Browsing by Author "Martínez Quiroga, Víctor Manuel"Més informacióMés informació

Now showing items 1-20 of 32

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

      Martínez Quiroga, Víctor Manuel; Reventós Puigjaner, Francesc Josep; Freixa Terradas, Jordi (2014-03-02)
      Article
      Open Access
      In the framework of the nodalization qualification process and quality guarantee procedures and following the guidelines of Kv-scaled analysis and UMAE methodology, further development has been performed by UPC team resulting ...

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

      Batet Miracle, Lluís; Mas de les Valls Ortiz, Elisabet; Osychenko, Oleg; Martínez Quiroga, Víctor Manuel; Pérez-Ferragut, Marina; Freixa Terradas, Jordi; Reventós Puigjaner, Francesc Josep (2014)
      Conference report
      Restricted access - publisher's policy
      El Grupo de Estudios Termohidráulicos (GET) de la UPC posee gran experiencia en estudios de seguridad nuclear mediante códigos de simulación de plantas nucleares. Desde 1987, el grupo ha colaborado con las CN de Ascó y ...

    • Assessment of SBO Fukushima likewise scenario for an IPWR design with RELAP5MOD33 and RELAPSCDAPSIMMOD3. 5 codes 

      Martínez Quiroga, Víctor Manuel; Pérez-Ferragut, Marina; Pericas Casals, Raimon; Freixa Terradas, Jordi (2022)
      Conference report
      Open Access
      In recent years Small Modular Reactors (SMR) have become very popular within the nuclear industry. These designs allow to reduce costs as well as to enhance the safety due to passive nuclear safety features. Within these ...

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

      Freixa Terradas, Jordi; Martínez Quiroga, Víctor Manuel; Reventós Puigjaner, Francesc Josep (2015)
      Conference report
      Restricted access - publisher's policy
      Given the difficulties in placing measurements in the core region, core exit temperature (CET) measurements are used as a criterion for the initiation of safety operational procedures during accidental conditions in ...

    • Development and application in multiscale and multiphysics methodologies in Spain: present and future trends 

      Gallardo Bermell, Sergio; Alvarez Velarde, Francisco; Barrachina Celda, Teresa María; Cabellos de Francisco, Oscar Luis; Castro Gonzalez, Emilio; Casamor Vidal, Max; Cuervo Gomez, Diana; Escrivá Castells, Facundo Alberto; Freixa Terradas, Jordi; García Herranz, Nuria; Martínez Quiroga, Víctor Manuel; Miro Herrero, Rafael; Queral, Cesar; Rivera Durán, Yago (2024-03-15)
      Article
      Open Access
      In the field of reactor physics analysis, the coupling of multiple physics phenomena plays a crucial role in enhancing the accuracy of predictions and understanding complex systems. Multiphysics refers to the study and ...

    • Effectiveness of the ASVAD valve in a reactor vessel bottom leak scenario 

      Freixa Terradas, Jordi; Laborda, Arnaldo; Martínez Quiroga, Víctor Manuel (2021-09-15)
      Article
      Open Access
      Decay heat removal can be seriously degraded by the presence of non-condensable gases in the cooling circuits. Nitrogen gas may be pushed into the primary system after a full discharge of the accumulators. This may produce ...

    • Full scope scaling analysis and recommendations for PWR SGTR scenarios 

      Martin Gil, Kevin; Martínez Quiroga, Víctor Manuel; Freixa Terradas, Jordi (Elsevier, 2024-03-01)
      Article
      Restricted access - publisher's policy
      Scaling studies were conducted in the field of nuclear thermal-hydraulics to analyze the scaling distortions in a Steam Generator Tube Rupture (SGTR) scenario. Test 4 of the NEA/OECD/ROSA-2 Large-Scale Test Facility (LSTF) ...

    • Kv-scaling in thermal hydraulics: background, applications and forthcoming uses 

      Martínez Quiroga, Víctor Manuel; Freixa Terradas, Jordi; Reventós Puigjaner, Francesc Josep (2023-04-01)
      Article
      Open Access
      Addressing the scaling issue refers to a rather complex process of demonstrating the applicability of activities devoted to predict the behaviour of actual nuclear power plants using the knowledge acquired in scaled-down ...

    • Linden code validation against NUPEC / PSBT experimental data for void fraction and temperature benchmarks 

      Pérez-Ferragut, Marina; Freixa Terradas, Jordi; Martínez Quiroga, Víctor Manuel; Casamor Vidal, Max (2022)
      Conference report
      Restricted access - publisher's policy
      The subchannel analysis code LINDEN is being developed by China Nuclear Power Technology Research Institute Co. Ltd (CNPRI). The LINDEN code is used in thermal-hydraulics design and safety analysis of pressurized water ...

    • Methodology for phenomenological code assessment with integral test data 

      Pérez-Ferragut, Marina; Martínez Quiroga, Víctor Manuel; Casamor Vidal, Max; Freixa Terradas, Jordi (2022-02-28)
      Article
      Open Access
      The use of codes in the licensing process requires a rigorous validation process that can be accomplished by means of qualitative and quantitative assessment. In thermal hydraulics, this validation has to be performed at ...

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

      Batet Miracle, Lluís; Álvarez Fernández, Josep Maria; Mas de les Valls Ortiz, Elisabet; Pérez, Marina; Martínez Quiroga, Víctor Manuel; Reventós Puigjaner, Francesc Josep; Sedano Miguel, Luis Ángel (2013)
      Conference report
      Restricted access - publisher's policy
      En el marco del programa español de Tecnología de Fusión TECNO_FUS se ha avanzado en la definición de sistemas para DEMO, entre ellos las unidades reproductoras de tritio y el ciclo de potencia. Para las primeras, se ha ...

    • Modelling guidelines for core exit temperature simulations with system codes 

      Freixa Terradas, Jordi; Martínez Quiroga, Víctor Manuel; Zerkak, O; Reventós Puigjaner, Francesc Josep (2015-05-01)
      Article
      Open Access

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

      Freixa Terradas, Jordi; Martínez Quiroga, Víctor Manuel; Reventós Puigjaner, Francesc Josep (2020-04-01)
      Article
      Open Access
      After the Fukushima accident, “stress-test” activities carried out worldwide pointed out the need to study additional accident management measures to deal with prolonged Station Black Out (SBO) scenarios. Without any ...

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

      Batet Miracle, Lluís; Álvarez Fernández, Josep Maria; Mas de les Valls Ortiz, Elisabet; Martínez Quiroga, Víctor Manuel; Pérez-Ferragut, Marina; Reventós Puigjaner, Francesc Josep; Sedano Miguel, Luis Ángel (2014-04-01)
      Article
      Restricted access - publisher's policy
      A supercritical recompression CO2 power cycle has been simulated using the system code RELAP5-3D. This code is being developed by INL and has traditionally been used in the simulation of operational and accidental transients ...

    • Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor 

      Peakman, Aiden; Gregg, Robert; Bennett, Tom; Casamor Vidal, Max; Martínez Quiroga, Víctor Manuel; Freixa Terradas, Jordi; Pericas Casals, Raimon; Rossiter, Glyn (2022-08-01)
      Article
      Open Access
      The increasing deployment of renewable energy sources and greater electrification of demand is requiring more frequent use of load following in pressurised water reactors (PWRs) . A limiting aspect with respect to load ...

    • OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment 

      Martínez Quiroga, Víctor Manuel; Szogradi, Marton; Schollenberger, Simon; Sánchez Perea, Miguel; Sandberg, Nils; Zhongyun, J.; Freydier, P.; Freixa Terradas, Jordi (2022-04-01)
      Article
      Open Access
      Code assessment and validation is one of the most relevant research lines in thermal hydraulics and best estimate codes. During the last decades, the Nuclear Energy Agency (NEA) and the Organization for Economic Co-operation ...

    • On the scaling of uncertainties in thermal hydraulic system codes 

      Casamor Vidal, Max; Martínez Quiroga, Víctor Manuel; Reventós Puigjaner, Francesc Josep; Mendizabal Sanz, Rafael; Freixa Terradas, Jordi (2020-02-01)
      Article
      Open Access
      The present work addresses the scaling e ect on safety margins and uncertainties for best estimate plus uncertainty (BEPU) methodologies. The results of an experiment from the OECD/NEA ROSA-2 project at the LSTF facility ...

    • On the validation of BEPU methodologies through the simulation of integral experiments: Application to the PKL test facility 

      Freixa Terradas, Jordi; Martínez Quiroga, Víctor Manuel; Casamor Vidal, Max; Reventós Puigjaner, Francesc Josep; Mendizabal Sanz, Rafael; Sánchez Perea, Miguel (2021-08-01)
      Article
      Open Access
      Validation procedure for BEPU deterministic safety analysis.•BEPU analysis of a semi-blind simulation of an IBLOCA scenario at the PKL facility.•Definition of alternative Figures of Merit for BEPU analysis allows for a ...

    • Perfecting the use of hybrid models in scaling analysis 

      Reventós Puigjaner, Francesc Josep; Martínez Quiroga, Víctor Manuel; Freixa Terradas, Jordi (2019-12-01)
      Article
      Open Access
      Different methodologies devoted to qualify Nuclear Power Plant (NPP) system-code nodalizations rely on Kv-scaled calculations as an essential tool for their purpose. In the framework of Power-To-Volume strategy, a Kv-scaled ...

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

      Freixa Terradas, Jordi; Martínez Quiroga, Víctor Manuel; Reventós Puigjaner, Francesc Josep (2016)
      Conference report
      Restricted access - publisher's policy
      After the Fukushima accident, “st ress- test” activities carried out worldwide pointed out the need to study additional accident management measures to deal with prolonged Station Black Out (SBO) scenarios. Without any ...