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Adam Kraus
Adam Kraus
Nuclear Engineer, Argonne National Laboratory; PhD Candidate, Penn State University
Verified email at anl.gov
Title
Cited by
Cited by
Year
Flow-induced vibration analysis of a helical coil steam generator experiment using large eddy simulation
H Yuan, J Solberg, E Merzari, A Kraus, I Grindeanu
Nuclear Engineering and Design 322, 547-562, 2017
382017
Generation IV nuclear energy system initiative; air-cooled option RCCS studies and NSTF preparation.
S Lomperski, WD Pointer, CP Tzanos, TYC Wei, AR Kraus
Argonne National Lab.(ANL), Argonne, IL (United States), 2012
302012
Feasibility of full-core pin resolved CFD simulations of small modular reactor with momentum sources
J Fang, DR Shaver, A Tomboulides, M Min, P Fischer, YH Lan, ...
Nuclear Engineering and Design 378, 111143, 2021
232021
High-fidelity simulation of flow-induced vibrations in helical steam generators for small modular reactors
E Merzari, H Yuan, A Kraus, A Obabko, P Fischer, J Solberg, S Lee, J Lai, ...
Nuclear Technology 205 (1-2), 33-47, 2019
232019
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
182016
Direct numerical simulation of fluid flow in a 5x5 square rod bundle
A Kraus, E Merzari, T Norddine, O Marin, S Benhamadouche
International Journal of Heat and Fluid Flow 90, 108833, 2021
172021
Multiscale modelling of the phénix dissymmetric test benchmark
HJ Uitslag-Doolaard, F Alcaro, F Roelofs, X Wang, A Kraus, A Brunett, ...
Nuclear Engineering and Design 356, 110375, 2020
162020
Air-cooled option RCCS studies and NSTF preparation
S Lomperski, WD Pointer, CP Tzanos, TYC Wei, AR Kraus, ...
ANL-GenIV-179, Argonne National Laboratory, Argonne, IL, 2011
152011
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
142022
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark
V Narcisi, F Giannetti, A Del Nevo, F Alcaro, X Wang, A Kraus, A Brunett, ...
Nuclear Engineering and Design 353, 110272, 2019
112019
Water NSTF Design, Instrumentation, and Test Planning
DD Lisowski, CD Gerardi, R Hu, DJ Kilsdonk, NC Bremer, SW Lomperski, ...
Argonne National Lab.(ANL), Argonne, IL (United States), 2017
112017
Experimental observations of natural circulation flow in the NSTF
DD Lisowski, AR Kraus, MD Bucknor, R Hu, MT Farmer
Nuclear Engineering and Design 306, 124-132, 2016
112016
ADS design concept for disposing of the US spent nuclear fuel inventory
Y Gohar, Y Cao, AR Kraus
Annals of Nuclear Energy 160, 108385, 2021
102021
Advanced Model Developments in SAM for Thermal Stratification Analysis during Reactor Transients
R Hu, Y Zhu, A Kraus
Argonne National Lab.(ANL), Argonne, IL (United States), 2018
102018
Progress Report on Computational Analyses of Water-Based NSTF
Q Lv, A Kraus, R Hu, M Bucknor, D Lisowski, D Nunez
Argonne National Lab.(ANL), Argonne, IL (United States), 2017
92017
Large Eddy Simulation of a 5× 5 rod bundle: Impacts of a central control rod thimble tube
A Kraus, E Merzari, T Norddine, O Marin, S Benhamadouche
Nuclear Engineering and Design 381, 111337, 2021
82021
RCCS Testing with the Water-based NSTF: Year-1 Single-Phase Results
D Lisowski, Q Lv, R Hu, A Kraus, N Bremer, DJ Kilsdonk, M Farmer
Argonne National Lab.(ANL), Argonne, IL (United States), 2019
72019
Erosion of a large-scale gaseous stratified layer by a turbulent jet-Simulations with URANS and LES approaches
A Kraus, S Aithal, A Obabko, E Merzari, A Tomboulides, P Fischer
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2015
72015
Report on Year-2 of Water NSTF Matrix Testing: Two-Phase Baseline & Repeatability
D Lisowski, Q Lv, N Bremer, R Hu, A Kraus, D Kilsdonk, S Lomperski, ...
Argonne National Lab (ANL), Lemont, IL (United States), ANL-ART-206, 2020
62020
On the relevance of turbulent structures resolution for cross-flow in a helical-coil tube bundle
J Feng, M Acton, E Baglietto, AR Kraus, E Merzari
Annals of Nuclear Energy 140, 107298, 2020
62020
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