Browsing by Author "Martínez Quiroga, Víctor Manuel"
Now showing items 1-18 of 18
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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 ... -
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 ... -
Modelado de un ciclo de potencia de CO2 supercrítico para reactores de fusión utilizando RELAP5-3D
(2013)
Conference report
Restricted access - publisher's policyEn 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
(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 ... -
Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5-3D
(2014-04-01)
Article
Restricted access - publisher's policyA 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 ... -
On the scaling of uncertainties in thermal hydraulic system codes
(2020-02-01)
Article
Open AccessThe 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
(2021-08-01)
Article
Restricted access - publisher's policyValidation 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
(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
Open AccessSystem 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 ... -
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 ... -
The use of system codes in scaling studies: relevant techniques for qualifying NPP nodalizations for particular scenarios
(2014-02-10)
Article
Restricted access - publisher's policySystem codes along with necessary nodalizations are valuable tools for thermal hydraulic safety analysis. Qualifying both codes and nodalizations is an essential step prior to their use in any significant study involving ... -
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 ...
