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Marina Pérez-Ferragut

Observed names: M. Perez-Ferragut, M. Pérez-Ferragut, Marina Perez-Ferragut, Marina Pérez Ferragut, Pérez-Ferragut, Marina
ORCID: 0009-0002-1978-2834
Observed ORCID: 0009-0002-1978-2834
OpenAlex ID: A5010130686
Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM
2021 · Katarzyna Skolik, Chris Allison, et al. · Progress in Nuclear Energy · 27
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Integration of a quantitative-based selection procedure in an uncertainty analysis methodology for npp safety analysis
2011 · Marina Pérez Ferragut · Dialnet (Universidad de la Rioja) · 14
Methodology for phenomenological code assessment with integral test data
2021 · Marina Perez-Ferragut, Víctor Martinez-Quiroga, et al. · Nuclear Engineering and Design · 11
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Uncertainty Study of the In-Vessel Phase of a Severe Accident in a Pressurized Water Reactor
2022 · Siniša Šadek, Davor Grgić, et al. · Energies · 9
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Application of a BEPU-based code assessment to the ATLAS upper head SB-LOCA test
2021 · Abdulrahman S. Al-Awad, Marina Perez-Ferragut, et al. · Annals of Nuclear Energy · 8
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Development of the ASYST VER 3.x LWR/HPWR Best Estimate Integral Code
2021 · Daniel Dupleac, Roxana-Mihaela Nistor-Vlad, et al. · 7
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future
2023 · J. Freixa, T. Barrachina, et al. · Nuclear Engineering and Design · 5
Assessment of RELAP/SCDAPSIM for Turbine Trip Transient in NuScale-SMR
2018 · Katarzyna Skolik, Anuj Trivedi, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 5
QUENCH-06 Experiment Post-Test Calculations and Integrated Uncertainty Analysis With RELAP/SCDAPSIM/MOD3.4 and MOD3.5
2018 · C. Allison, B. T. Le, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 5
RELAP/SCDAPSIM/MOD4.0 modification for transient accident scenario of test blanket modules involving helium flows into heavy liquid metal
2015 · Marina Pérez-Ferragut, J. Freixa, et al. · RECERCAT (Consorci de Serveis Universitaris de Catalunya) · 4
Development of flow regime maps for lead lithium eutectic–helium flows
2020 · E. Mas de les Valls, A. Cegielski, et al. · Fusion Engineering and Design · 3
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Significance of the input parameters selection and the nodalization qualification in the final results of an IBLOCA BEPU calculation
2016 · Víctor Martínez-Quiroga, J. Freixa, et al. · RECERCAT (Consorci de Serveis Universitaris de Catalunya) · 2
CANDU 6 Accident Analysis Using RELAP/SCDAPSIM With the Integrated Uncertainty Package
2018 · Roxana-Mihaela Nistor-Vlad, Daniel Dupleac, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using core SCDAP components
2015 · J. Freixa, Marina Pérez-Ferragut, et al. · 1
Stepwise Uncertainty Analysis Methodology: First Insights
2026 · Rafael Bocanegra, Victor Martinez-Quiroga, et al. · Nuclear Technology
Application of the ANT assessment methodology for validating LOCUST 1.2 thermal-hydraulic code
2024 · Kevin Martin, Max Casamor, et al. · Nuclear Engineering and Design
Application of RELAP/SCDAPSIM/MOD4.1 to the Analysis of Advanced Reactor/Fluid Systems With Liquid Molten Salt in the Presence of Non-Condensable Gases
2018 · S. Jiang, M. Perez-Ferragut, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Aproximación multiescala a la simulación termohidráulica de reactores de fusión en la Universidad Politécnica de Cataluña
2014 · Lluís Batet Miracle, Elisabet Mas de les Valls Ortiz, et al.
Works count: 22
Citation count: 102
H-index: 6
I10-index: 3
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