SAM theory manual R Hu, L Zou, G Hu, D Nunez, T Mui, T Fei Argonne National Lab.(ANL), Argonne, IL (United States), 2021 | 153 | 2021 |
Uncertainty quantification for Multiphase-CFD simulations of bubbly flows: a machine learning-based Bayesian approach supported by high-resolution experiments Y Liu, D Wang, X Sun, N Dinh, R Hu Reliability Engineering & System Safety 212, 107636, 2021 | 53 | 2021 |
Multi-physics simulations of heat pipe micro reactor G Hu, R Hu, JM Kelly, J Ortensi Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 47 | 2019 |
Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses R Hu Nuclear Engineering and Design 345, 209-215, 2019 | 41 | 2019 |
SAM user’s guide R Hu, L Zou, G Hu, T Mui Argonne National Lab.(ANL), Argonne, IL (United States), 2021 | 40 | 2021 |
A momentum source model for wire-wrapped rod bundles—Concept, validation, and application R Hu, TH Fanning Nuclear Engineering and Design 262, 371-389, 2013 | 39 | 2013 |
A fully-implicit high-order system thermal-hydraulics model for advanced non-LWR safety analyses R Hu Annals of Nuclear Energy 101, 174-181, 2017 | 38 | 2017 |
Multiphysics for nuclear energy applications using a cohesive computational framework R Martineau, D Andrs, R Carlsen, D Gaston, J Hansel, F Kong, A Lindsay, ... Nuclear Engineering and Design 367, 110751, 2020 | 27 | 2020 |
SAM Theory Manual, Argonne National Laboratory R Hu ANL/NE-17/4, March, 2017 | 25 | 2017 |
Development of a thermal–hydraulic system code for simulators based on RELAP5 code M Lin, Y Su, R Hu, R Zhang, Y Yang Nuclear engineering and design 235 (6), 675-686, 2005 | 25 | 2005 |
New reactor cavity cooling system having passive safety features using novel shape for HTGRs and VHTRs K Takamatsu, R Hu Annals of Nuclear Energy 77, 165-171, 2015 | 24 | 2015 |
Neutronic design and analysis of the holos-quad concept N Stauff, C Lee, P Shriwise, Y Miao, R Hu, P Vegendla, T Fei Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 23 | 2019 |
Final project report on rccs testing with air-based nstf DD Lisowski, CD Gerardi, DJ Kilsdonk, NC Bremer, SW Lomperski, R Hu, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 23 | 2016 |
An advanced one-dimensional finite element model for incompressible thermally expandable flow R Hu Nuclear Technology 190 (3), 313-322, 2015 | 23 | 2015 |
Data-driven modeling of coarse mesh turbulence for reactor transient analysis using convolutional recurrent neural networks Y Liu, R Hu, A Kraus, P Balaprakash, A Obabko Nuclear Engineering and Design 390, 111716, 2022 | 22 | 2022 |
Explicit modeling of pebble temperature in the porous-media model for pebble-bed reactors L Zou, G Hu, D O'Grady, R Hu Progress in Nuclear Energy 146, 104175, 2022 | 22 | 2022 |
Development of heat pipe reactor modeling in sam G Hu, R Hu, L Zou Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 22 | 2019 |
Moose navier–stokes module A Lindsay, G Giudicelli, P German, J Peterson, Y Wang, R Freile, D Andrs, ... SoftwareX 23, 101503, 2023 | 21 | 2023 |
Recent SAM Code Improvement to Heat Transfer Modeling Capabilities L Zou, R Hu Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 21 | 2019 |
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 | 21 | 2016 |