关注
Rui Hu
Rui Hu
在 anl.gov 的电子邮件经过验证
标题
引用次数
引用次数
年份
SAM theory manual
R Hu, L Zou, G Hu, D Nunez, T Mui, T Fei
Argonne National Lab.(ANL), Argonne, IL (United States), 2021
1342021
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
422021
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
402019
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
392019
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
372017
SAM user’s guide
R Hu, L Zou, G Hu, T Mui
Argonne National Lab.(ANL), Argonne, IL (United States), 2021
322021
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
322013
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
272020
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
252005
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
242015
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
232019
SAM Theory Manual, Argonne National Laboratory
R Hu
ANL/NE-17/4, March, 2017
232017
Development of heat pipe reactor modeling in sam
G Hu, R Hu, L Zou
Argonne National Lab.(ANL), Argonne, IL (United States), 2019
222019
An advanced one-dimensional finite element model for incompressible thermally expandable flow
R Hu
Nuclear Technology 190 (3), 313-322, 2015
222015
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
212016
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
202016
MSRE Transient benchmarks using SAM
T Fei, T Hua, B Feng, F Heidet, R Hu
EPJ Web of Conferences 247, 07008, 2021
182021
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
172022
Development of a reference model for molten-salt-cooled pebble-bed reactor using sam
G Hu, D O'Grady, L Zou, R Hu
Argonne National Lab.(ANL), Argonne, IL (United States), 2020
172020
Recent SAM Code Improvement to Heat Transfer Modeling Capabilities
L Zou, R Hu
Argonne National Lab.(ANL), Argonne, IL (United States), 2019
172019
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