| Fission product release modelling for application of fuel-failure monitoring and detection-An overview BJ Lewis, PK Chan, A El-Jaby, FC Iglesias, A Fitchett Journal of Nuclear Materials 489, 64-83, 2017 | 58 | 2017 |
| Multiphysics coupled modeling of light water reactor fuel performance R Liu, A Prudil, W Zhou, PK Chan Progress in Nuclear Energy 91, 38-48, 2016 | 47 | 2016 |
| Fully coupled multiphysics modeling of enhanced thermal conductivity UO2–BeO fuel performance in a light water reactor R Liu, W Zhou, P Shen, A Prudil, PK Chan Nuclear Engineering and Design 295, 511-523, 2015 | 42 | 2015 |
| Growth and characterization of oxide films on zirconium-niobium alloys VF Urbanic, PK Chan, D Khatamian, OTT Woo Zirconium in the Nuclear Industry: Tenth International Symposium, 1994 | 34 | 1994 |
| Multiphysics modeling of UO2-SiC composite fuel performance with enhanced thermal and mechanical properties R Liu, W Zhou, A Prudil, PK Chan Applied Thermal Engineering 107, 86-100, 2016 | 32 | 2016 |
| Development and testing of the FAST fuel performance code: Normal operating conditions (Part 1) A Prudil, BJ Lewis, PK Chan, JJ Baschuk Nuclear Engineering and Design 282, 158-168, 2015 | 29 | 2015 |
| Development and testing of the FAST fuel performance code: Transient conditions (Part 2) A Prudil, BJ Lewis, PK Chan, JJ Baschuk, D Wowk Nuclear Engineering and Design 282, 169-177, 2015 | 19 | 2015 |
| Variation of burnable neutron absorbers in a heavy water–moderated fuel lattice: A potential to improve CANDU reactor operating margins PK Chan, S Paquette, HW Bonin Nuclear Technology 191 (1), 1-14, 2015 | 12 | 2015 |
| Zirconium in the Nuclear Industry: Tenth International Symposium VF Urbanic, PK Chan, D Khatamian, OT Woo ASTM STP 1245, 116, 1994 | 11 | 1994 |
| Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings Revisited GA Ferrier, M Farahani, J Metzler, PK Chan, EC Corcoran Journal of Nuclear Engineering and Radiation Science 2 (2), 021004, 2016 | 10 | 2016 |
| Protective coating to reduce stress corrosion cracking in zirconium alloy sheathing PKH Chan US Patent 5,805,655, 1998 | 10 | 1998 |
| The role of ZrxIyC compounds in minimizing stress corrosion cracking in fuel cladding PK Chan, KG Irving, JR Mitchell | 8 | 1992 |
| Thorium-based nuclear fuel performance modelling with multi-pellet material fuel and sheath modelling tool JS Bell | 7 | 2017 |
| Neutron absorbers in candu natural uranium fuel bundles to improve operating margins PK Chan, S Paquette, HW Bonin, C French, A Pant International Conference on Nuclear Engineering 55782, V001T02A030, 2013 | 7 | 2013 |
| How does CANLUB work? PK Chan, KJ Kaddatz | 7 | 1994 |
| Circulation of cosmogenic 22Na using the global monitoring network of the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) I Hoffman, B Lewis, P Chan Journal of Environmental Radioactivity 187, 8-15, 2018 | 6 | 2018 |
| Fueling Study of a CANDU Reactor Using Fuels Containing Burnable Neutron Absorbers JJ Song, PK Chan, HW Bonin, S Paquette Nuclear Technology 195 (3), 310-328, 2016 | 6 | 2016 |
| Reactor power monitoring using Cherenkov radiation transmitted through a small-bore metallic tube G Bentoumi, B Benson, PK Chan, M Gaudet, G Li, L Li, P Samuleev, B Sur Annals of Nuclear Energy 114, 86-91, 2018 | 5 | 2018 |
| The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle M Lovecký, R Škoda, MS Hussein, JJ Song, PK Chan Progress in Nuclear Energy 90, 127-139, 2016 | 5 | 2016 |
| A Solid Element Approach to Analyzing CANDU Fuel Element Behaviour Under Post-Dryout Heat Transfer Conditions CJ Krasnaj | 5 | 2015 |
