Víctor Hugo Sánchez-Espinoza

Author

Also Known As

Sanchez Espinoza, Victor Hugo, Sanchez, V., Sanchez, V.H., Sanchez, Victor, Sanchez-Espinoza V., H., Sanchez-Espinoza, V., Sanchez-Espinoza, V.H., Sanchez-Espinoza, Victor, Sanchez-Espinoza, Victor H., Sanchez-Espinoza, Victor Hugo

222

Publications

1.6K

Citations

H-Index

114

Concepts

All Affiliations

Karlsruhe Institute of Technology VTT Technical Research Centre of Finland Helmholtz-Zentrum Dresden-Rossendorf Tieto (Finland)Commissariat à l'Énergie Atomique et aux Énergies Alternatives

About

Víctor Hugo Sánchez-Espinoza is an author at Karlsruhe Institute of Technology specializing in engineering, modeling and simulation, and systems engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	19	41	959
2	Education	1	1	10
3	Management	1	1	47
4	Natural Sciences	1	1	18
5	Chemical Engineering	1	1	15

Víctor Hugo Sánchez-Espinoza

Publications

1.1K

Citations

H-Index

Page 1

	Year	Citations
Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT) Uwe Imke, Víctor Hugo Sánchez-Espinoza Science and Technology of Nuclear Installations EngineeringSingle-phase FlowFluid MechanicsVerificationSoftware Engineering	2012	78
Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project Bruno Chanaron, Carol Ahnert, Nicolas Crouzet, Annals of Nuclear Energy Advanced Multi-physics SimulationEngineeringNuclear PhysicsNuresafe ProjectNuclear Safety	2015	62
High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW Miriam Daeubler, A. Ivanov, Bart L. Sjenitzer, Annals of Nuclear Energy EngineeringPhysicsThermal HydraulicsThermal-hydraulic SimulationsMonte Carlo	2015	60
The EC MUSA Project on Management and Uncertainty of Severe Accidents: Main Pillars and Status L.E. Herranz, S. Beck, Víctor Hugo Sánchez-Espinoza, Energies EngineeringEmergency ManagementMain PillarsSafety ScienceReactor Physics	2021	47
Coupling of dynamic Monte Carlo with thermal-hydraulic feedback Bart L. Sjenitzer, J.E. Hoogenboom, Javier Jiménez Escalante, Annals of Nuclear Energy EngineeringMonte CarloMonte Carlo MethodNumerical SimulationMonte Carlo Methods	2014	45
Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore Diego Ferraro, Manuel García, Ville Valtavirta, Annals of Nuclear Energy EngineeringMechanicsNumerical SimulationMultiphysics ProblemMechanical Modeling	2019	34
Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests Diego Ferraro, Manuel García, Ville Valtavirta, Annals of Nuclear Energy	2020	34
Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark T. Skorek, A. de Crécy, A. Kovtonyuk, Nuclear Engineering and Design Thermodynamic ModellingEngineeringThermal HydraulicsUncertainty QuantificationUncertainty Estimation	2019	31
Review and proposal for heat transfer predictions at supercritical water conditions using existing correlations and experiments Wadim Jäger, Víctor Hugo Sánchez-Espinoza, Antonio Hurtado Nuclear Engineering and Design Heat Transfer PredictionsHeat Transfer ProcessEngineeringSupercritical Water ConditionsSupercritical Water	2011	30
DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters – Part I: Development, implementation and verification Armando Gómez-Torres, Víctor Hugo Sánchez-Espinoza, Kostadin Ivanov, Annals of Nuclear Energy EngineeringSoftware SystemsVerificationSafety ScienceSoftware Analysis	2012	29

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