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Yiqi Yu
Yiqi Yu
Verified email at anl.gov
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Year
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
552017
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
492020
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
462012
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
432014
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
292020
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
252015
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
232014
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
212011
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
192017
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
192016
Local thermal–hydraulic behaviour in tight 7-rod bundles
X Cheng, YQ Yu
Nuclear engineering and design 239 (10), 1944-1955, 2009
182009
SHARP user manual
YQ Yu, ER Shemon, JW Thomas, VS Mahadevan, RO Rahaman, ...
Argonne National Lab.(ANL), Argonne, IL (United States), 2016
172016
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
142015
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
112008
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
102020
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
82015
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
82013
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), 1207-1211, 2012
82012
Demonstration of NEAMS Multiphysics Tools for Fast Reactor Applications
ER Shemon, Y Yu, TK Kim
Argonne National Lab.(ANL), Argonne, IL (United States), 2020
72020
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
72019
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