Browsing by Author "Reventós Puigjaner, Francesc Josep"
Now showing items 1-20 of 36
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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 ... -
Code improvement and model validation for Asco-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal-hydraulic code
(2016-01-01)
Article
Open AccessThis paper provides a Best Estimate validation calculation with a coupled thermal–hydraulic and 3D neutron kinetic model for Ascó-II Nuclear Power Plant. Common NRC codes have been used for its purpose. TRACE is the code ... -
Comparison of best-estimate plus uncertainty and conservative methodologies for a PWR MSLB analysis using a coupled 3-D neutron-kinetics/thermal-hydraulic code
(2017-05-04)
Article
Open AccessThis paper compares the Best-Estimate Plus Uncertainty (BEPU) methodology with the Conservative Bounding methodology for design-basis-accident analysis. Calculations have been performed with TRACE [for thermal-hydraulic ... -
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 ... -
International Course to Support Nuclear Licensing by User Training in the Areas of Scaling, Uncertainty, and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes: 3D S.UN.COP Seminars
(2008)
Article
Restricted access - publisher's policy -
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 ... -
Master’s degree in Nuclear Engineering UPC-ENDESA. A consolidated international program
(2016)
Conference lecture
Open AccessThe Master’s degree in Nuclear Engineering (MNE) UPC-ENDESA offers a unique and practical oriented training, with the aim to prepare competent engineers so that they can assume managerial positions within the Nuclear ... -
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 ... -
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison
(2022-12)
Article
Restricted access - publisher's policySeveral TH-TH code coupling methods are used in the nuclear industry to model the core thermal–hydraulic conditions and the system behaviour. In some cases, the boundary conditions obtained by system codes are applied to ... -
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
Open AccessValidation 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 ... -
Project-based learning in the Master’s degree in Nuclear Engineering at BarcelonaTECH. Experience gained in the area of Management of Nuclear Power Plants
(2014)
Conference report
Restricted access - publisher's policyFrom its first edition, that took place in 2011-2012, the Master’s degree in Nuclear Engineering from BarcelonaTECH has been using techniques of Project-Based Learning to fulfil the purpose of training nuclear engineers ... -
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, ...
