Browsing by Author "Freixa Terradas, Jordi"
Now showing items 1-20 of 42
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A systematic approach for the adequacy analysis of a set of experimental databases: application in the framework of the ATRIUM activity
(2024-05-01)
Article
Restricted access - publisher's policyIn 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
(2024-04-01)
Article
Restricted access - publisher's policyThis 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
(2021-12-15)
Article
Open AccessThe 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 ... -
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 ... -
Assessment of SBO Fukushima likewise scenario for an IPWR design with RELAP5MOD33 and RELAPSCDAPSIMMOD3. 5 codes
(2022)
Conference report
Open AccessIn 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
(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 ... -
Development and application in multiscale and multiphysics methodologies in Spain: present and future trends
(2024-03-15)
Article
Open AccessIn 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
(2020-09-01)
Article
Open Accessnstitute 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
(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 ... -
Effectiveness of the ASVAD valve in a reactor vessel bottom leak scenario
(2021-09-15)
Article
Open AccessDecay 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
(Elsevier, 2024-03-01)
Article
Restricted access - publisher's policyScaling 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
(2023-04-01)
Article
Open AccessAddressing 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
(2022)
Conference report
Restricted access - publisher's policyThe 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
(2022)
Conference report
Restricted access - publisher's policyThe 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
(2022-02-28)
Article
Open AccessThe 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 ... -
Modelling guidelines for core exit temperature simulations with system codes
(2015-05-01)
Article
Open Access -
Modelling guidelines for safety analysis of Station Black Out sequences based on experiments at the PKL test facility
(2020-04-01)
Article
Open AccessAfter 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 ... -
Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
(2022-08-01)
Article
Open AccessThe 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
(2022-04-01)
Article
Open AccessCode 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 ...
