclear Engineering and Design. 264:1-2. 2013
- New Monographs Series on Nuclear Technology for the 21st Century. Mechanical Engineering. 135:51-51. 2013
- Foreword: Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics. Nuclear Technology. 181:1-1. 2013
- INVESTIGATION OF SUBCOOLEDWATER DISCHARGE THROUGH SIMULATED STEAM GENERATOR TUBE CRACKS. Multiphase Science and Technology. 25:249-285. 2013
- SPECIAL ISSUE ON THE 14TH INTERNATIONAL TOPICAL MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS FOREWORD. Nuclear Technology. 181:1-1. 2013
- Preface to Special Issue — Part 2 of Selected Contributions from 14th International Topical Meeting on Nuclear Reactor Thermal hydraulics NURETH-14 in Toronto. Journal of Computational Multiphase Flows. 4:i-i. 2012
- Preface to Special Issue — Part I of Selected Contributions from 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH-14 in Toronto. Journal of Computational Multiphase Flows. 4:i-i. 2012
- Pressure Surges in Nuclear Power Plants – selected contributions for the homonymous mini-symposium of the NURETH-14 in Toronto. Kerntechnik. 77:81-82. 2012
- Preface. Nuclear Engineering and Design. 241:1287-1287. 2011
- ICONE19-43020 APPLICATION OF CONCEPT MAPPING PRINCIPLES TO MANAGING STEAM GENERATOR KNOWLEDGE AT CNSC. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2011.19:_ICONE1943-_ICONE1943. 2011
- ICONE19-43676 Assessment of Choking Flow Models for Subcooled Flashing Flow through Steam Generator Tube Cracks. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2011.19:_ICONE1943-_ICONE1943. 2011
- Bayesian Analysis of Piping Leak Frequency Using OECD/NEA Data. Journal of Engineering for Gas Turbines and Power. 132. 2010
- The Logical Framework Approach-Millennium. Project Management Journal. 40:31-44. 2009
- Assessment of Steam Generator Tube Flaw Size and Leak Rate Models. Nuclear Technology. 167:157-168. 2009
- OPDE—The international pipe failure data exchange project. Nuclear Engineering and Design. 238:2115-2123. 2008
- Program management for improved business results. EMJ - Engineering Management Journal. 19:51-51. 2007
- Shape and structure from engineering to nature, author Adrian Bejan, Cambridge university press, ISBN 0-521-79049-2. Thermal Science. 10:141-142. 2006
- ICONE11-36387 DISCRETE SCALE INVARIANCE METHOD FOR PREDICTING TUBE RUPTURE. The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2003:421-421. 2003
- On the Spherically Symmetric Phase Change Problem. International Journal of Fluid Mechanics Research. 26:110-145. 1999
- Experimental Studies of Interfacial Area in a Horizontal Slug Flow. American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD. 1996-AJ:27-37. 1996
- Strange attractors and chaotic dynamics in boiling flows. International Journal of Heat and Technology. 14:3-19. 1996
- Spatio-temporal complexities and chaos in a two-phase flashing flow. Nuclear Engineering and Design. 149:53-66. 1994
- Study of two-phase bubbly flow dynamics in binary mixtures. Shock Waves. 2:49-56. 1992
- Air pollution from coal-fired power plants in comparison with other energy sources. International Journal of Global Energy Issues. 4:74-78. 1992
- Professor Naim H. Afgan on his 60th birthday. International Journal of Heat and Mass Transfer. 33:1045-1046. 1990
- Bubble number density and vapor generation in flashing flow. International Journal of Heat and Mass Transfer. 32:1821-1833. 1989
- The empirical failure rate and repair rate of PWR primary coolant pumps. Reliability Engineering & System Safety. 24:267-273. 1989
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preprints