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Guojun Hu
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Cited by
Year
SAM theory manual
R Hu, L Zou, G Hu, D Nunez, T Mui, T Fei
Argonne National Lab.(ANL), Argonne, IL (United States), 2021
1372021
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
412019
Inverse uncertainty quantification of TRACE physical model parameters using sparse gird stochastic collocation surrogate model
X Wu, T Mui, G Hu, H Meidani, T Kozlowski
Nuclear Engineering and Design 319, 185-200, 2017
392017
SAM user’s guide
R Hu, L Zou, G Hu, T Mui
Argonne National Lab.(ANL), Argonne, IL (United States), 2021
342021
Inverse uncertainty quantification of trace physical model parameters using BFBT benchmark data
G Hu, T Kozlowski
Annals of Nuclear Energy 96, 197-203, 2016
312016
A roe-type numerical solver for the two-phase two-fluid six-equation model with realistic equation of state
G Hu, T Kozlowski
Nuclear Engineering and Design 326, 354-370, 2018
252018
Development of Heat Pipe Reactor Modeling in SAM
G Hu, R Hu, L Zou
Argonne National Laboratory, 2019
222019
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
Application of implicit Roe-type scheme and Jacobian-Free Newton-Krylov method to two-phase flow problems
G Hu, T Kozlowski
Annals of Nuclear Energy 119, 180-190, 2018
172018
Reactivity feedback modeling in sam
G Hu, G Zhang, R Hu
Argonne National Lab.(ANL), Argonne, IL (United States), 2019
142019
Application of continuous adjoint method to steady-state two-phase flow simulations
G Hu, T Kozlowski
Annals of Nuclear Energy 117, 202–212, 2018
122018
ORIGEN: Neutron activation, actinide transmutation, fission product generation, and radiation source term calculation
W Wieselquist, S Hart, A Isotalo, F Havluj, S Skutnik, R Lefebvre, I Gauld, ...
SCALE Manual, 3-5, 2016
122016
SAM Code Development for Transient Safety Analyses of Fluoride-salt-cooled High-temperature Reactors
D O'Grady, T Mui, L Zou, G Hu, R Hu
Argonne National Lab.(ANL), Argonne, IL (United States), 2022
82022
Code Enhancement to SAM Multi-scale/multi-dimensional Heat Transfer Modeling Capabilities
L Zou, G Hu, R Hu
American Nuclear Society Virtual Winter Meeting (Chicago, IL, US, 11/16/2020 …, 2020
72020
Application of discrete adjoint method to sensitivity and uncertainty analysis in steady-state two-phase flow simulations
G Hu, T Kozlowski
Annals of Nuclear Energy 126, 122-132, 2019
72019
Adjoint Sensitivity Analysis of the Two-Phase Two-Fluid Model Based On An Approximate Riemann Solver
G Hu
University of Illinois at Urbana-Champaign, 2018
72018
Code validation of SAM using natural-circulation experimental data from the compact integral effects test (CIET) facility
L Zou, G Hu, D O'Grady, R Hu
Nuclear Engineering and Design 377, 111144, 2021
62021
SAM code enhancement, validation, and reference model development for fluoride-salt-cooled high-temperature reactors
D O'Grady, T Mui, A Lee, L Zou, G Hu, R Hu
Argonne National Lab.(ANL), Argonne, IL (United States), 2021
62021
Sam developments to support transient safety analysis of advanced non-lwrs
R Hu, G Hu, L Zou, G Zhang, B Hollrah, M Gorman
Argonne National Lab.(ANL), Argonne, IL (United States), 2019
62019
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