| Large-scale large eddy simulation of nuclear reactor flows: Issues and perspectives E Merzari, A Obabko, P Fischer, N Halford, J Walker, A Siegel, Y Yu Nuclear Engineering and Design 312, 86-98, 2017 | 60 | 2017 |
| Toward exascale: overview of large eddy simulations and direct numerical simulations of nuclear reactor flows with the spectral element method in Nek5000 E Merzari, P Fischer, M Min, S Kerkemeier, A Obabko, D Shaver, H Yuan, ... Nuclear Technology 206 (9), 1308-1324, 2020 | 54 | 2020 |
| Experimental study of water film falling and spreading on a large vertical plate YQ Yu, SJ Wei, YH Yang, X Cheng Progress in Nuclear Energy 54 (1), 22-28, 2012 | 49 | 2012 |
| Experimental study of water film flow on large vertical and inclined flat plate YQ Yu, X Cheng Progress in Nuclear Energy 77, 176-186, 2014 | 46 | 2014 |
| Spectral element applications in complex nuclear reactor geometries: Tet-to-hex meshing H Yuan, MA Yildiz, E Merzari, Y Yu, A Obabko, G Botha, G Busco, ... Nuclear Engineering and design 357, 110422, 2020 | 28 | 2020 |
| A porous medium model for predicting the duct wall temperature of sodium fast reactor fuel assembly Y Yu, E Merzari, A Obabko, J Thomas Nuclear Engineering and Design 295, 48-58, 2015 | 25 | 2015 |
| Three-dimensional simulation on behavior of water film flow with and without shear stress on water–air interface YQ Yu, X Cheng International Journal of Heat and Mass Transfer 79, 561-572, 2014 | 24 | 2014 |
| Simulation of turbulent flow inside different subchannels in tight lattice bundle YQ Yu, BH Yan, X Cheng, HY Gu Annals of Nuclear Energy 38 (11), 2363-2373, 2011 | 23 | 2011 |
| Local thermal–hydraulic behaviour in tight 7-rod bundles X Cheng, YQ Yu Nuclear engineering and design 239 (10), 1944-1955, 2009 | 20 | 2009 |
| A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors R Hu, Y Yu Nuclear Engineering and Design 308, 182-193, 2016 | 19 | 2016 |
| Steady and unsteady calculations on thermal striping phenomena in triple-parallel jet YQ Yu, E Merzari, JW Thomas, A Obabko, SM Aithal Nuclear Engineering and Design 312, 429-437, 2017 | 18 | 2017 |
| SHARP user manual YQ Yu, ER Shemon, JW Thomas, VS Mahadevan, RO Rahaman, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 15 | 2016 |
| Multi-physics demonstration problem with the sharp reactor simulation toolkit E Merzari, ER Shemon, YQ Yu, JW Thomas, A Obabko, R Jain, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2015 | 14 | 2015 |
| Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels H Gu, X Cheng, X Liu International Conference on Nuclear Engineering 48159, 563-571, 2008 | 11 | 2008 |
| Evaluation of hot channel factor for sodium-cooled fast reactors with multi-physics toolkit Y Yu, ER Shemon, TK Kim, E Merzari Nuclear Engineering and Design 365, 110704, 2020 | 10 | 2020 |
| Status Report on NEAMS System Analysis Module Development R Hu, TH Fanning, T Sumner, Y Yu Argonne National Lab.(ANL), Argonne, IL (United States), 2015 | 8 | 2015 |
| Coolant distribution and mixing at the core inlet of PWR in a real geometry G Zhang, YH Yang, HY Gu, YQ Yu Annals of Nuclear Energy 60, 187-194, 2013 | 8 | 2013 |
| 降膜流动行为的数值模拟研究 于意奇， 杨燕华， 程旭， 顾汉洋 原子能科学技术 46 (10), 1207, 2012 | 8 | 2012 |
| Demonstration of NEAMS Multiphysics Tools for Fast Reactor Applications ER Shemon, Y Yu, TK Kim Argonne National Lab.(ANL), Argonne, IL (United States), 2020 | 7 | 2020 |
| Extension and Demonstration of NEAMS Multiphysics Tools to Lead-Cooled, Sodium-Cooled, and Molten Salt Fast Reactor Applications ER Shemon, Y Yu, YS Jung, B Feng, TK Kim Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 7 | 2019 |
Elia MerzariPennsylvania State University, Argonne National Laboratory在 anl.gov 的电子邮件经过验证
