Perfecting the use of hybrid models in scaling analysis
Reventos, F., Martinez-Quiroga, V., Freixa, J.
Published in Nuclear engineering and design (01.12.2019)
Published in Nuclear engineering and design (01.12.2019)
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PVST, a tool to assess the Power to Volume scaling distortions associated to code simulations
Martinez-Quiroga, V., Freixa, J., Reventos, F.
Published in Nuclear engineering and design (01.06.2018)
Published in Nuclear engineering and design (01.06.2018)
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The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios
Martinez-Quiroga, V., Reventos, F.
Published in Science and Technology of Nuclear Installations (01.01.2014)
Published in Science and Technology of Nuclear Installations (01.01.2014)
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Applying UPC Scaling-Up Methodology to the LSTF-PKL Counterpart Test
Martinez-Quiroga, V., Freixa, J., Reventos, Francesc
Published in Science and Technology of Nuclear Installations (01.01.2014)
Published in Science and Technology of Nuclear Installations (01.01.2014)
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Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme
Perez, M., Reventos, F., Batet, L., Guba, A., Tóth, I., Mieusset, T., Bazin, P., de Crécy, A., Borisov, S., Skorek, T., Glaeser, H., Joucla, J., Probst, P., Ui, A., Chung, B.D., Oh, D.Y., Pernica, R., Kyncl, M., Macek, J., Manera, A., Freixa, J., Petruzzi, A., D’Auria, F., Del Nevo, A.
Published in Nuclear engineering and design (01.10.2011)
Published in Nuclear engineering and design (01.10.2011)
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SBLOCA with boron dilution in pressurized water reactors. Impact on operation and safety
Freixa, J., Reventós, F., Pretel, C., Batet, L., Sol, I.
Published in Nuclear engineering and design (01.04.2009)
Published in Nuclear engineering and design (01.04.2009)
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Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM
Allison, C. M., Hohorst, J. K., Allison, B. S., Konjarek, D., Bajs, T., Pericas, R., Reventos, Francesc, Lopez, R.
Published in Science and technology of nuclear installations (01.01.2012)
Published in Science and technology of nuclear installations (01.01.2012)
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Uncertainty Analysis of Light Water Reactor Fuel Lattices
Arenas, C., Bratton, R., Reventos, Francesc, Ivanov, Kostadin
Published in Science and Technology of Nuclear Installations (01.01.2013)
Published in Science and Technology of Nuclear Installations (01.01.2013)
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Analysis of the feed & bleed procedure for the ascó NPP first approach study for operation support
REVENTOS, F, BATET, L, PRETEL, C, RIOS, M, SOL, I
Published in Nuclear engineering and design (01.10.2007)
Published in Nuclear engineering and design (01.10.2007)
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Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme
de Crécy, A., Bazin, P., Glaeser, H., Skorek, T., Joucla, J., Probst, P., Fujioka, K., Chung, B.D., Oh, D.Y., Kyncl, M., Pernica, R., Macek, J., Meca, R., Macian, R., D’Auria, F., Petruzzi, A., Batet, L., Perez, M., Reventos, F.
Published in Nuclear engineering and design (01.12.2008)
Published in Nuclear engineering and design (01.12.2008)
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Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison
Casamor, M., Avramova, M., Reventós, F., Freixa, J.
Published in Annals of nuclear energy (01.12.2022)
Published in Annals of nuclear energy (01.12.2022)
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On the validation of BEPU methodologies through the simulation of integral experiments: Application to the PKL test facility
Freixa, J., Martínez-Quiroga, V., Casamor, M., Reventós, F., Mendizábal, R., Sánchez-Perea, M.
Published in Nuclear engineering and design (01.08.2021)
Published in Nuclear engineering and design (01.08.2021)
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Analysis of low load transients for the Vandellòs-II NPP Application to operation and control support
LLOPIS, C, REVENTOS, F, BATET, L, PRETEL, C, SOL, I
Published in Nuclear engineering and design (01.10.2007)
Published in Nuclear engineering and design (01.10.2007)
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Modelling guidelines for core exit temperature simulations with system codes
Freixa, J., Martínez-Quiroga, V., Zerkak, O., Reventós, F.
Published in Nuclear engineering and design (01.05.2015)
Published in Nuclear engineering and design (01.05.2015)
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Qualification of a full plant nodalization for the prediction of the core exit temperature through a scaling methodology
Freixa, J., Martínez-Quiroga, V., Reventós, F.
Published in Nuclear engineering and design (01.11.2016)
Published in Nuclear engineering and design (01.11.2016)
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Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future
Freixa, J., Barrachina, T., Berna, C., Bocanegra, R., Carlos, S., Castro, E., Cuervo, D., Durán-Vinuesa, L.F., Escrivá, A., Feria, F., Cosials, K. Fernández, García-Herranz, N., Herranz, L.E., Jiménez, G., Martínez-Quiroga, V., Martorell, S., Mendizabal, R., Miró, R., Muñoz-Cobo, J.L., Pérez-Ferragut, M., Pericas, R., Queral, C., Reventós, F., Riverola, J., Sánchez, A., Villanueva, J.F.
Published in Nuclear engineering and design (01.02.2024)
Published in Nuclear engineering and design (01.02.2024)
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