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Augusto Hernández-Solís

Observed names: A. HERNANDEZ-SOLIS, A. Hernandez-Solis, A. Hernández-Solís, Augusto Hernandez Solis, Augusto Hernandez-Solis, Augusto Hernández Solís, Augusto Hernández-Solis, Augusto Solis
Observed institutions: Uppsala University, Belgian Nuclear Research Centre, AlbaNova, Chalmers University of Technology, KTH Royal Institute of Technology, Universidad Nacional Autónoma de México
ORCID: 0000-0002-7439-1994
Observed ORCID: 0000-0002-7439-1994
OpenAlex ID: A5028243643
Diagnosis of Submersible Centrifugal Pumps: A Motor Current and Power Signature Approaches
2010 · Augusto Hernandez-Solis, Fredrik Carlsson · EPE Journal · 20
Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat
2022 · Peter Jansson, Martin Bengtsson, et al. · Nuclear Science and Engineering · 18
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The nuclear fuel cycle code ANICCA: Verification and a case study for the phase out of Belgian nuclear power with minor actinide transmutation
2020 · I. Merino Rodríguez, A. Hernández-Solís, et al. · Nuclear Engineering and Technology · 14
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Nuclear data uncertainty analysis for the Po-210 production in MYRRHA
2018 · Luca Fiorito, Alexey Stankovskiy, et al. · EPJ Nuclear Sciences & Technologies · 13
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Uncertainty and sensitivity analyses applied to the DRAGONv4.05 code lattice calculations and based on JENDL-4 data
2013 · Augusto Hernández-Solís, Christophe Demazière, et al. · Annals of Nuclear Energy · 10
Uncertainty and sensitivity analysis applied to LWR neutronic and thermal-hydraulic calculations
2012 · Augusto Hernández-Solís · Chalmers Research (Chalmers University of Technology) · 10
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On the use of criticality and depletion benchmarks for verification of nuclear data
2021 · L. Fiorito, P. Romojaro, et al. · Annals of Nuclear Energy · 9
Developments in Core-Barrel Motion Monitoring and Applications to the Ringhals PWR Units
2016 · Imre Pázsit, Cristina Montalvo, et al. · Nuclear Science and Engineering · 9
Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies
2019 · A.V. Skarbeli, I. Merino Rodríguez, et al. · Annals of Nuclear Energy · 8
Development of three-dimensional capabilities for modelling stationary fluctuations in nuclear reactor cores
2014 · Christophe Demazière, Victor Dykin, et al. · Annals of Nuclear Energy · 8
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Uncertainty and sensitivity analyses as a validation tool for BWR bundle thermal–hydraulic predictions
2011 · Augusto Hernandez-Solis, Christian Ekberg, et al. · Nuclear Engineering and Design · 7
Impact of fresh fuel loading management in fuel cycle simulators: A functionality isolation test
2022 · N. Thiollière, X. Doligez, et al. · Nuclear Engineering and Design · 6
Global physical and numerical stability of a nuclear reactor core
2005 · Jaime Morales-Sandoval, Augusto Hernández-Solís · Annals of Nuclear Energy · 4
Dataset of observables for UOX and MOX spent fuel extracted from Serpent2 fuel depletion calculations for PWRs
2023 · Victor J. Casas-Molina, Augusto Hernandez-Solis, et al. · Data in Brief · 3
Boundary Condition Modeling Effect on the Spent Fuel Characterization and Final Decay Heat Prediction From a Pwr Assembly
2021 · Augusto Hernandez-Solis, Klemen Ambrožič, et al. · EPJ Web of Conferences · 3
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Statistical Uncertainty Analyses of Void Fraction Predictions Using Two Different Sampling Strategies: Latin Hypercube and Simple Random Sampling
2010 · Augusto Hernandez-Solis, Christian Ekberg, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 3
A novel irradiation module for ANICCA fuel cycle code based on multi-task learning
2024 · Victor J. Casas-Molina, Nerea Aguilera-Gómez, et al. · Nuclear Engineering and Technology · 2
Nuclear Data Uncertainty Analysis to Meet the Target Accuracy Requirements on the MYRRHAkeff
2023 · Pablo Romojaro, Ciro Alfonso, et al. · EPJ Web of Conferences · 2
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Deep Learning Models as an Approach to Nuclear Fuel Irradiation Processes in Pressurized Water Reactors
2022 · Víctor J. Casas Molina, Augusto Hernández Solís, et al. · International Conference of the Chilean Computer Science Society (SCCC) · 2
Nuclear Data Uncertainty Quantification for the Nuclide Inventory of a Calvert Cliffs Spent Fuel Sample
2022 · F. Grimaldi, L. Fiorito, et al. · International Conference on Physics of Reactors (PHYSOR) · 2
Sensitivity Analyses of a Homogeneous Model and a RZ Model of the MYRRHA Reactor in its Critical Configuration
2022 · Ciro Alfonso, Pablo Romojaro, et al. · International Conference on Physics of Reactors (PHYSOR) · 2
Sensitivity and Uncertainty Analysis of PWR Spent Fuel Observables to Operational and Model Parameters
2022 · P. Romojaro, K. Ambrožič, et al. · International Conference on Physics of Reactors (PHYSOR) · 1
VERIFICATION OF THE OpenMC HOMOGENIZED MYRRHA-1.6 CORE MODEL
2021 · Augusto Hernandez-Solis, Yohannes Molla, et al. · EPJ Web of Conferences · 1
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A Novel Computational Platform for the Propagation of Nuclear Data Uncertainties Through the Fuel Cycle Code Anicca
2021 · Augusto Hernandez Solis, Ivan Merino Rodriguez, et al. · EPJ Web of Conferences · 1
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Depletion uncertainty analysis to the MYRRHA fuel assembly model
2020 · Augusto Hernandez Solis, Alexey Stankovskiy, et al. · EPJ Web of Conferences · 1
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Works count: 46
Citation count: 165
H-index: 8
I10-index: 6
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