Exploració per autor "Pericas Casals, Raimon"
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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)
Text en actes de congrés
Accés obertIn 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 ... -
Code improvement and model validation for Asco-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal-hydraulic code
Pericas Casals, Raimon; Ivanov, K; Reventós Puigjaner, Francesc Josep; Batet Miracle, Lluís (2016-01-01)
Article
Accés obertThis 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
Pericas Casals, Raimon; Ivanov, K.; Reventós Puigjaner, Francesc Josep; Batet Miracle, Lluís (2017-05-04)
Article
Accés obertThis 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 ... -
Contribution to the validation of best estimate plus uncertainties coupled codes for the analysis of NK-TH nuclear transients
Pericas Casals, Raimon (Universitat Politècnica de Catalunya, 2015-05-15)
Tesi
Accés obertThe calculations that allow the operating license of the nuclear reactors are usually made using conservative methods. This conservatism, often excessive, limits the actual capabilities of the industry to increase energy ... -
Multi-physics framework for whole-core analysis of transient fuel performance after load following in a pressurised water reactor
Peakman, Aiden; Gregg, Robert; Bennett, Tom; Casamor Vidal, Max; Martínez Quiroga, Víctor Manuel; Freixa Terradas, Jordi; Pericas Casals, Raimon; Rossiter, Glyn (2022-08-01)
Article
Accés restringit per política de l'editorialThe 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 ... -
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: past, present and future
Freixa Terradas, Jordi; Barrachina Celda, Teresa María; Berna Escriche, Cesar; Bocanegra Melian, Rafael; Carlos Alberola, Sofía; Castro Gonzalez, Emilio; Cuervo Gomez, Diana; Durán Vinuesa, Luis Felipe; Escrivá Castells, Facundo Alberto; Feria Márquez, Francisco; Fernández Cosials, Kevin; Martínez Quiroga, Víctor Manuel; Pérez-Ferragut, Marina; Pericas Casals, Raimon; Reventós Puigjaner, Francesc Josep (Elsevier, 2024-02-01)
Article
Accés restringit per política de l'editorialBest-Estimate Plus Uncertainty (BEPU) nuclear safety analysis is an approach widely used in the field of nuclear engineering and reactor safety assessment. It aims to provide a more realistic assessment of reactor safety ...