Victor Hugo Sanchez Espinoza

Head of Group

Karlsruhe Institute of Technology (KIT)

Germany

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Victor Hugo Sanchez Espinoza is the Head of Group at the Karlsruhe Institute of Technology (KIT) in Germany. His research focuses on reactor modeling and safety analyses, particularly in the context of small modular reactors and severe-accident scenarios. Recent articles authored by Dr. Sanchez Espinoza address topics such as overcooling transient analysis, uncertainty quantification in reactor modeling, and the validation of coupled code systems for nuclear fuel performance simulations.

Articles (10)

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2025

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2025

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2025

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2025

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2024

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2024

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2024

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2024

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2024

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2024

Collaborators (3)

Alejandro Soba

Barcelona Supercomputing Center

SPAIN

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Juan Carlos Almachi Nacimba

GERMANY

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david legrady

associate professor

Budapest University of Technology and Economics

HUNGARY

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Victor Hugo Sanchez Espinoza

Research Interests

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Articles (10)

HZP and HFP rod ejection analysis in a SMART-like reactor model using the GUARDYAN-SUBCHANFLOW coupled code system

An overcooling transient analysis in a CAREM-like SMR core using Serpent/Subchanflow

Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package

Main goals and research outcomes of the EU Projects ELSMOR, McSAFER, and EASI-SMR: regulatory, experimental and analytical safety-related investigations

Validation of the dynamic simulation capabilities of Serpent2/Subchanflow using experimental data from the research reactor SPERT IV D-12/25

Assessing the impact of DIONISIO-SubChanFlow code coupling in nuclear fuel performance simulations

Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies

Corrigendum to “Comparison of MSLB transient results using the 3D coupled code TRACEv5p05/PARCS and the system thermal hydraulic code RELAP5” [Ann. Nucl. Energy 203 (2024) 110518]

Comparison of MSLB transient results using the 3D coupled code TRACEv5p05/PARCS and the system thermal hydraulic code RELAP5

Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors

Collaborators (3)

Alejandro Soba

Juan Carlos Almachi Nacimba

david legrady

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