selected scholarly activity
-
books
-
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
-
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. The 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. The 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
-
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
-
preprints