FUTUR. Website for the scientific production of UPC researchers.

Martinez Quiroga, Victor Manuel

Total activity: 20

Areas of expertise: Nuclear Engineering, Physics, Scaling, Thermal-hydraulics
h index: 3

Doctoral courses: Doctor
Professional category: Other

Research group: ANT - Advanced Nuclear Technologies Research Group
Department: Department of Physics
School: Barcelona School of Industrial Engineering (ETSEIB)

E-mail: victor.martinez.quirogaupc.edu
Contact details: UPC directory

Orcid: 0000-0003-0096-8348
Scopus Author ID: 56069653200

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Scientific and technological production

1 to 20 of 20 results

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Modelling guidelines for safety analysis of Station Black Out sequences based on experiments at the PKL test facility
Freixa, J.; Martinez, V.; Reventos, F.
Annals of nuclear energy
Vol. 138, num. April, p. 107179:1-107179:11
DOI: 10.1016/j.anucene.2019.107179
Date of publication: 2020-04-01
Journal article

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On the scaling of uncertainties in thermal hydraulic system codes
Casamor, M.; Martinez, V.; Reventos, F.; Mendizabal, R.; Freixa, J.
Annals of nuclear energy
Vol. 136
DOI: 10.1016/j.anucene.2019.107026
Date of publication: 2020-02-01
Journal article

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Perfecting the use of hybrid models in scaling analysis
Reventos, F.; Freixa, J.; Martinez, V.
Nuclear engineering and design
Vol. 354, num. 110187, p. 110187:1-110187:7
DOI: 10.1016/j.nucengdes.2019.110187
Date of publication: 2019-12-01
Journal article

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Validation of a BEPU methodology through a blind benchmark activity at the PKL test facility
Freixa, J.; Martinez, V.; Casamor, M.; Reventos, F.; Mendizabal, R.
International Topical Meeting on Nuclear Reactor Thermal Hydraulics
p. 366-379
Presentation's date: 2019-08-26
Presentation of work at congresses

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PVST, a tool to assess the power to volume scaling distortions associated to code simulations
Martinez, V.; Freixa, J.; Reventos, F.
Nuclear engineering and design
Vol. 332, p. 173-185
DOI: 10.1016/j.nucengdes.2018.03.035
Date of publication: 2018-06-01
Journal article

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Qualification of a full plant nodalization for the prediction of the core exit temperature through a scaling methodology
Freixa, J.; Martinez, V.; Reventos, F.
Nuclear engineering and design
Vol. 308, p. 115-132
DOI: 10.1016/j.nucengdes.2016.08.014
Date of publication: 2016-11-01
Journal article

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Significance of the input parameters selection and the nodalization qualification in the final results of an IBLOCA BEPU calculation
Martinez, V.; Freixa, J.; Perez, M.; Reventos, F.
International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety
p. 1-12
Presentation's date: 2016-10
Presentation of work at congresses

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Pre-and post-test simulations of station black out experiments at the PKL test facility
Freixa, J.; Martinez, V.; Reventos, F.
International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety
p. 1/14-14/14
Presentation's date: 2016-10
Presentation of work at congresses

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Simulación de experimentos realizados en la instalación PKL sobre pérdida total de suministro eléctrico
Freixa, J.; Martinez, V.; Pretel, C.; Batet, L.; Reventos, F.
Reunión Anual de la Sociedad Nuclear Española
p. 1-8
Presentation's date: 2016-09
Presentation of work at congresses

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Core Exit temperature response during an SBLOCA event in the ASCO NPP
Freixa, J.; Martinez, V.; Reventos, F.
International Topical Meeting on Nuclear Reactor Thermal Hydraulics
p. 217-230
Presentation's date: 2015-09
Presentation of work at congresses

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Modelling guidelines for core exit temperature simulations with system codes
Freixa, J.; Martinez, V.; Zerkak, O.; Reventos, F.
Nuclear engineering and design
Vol. 286, p. 116-129
DOI: 10.1016/j.nucengdes.2015.02.003
Date of publication: 2015-05-01
Journal article

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Scaling-up methodology, a systematical procedure for qualifying NPP nodalizations. Application to the OECD/NEA ROSA-2 and PKL-2 Counterpart test
Martinez, V.
Department of Physics and Nuclear Engineering, Universitat Politècnica de Catalunya
Theses

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Estudio dinámico de un ciclo de potencia avanzado de CO2 supercrítico para reactores de fusión
Batet, L.; Mas de les Valls, E.; Reventos, F.; Linares, J.I.; Sanmartí, M.; Cantizano, A.; Sedano, L.; Díaz-González, F.; Martinez, V.; Perez, M.
Reunión Anual de la Sociedad Nuclear Española
Presentation's date: 2014-10-02
Presentation of work at congresses

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Aproximación multiescala a la simulación termohidráulica de reactores de fusión en la Universidad Politécnica de Cataluña
Batet, L.; Mas de les Valls, E.; Osychenko, O.; Martinez, V.; Perez, M.; Freixa, J.; Reventos, F.
Reunión Anual de la Sociedad Nuclear Española
p. 1-7
Presentation's date: 2014-10-02
Presentation of work at congresses

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Modelling the thermal-hydraulic dynamic behaviour of a generic fusion plant with dual coolant blanket and a supercritical CO2 power cycle using RELAP5-3D
Batet, L.; Martinez, V.; Mas de les Valls, E.; Perez, M.; Reventos, F.; Sanmartí, M.; Sedano, L.
Symposium on Fusion Technology
p. 751
Presentation's date: 2014-10-02
Presentation of work at congresses

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Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5-3D
Batet, L.; Álvarez-Fernández, J.M.; Mas de les Valls, E.; Martinez, V.; Perez, M.; Reventos, F.; Sedano, L.
Fusion engineering and design
Vol. 89, num. 4, p. 354-359
DOI: 10.1016/j.fusengdes.2014.03.018
Date of publication: 2014-04-01
Journal article

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Applying UPC scaling-up methodology to the LSTF-PKL counterpart test
Martinez, V.; Reventos, F.; Freixa, J.
Science and technology of nuclear installations
Vol. 2014, p. 1-18
DOI: 10.1155/2014/292916
Date of publication: 2014-03-02
Journal article

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The use of system codes in scaling studies: relevant techniques for qualifying NPP nodalizations for particular scenarios
Martinez, V.; Reventos, F.
Science and technology of nuclear installations
Vol. 2014, p. 1-13
DOI: 10.1155/2014/138745
Date of publication: 2014-02-10
Journal article

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Modelado de un ciclo de potencia de CO2 supercrítico para reactores de fusión utilizando RELAP5-3D
Batet, L.; Álvarez, J.; Mas de les Valls, E.; Perez, M.; Martinez, V.; Reventos, F.; Sedano, L.
Reunión Anual de la Sociedad Nuclear Española
p. 1-13
Presentation's date: 2013-09-24
Presentation of work at congresses

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Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5–3D
Batet, L.; Álvarez-Fernández, J.M.; Mas de les Valls, E.; Martinez, V.; Perez, M.; Sedano, L.
International Symposium on Fusion Nuclear Technology
p. 458
Presentation's date: 2013-09-19
Presentation of work at congresses

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FUTUR. Website for the scientific production of UPC researchers

Martinez Quiroga, Victor Manuel

Scientific and technological production

Modelling guidelines for safety analysis of Station Black Out sequences based on experiments at the PKL test facility

On the scaling of uncertainties in thermal hydraulic system codes

Perfecting the use of hybrid models in scaling analysis

Validation of a BEPU methodology through a blind benchmark activity at the PKL test facility

PVST, a tool to assess the power to volume scaling distortions associated to code simulations

Qualification of a full plant nodalization for the prediction of the core exit temperature through a scaling methodology

Significance of the input parameters selection and the nodalization qualification in the final results of an IBLOCA BEPU calculation

Pre-and post-test simulations of station black out experiments at the PKL test facility

Simulación de experimentos realizados en la instalación PKL sobre pérdida total de suministro eléctrico

Core Exit temperature response during an SBLOCA event in the ASCO NPP

Modelling guidelines for core exit temperature simulations with system codes

Scaling-up methodology, a systematical procedure for qualifying NPP nodalizations. Application to the OECD/NEA ROSA-2 and PKL-2 Counterpart test

Estudio dinámico de un ciclo de potencia avanzado de CO2 supercrítico para reactores de fusión

Aproximación multiescala a la simulación termohidráulica de reactores de fusión en la Universidad Politécnica de Cataluña

Modelling the thermal-hydraulic dynamic behaviour of a generic fusion plant with dual coolant blanket and a supercritical CO2 power cycle using RELAP5-3D

Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5-3D

Applying UPC scaling-up methodology to the LSTF-PKL counterpart test

The use of system codes in scaling studies: relevant techniques for qualifying NPP nodalizations for particular scenarios

Modelado de un ciclo de potencia de CO2 supercrítico para reactores de fusión utilizando RELAP5-3D

Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5–3D

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