Browsing by Author "Freixa Terradas, Jordi"Més informacióMés informació

Now showing items 1-20 of 48

    • A systematic approach for the adequacy analysis of a set of experimental databases: application in the framework of the ATRIUM activity 

      Baccou, Jean; Glantz, Tony; Ghione, Alberto; Sargentini, Lucia; Fillion, Philippe; Damblin, Guillaume; Sueur, Roman; Iooss, Bertrand; Fang, Jun; Freixa Terradas, Jordi (2024-05-01)
      Article
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      In the Best-Estimate Plus Uncertainty (BEPU) framework, the use of best-estimate code requires to go through a Verification, Validation and Uncertainty Quantification process (VVUQ). The relevance of the experimental data ...

    • Activities in Spain on the integration of probabilistic and deterministic safety analysis methods. Discussion on their applicability to DEC-A scenarios 

      Mendizabal Sanz, Rafael; Sánchez, Miguel Irlesa I.; Queral Salazar, José César; Hortal Iglesias, Francisco Javier; Martorell Alsina, Sebastián Salvador; Pelayo Loscertales, Fernando; Freixa Terradas, Jordi (2024-04-01)
      Article
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      This paper presents a summary of theoretical and applied achievements in the field of integrated methods of nuclear safety analysis produced by Spain’s nuclear safety community. These integrated methods combine deterministic ...

    • Application of a BEPU-based code assessment to the ATLAS upper head SB-LOCA test 

      Al Awad, Abdulrahman; Freixa Terradas, Jordi; Pérez-Ferragut, Marina (2021-12-15)
      Article
      Open Access
      The prevailing state of knowledge of two-phase flow in complex systems, as in the nuclear field, usually leads a certain degree of ad hoc calibration of computational models and the consequent inevitable subjectivity in ...

    • Application of the ANT assessment methodology for validating LOCUST 1.2 thermal-hydraulic code 

      Martin Gil, Kevin; Casamor Vidal, Max; Martínez Quiroga, Víctor Manuel; Pérez-Ferragut, Marina; Zhongyun, J.; Freixa Terradas, Jordi (Elsevier, 2024-10)
      Article
      Open Access
      Nuclear power plants play a critical role in providing clean and sustainable energy. Ensuring the safety of these plants is of utmost importance to the nuclear industry. In this regards, thermal-hydraulic computer codes ...

    • 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
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      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 ...

    • Assessment of the choked flow model of RELAP5 for application of inverse quantification methods 

      Osés Ezquerra, Pablo; Freixa Terradas, Jordi; Mendizabal Sanz, Rafael; Sánchez Perea, Miguel (2024-10-24)
      Article
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      In the framework of deterministic safety analysis, best estimate plus uncertainty methodologies can provide a more informative detailed analysis of transients than conservative approaches. However, one important step in ...

    • 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 ...

    • Core-wide multi-physics simulation of fuel behaviour during large-break LOCA using NEXUS 

      Peakman, Aiden; Gregg, Robert; Martínez Quiroga, Victor; Freixa Terradas, Jordi (2025-06-01)
      Article
      Open Access
      Large-break loss-of-coolant accidents (LB-LOCAs) are among the most critical scenarios in nuclear power plant safety analysis due to their potential to significantly challenge the integrity of barriers confining radioactive ...

    • 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 ...

    • Development of flow regime maps for lead lithium eutectic–helium flows 

      Mas de les Valls Ortiz, Elisabet; Cegielski, Andrzej; Jaros, Mark; Pérez-Ferragut, Marina; Batet Miracle, Lluís; Freixa Terradas, Jordi (2020-09-01)
      Article
      Open Access
      nstitute for Plasma Research (IPR), Gandhinagar (India) is currently involved in the design and development of its Lead-Lithium Ceramic Breeder (LLCB) module for testing in the International Thermo-nuclear Experimental ...

    • Dinámicas de las concentraciones de empleo en sectores intensivos en conocimiento y su relación con las políticas locales de promoción económica: un estudio para la Provincia de Barcelona 

      Chica Mejía, Juan Eduardo; Marmolejo Duarte, Carlos Ramiro; Freixa Terradas, Jordi; Burns, Malcolm (Centre de Política de Sòl i Valoracions / Universidad Autónoma de Baja California, 2010-10)
      Conference report
      Open Access
      Las economías de aglomeración están transformando el mapa de distribución del empleo en las regiones metropolitanas y están condicionando los cambios en sus estructuras urbanas. Uno de sus más claros efectos es el impacto ...

    • Doppler effect evaluation of the TRU-based Moroccan TRIGA Mark II reactor: applying novel methodologies 

      Mira, Mohamed; el Hajjaji, O.; Freixa Terradas, Jordi; el Bardouni, Tarek; Boukhal, Hamid; Boulaich, Y.; el Ghalbzouri, Tarik (2025-07-01)
      Article
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      The Doppler effect, commonly referred to as fuel temperature coefficient (aT), is a critical parameter that quantifies the reactivity feedback resulting from changes in fuel temperature. Understanding and accurately ...

    • 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
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      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 ...

    • Load follow with gen-iv very high temperature gas cooled reactor for the spanish future power mix 

      Freixa Terradas, Jordi; Radhakrishnan, Pravin (2022)
      Conference report
      Restricted access - publisher's policy
      The future power mix in Spain and most of the European countries is expected to be dominated by renewable sources. The Spanish government has set a policy to eliminate fossil fuels and nuclear power in the following decades ...

    • 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 ...