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Victor Martinez-Quiroga
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Modelling guidelines for core exit temperature simulations with system codes
J Freixa, V Martínez-Quiroga, O Zerkak, F Reventós
Nuclear engineering and design 286, 116-129, 2015
292015
Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5–3D
L Batet, JM Alvarez-Fernandez, EM de les Valls, V Martinez-Quiroga, ...
Fusion Engineering and Design 89 (4), 354-359, 2014
252014
The use of system codes in scaling studies: relevant techniques for qualifying NPP nodalizations for particular scenarios
V Martinez-Quiroga, F Reventos
Science and Technology of Nuclear Installations 2014 (2), 1-13, 2014
242014
Applying UPC scaling-up methodology to the LSTF-PKL counterpart test
V Martinez-Quiroga, F Reventos, J Freixa
Science and Technology of Nuclear Installations 2014, 2014
232014
Qualification of a full plant nodalization for the prediction of the core exit temperature through a scaling methodology
J Freixa, V Martinez-Quiroga, F Reventós
Nuclear Engineering and Design 308, 115-132, 2016
162016
Code Validation and Scaling of the ROSA/LSTF Test 3-1 experiment
V Martınez, F Reventós, C Pretel, I Sol
Proceedings of the International Topical Meeting on Safety of Nuclear …, 2008
112008
PVST, a tool to assess the Power to Volume scaling distortions associated to code simulations
V Martinez-Quiroga, J Freixa, F Reventos
Nuclear Engineering and Design 332, 173-185, 2018
102018
NIRK3D and 3DKIN: General Description and current status of the new 3D kinetics capabilities of RELAP5/SCDAPSIM/MOD4. 0
V Martínez-Quiroga, CM Allison, RJ Wagner, F Aydogan, S Akbas
11th International Topical Meeting on Nuclear Reactor Hydraulics (NUTHOS-11 …, 2016
102016
The development of RELAP/SCDAPSIM/MOD4. 0 for advanced fluid systems design analysis
CM Allison, RJ Wagner, JK Hohorst, M Perez-Ferragut, ...
NUTHOS-11, 2016
92016
On the validation of BEPU methodologies through the simulation of integral experiments: Application to the PKL test facility
J Freixa, V Martínez-Quiroga, M Casamor, F Reventós, R Mendizábal, ...
Nuclear Engineering and Design 379, 111238, 2021
82021
Validation of a BEPU methodology through a blind benchmark activity at the PKL test facility
J Freixa, V Martínez-Quiroga, M Casamor, F Reventós, R Mendizabal
NURETH-18, 2019
82019
Modelling guidelines for safety analysis of Station Black Out sequences based on experiments at the PKL test facility
J Freixa, V Martinez-Quiroga, F Reventós
Annals of Nuclear Energy 138, 107179, 2020
72020
Modelling guidelines for CCFL representation during IBLOCA scenarios of PWR reactors
J Freixa, V Martínez-Quiroga, F Reventós
NURETH-17, 2017
72017
Scaling-up methodology: a systematical procedure for qualifying NPP nodalizations. Application to the OECD/NEA ROSA-2 and PKL-2 Counterpart test
V Martínez Quiroga
Universitat Politècnica de Catalunya, 2014
72014
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment
V Martinez-Quiroga, M Szogradi, S Schollenberger, M Sanchez-Perea, ...
Nuclear Engineering and Design 389, 111632, 2022
62022
On the scaling of uncertainties in thermal hydraulic system codes
M Casamor, V Martinez-Quiroga, F Reventós, R Mendizábal, J Freixa
Annals of Nuclear Energy 136, 107026, 2020
62020
Perfecting the use of hybrid models in scaling analysis
F Reventos, V Martinez-Quiroga, J Freixa
Nuclear Engineering and Design 354, 110187, 2019
62019
Methodology for phenomenological code assessment with integral test data
M Perez-Ferragut, V Martinez-Quiroga, M Casamor, J Freixa
Nuclear Engineering and Design 387, 111608, 2022
52022
Core Exit temperature response during an SBLOCA event in the ASCO NPP
J Freixa, V Martinez-Quiroga, F Reventos
Tech. Rep. Spanish Regulatory Council Internal Report, 2014
52014
Post-Test Calculation of the ROSA/LSTF Test 3-1 Using RELAP5
V Martinez-Quiroga, F Reventos, C Pretel
Mod3. 3. Tech. Rep. NUREG/IA–0410, USNRC. URL http://pbadupws. nrc. gov/docs …, 2012
52012
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