| A CFD simulation of 5× 5 rod bundles with split-type spacers K Podila, YF Rao, M Krause, J Bailey Progress in Nuclear Energy 70, 167-175, 2014 | 46 | 2014 |
| CFD modelling of turbulent flows through 5× 5 fuel rod bundles with spacer-grids K Podila, Y Rao Annals of Nuclear Energy 97, 86-95, 2016 | 44 | 2016 |
| CFD analysis of flow and heat transfer in Canadian supercritical water reactor bundle K Podila, YF Rao Annals of Nuclear Energy 75, 1-10, 2015 | 34 | 2015 |
| CFD modelling of supercritical water flow and heat transfer in a 2× 2 fuel rod bundle K Podila, Y Rao Nuclear Engineering and Design 301, 279-289, 2016 | 32 | 2016 |
| Assessment of CFD for the Canadian SCWR bundle with wire wraps K Podila, YF Rao Progress in Nuclear Energy 77, 373-380, 2014 | 28 | 2014 |
| CFD simulation of gas–liquid contacting in tubular reactors K Podila, AM Al Taweel, M Koksal, A Troshko, YP Gupta Chemical Engineering Science 62 (24), 7151-7162, 2007 | 22 | 2007 |
| CFD simulations of molten salt reactor experiment core K Podila, Q Chen, Y Rao Nuclear Science and Engineering 193 (12), 1379-1393, 2019 | 14 | 2019 |
| Assessment of computational tools in support of heat-transfer correlation development for fuel assembly of Canadian supercritical water-cooled reactor LKH Leung, Y Rao, K Podila Journal of Nuclear Engineering and Radiation Science 2 (1), 011006, 2016 | 11 | 2016 |
| CFD simulation of heated tight-lattice rod bundles for an IAEA benchmark K Podila, YF Rao Progress in Nuclear Energy 108, 222-232, 2018 | 10 | 2018 |
| Assessment of subchannel code ASSERT-PV for supercritical applications YF Rao, EN Onder, K Podila The Journal of Supercritical Fluids 117, 164-171, 2016 | 10 | 2016 |
| Summary on the results of two computational fluid dynamic benchmarks of tube and different channel geometries A Kiss, A Churkin, DS Pilkhwal, AM Vaidya, W Ambrosini, A Pucciarelli, ... Journal of Nuclear Engineering and Radiation Science 4 (1), 011001, 2018 | 8 | 2018 |
| CFD simulation of multiphase flow: closure recommendations for fluid–fluid systems AM Al Taweel, S Madhavan, K Podila, M Koksal, A Troshko, YP Gupta Proceedings of 12th European Conference on Mixing, Bologna, Italy, 495-502, 2006 | 8 | 2006 |
| CFD simulation of vertical 7-element bundle cooled with supercritical Freon-12 X Huang, K Podila, YF Rao Atomic Energy of Canada Limited, 2013 | 7 | 2013 |
| Computational fluid dynamic simulations of heat transfer from a 2× 2 wire-wrapped fuel rod bundle to supercritical pressure water K Podila, Y Rao Journal of Nuclear Engineering and Radiation Science 4 (1), 011008, 2018 | 6 | 2018 |
| Assessment of CFD for unheated gas-liquid flows with high void fraction Q Chen, K Podila, YF Rao, R Bowden, SK Yang Nuclear Engineering and Design 341, 346-359, 2019 | 5 | 2019 |
| Coupled simulations for prismatic gas-cooled reactor K Podila, Q Chen, X Huang, C Li, Y Rao, G Waddington, T Jafri Nuclear Engineering and Design 395, 111858, 2022 | 4 | 2022 |
| Canadian participation in OECD/NEA-KAERI ROD bundle benchmark for CFD codes J Szymanski, D Chang, D Novog, K Podila, J Bailey, Y Rao, A Rashkovan, ... Proc. 24th Nuclear Simulation Symp., Ottawa, Canada, 2012 | 4 | 2012 |
| Application of high-fidelity modelling approach to predict smoke and fire propagation in a nuclear fire scenario A John, K Podila, Q Chen, Y Rao Thermal Science and Engineering Progress 23, 100903, 2021 | 3 | 2021 |
| Computational fluid dynamics modeling of fire and human evacuation for nuclear applications L Sun, K Podila, Q Chen, AM Bayomy, YF Rao Journal of Nuclear Engineering and Radiation Science 6 (1), 011112, 2020 | 3 | 2020 |
| Estimation of appendage pressure-loss coefficients for fuel rod bundles using computational fluid dynamics K Podila, YF Rao Annals of Nuclear Energy 112, 597-602, 2018 | 3 | 2018 |
