Browsing by Author "Freixa Terradas, Jordi"
Now showing items 1-19 of 19
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Applying UPC scaling-up methodology to the LSTF-PKL counterpart test
(2014-03-02)
Article
Open AccessIn 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
(2014)
Conference report
Restricted access - publisher's policyEl 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 ... -
Core Exit temperature response during an SBLOCA event in the ASCO NPP
(2015)
Conference report
Restricted access - publisher's policyGiven 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 ... -
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
(Centre de Política de Sòl i Valoracions / Universidad Autónoma de Baja California, 2010-10)
Conference report
Open AccessLas 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 ... -
Modelling guidelines for core exit temperature simulations with system codes
(2015-05-01)
Article
Open Access -
On the scaling of uncertainties in thermal hydraulic system codes
(2020-02-01)
Article
Restricted access - publisher's policyThe 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 ... -
Perfecting the use of hybrid models in scaling analysis
(2019-12-01)
Article
Open AccessDifferent 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
(2016)
Conference report
Restricted access - publisher's policyAfter 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 ... -
PVST, a tool to assess the power to volume scaling distortions associated to code simulations
(2018-06-01)
Article
Restricted access - publisher's policySystem codes along with necessary nodalizations are valuable tools for thermal hydraulic safety analysis. In order to assess the safety of a particular power plant, in addition to the validation and veri cation of the code, ... -
Qualification of a full plant nodalization for the prediction of the core exit temperature through a scaling methodology
(2016-11)
Article
Open AccessSystem codes and their necessary power plant nodalizations are an essential step in thermal hydraulic safety analysis. In order to assess the safety of a particular power plant, in addition to the validation and verification ... -
Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
(2019-08-10)
Article
Restricted access - publisher's policyPREMIUM (Post BEMUSE Reflood Models Input Uncertainty Methods) was an activity launched with the aim of pushing forward the methods of quantification of physical model uncertainties in thermal-hydraulic codes. The benchmark ... -
RELAP/SCDAPSIM/MOD4.0 modification for transient accident scenario of test blanket modules involving helium flows into heavy liquid metal
(2015)
Conference lecture
Restricted access - publisher's policyThe Institute for Plasma Research (IPR), India, is currently involved in the design and development of its Test Blanket Module (TBM) for testing in ITER (International Thermo nuclear Experimental Reactor). The Indian TBM ... -
Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using core SCDAP components
(2015)
Conference lecture
Restricted access - publisher's policyThe recent accident in the Fukushima Daiichi nuclear power plant opened a discussion on severe accident management that includes the analysis of the accident by means of computational tools that can predict the core behavior ... -
Significance of the input parameters selection and the nodalization qualification in the final results of an IBLOCA BEPU calculation
(2016)
Conference report
Restricted access - publisher's policyIn the framework of Design Basis Accidents (DBA) for Pressurized Water Reactor (PWR), and based on recent studies on pipe integrity combined with the Risk-Informed Decision Making (RIDM), the USNRC proposed the Intermediate ... -
Simulación de experimentos realizados en la instalación PKL sobre pérdida total de suministro eléctrico
(2016)
Conference report
Restricted access - publisher's policyA raíz del accidente de la central nuclear de Fukushima Daiichi, se han realizado pruebas de resistencia encaminadas al estudio de las medidas y acciones a llevar a cabo durante escenarios de pérdida de suministro eléctrico ... -
Simulation of condensation in a closed, slightly inclined horizontal pipe with a modified RELAP5 code
(2014-07-01)
Article
Restricted access - publisher's policyThe performance of the RELAP5 thermal-hydraulic system code was analyzed in predicting very fast transient condensation processes in horizontal pipes. The code significantly underpredicted the heat transfer from the primary ... -
System code validation series based on a consistent plant nodalization of the ROSA/LSTF integra test facility
(2016)
Conference report
Restricted access - publisher's policyExperimental results obtained at integral test facilities are used in the validation process of thermal - hydraulic system codes for the steady - state and transient simulation of light water reactors. The expertise and ... -
Testing methodologies for quantifying physical models uncertainties. A comparative exercise using CIRCE and IPREM (FFTBM)
(2016-08-15)
Article
Restricted access - publisher's policyThe increasing importance of Best-Estimate Plus Uncertainty (BEPU) analyses in nuclear safety and licensing processes have lead to several international activities. The latest findings highlighted the uncertainties of ... -
Validation of a BEPU methodology through a blind benchmark activity at the PKL test facility
(American Nuclear Society (ANS), 2019)
Conference report
Restricted access - publisher's policyValidation is a key step in the field of thermal hydraulics and has played a crucial role in the implementation of system codes. These codes are then included in licensing methodologies being those either best estimate ...
