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Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior

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Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior

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dc.contributor.author Ordóñez-Ródenas, José es_ES
dc.contributor.author Lázaro Chueca, Aurelio es_ES
dc.contributor.author Martorell Alsina, Sebastián Salvador es_ES
dc.date.accessioned 2018-01-11T09:24:03Z
dc.date.available 2018-01-11T09:24:03Z
dc.date.issued 2016 es_ES
dc.identifier.uri http://hdl.handle.net/10251/94463
dc.description.abstract [EN] One of the goals of Generation IV reactors is to increase safety from those of previous generations. Different research platforms have been identified the need to improve the reliability of the simulation tools to ensure the capability of the plant to accommodate the design basis transients established in preliminary safety studies. The paper describes the modelling of primary pumps in advanced sodium cooled reactors using the TRACE code. Following the implementation of the models, the results obtained in the analysis of different design basis transients are compared with the simplifying approximations used in reference models. The paper shows the process to obtain a consistent pump model of the ESFR (European Sodium Fast Reactor) design and the analysis of loss of flow transients triggered by pumps coast-down analyzing the thermal hydraulic neutronic coupled system response. A sensitivity analysis of the system pressure drops effect and the other relevant parameters that influence the natural convection after the pumps coast-down is also included. es_ES
dc.language Inglés es_ES
dc.publisher EDP Sciences es_ES
dc.relation.ispartof EPJ Nuclear Sciences & Technologies es_ES
dc.rights Reconocimiento - No comercial (by-nc) es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1051/epjn/2016027 es_ES
dc.rights.accessRights Abierto es_ES
dc.contributor.affiliation Universitat Politècnica de València. Departamento de Ingeniería Química y Nuclear - Departament d'Enginyeria Química i Nuclear es_ES
dc.description.bibliographicCitation Ordóñez-Ródenas, J.; Lázaro Chueca, A.; Martorell Alsina, SS. (2016). Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior. EPJ Nuclear Sciences & Technologies. 2(38):1-7. doi:10.1051/epjn/2016027 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion https://doi.org/10.1051/epjn/2016027 es_ES
dc.description.upvformatpinicio 1 es_ES
dc.description.upvformatpfin 7 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 2 es_ES
dc.description.issue 38 es_ES
dc.identifier.eissn 2491-9292 es_ES
dc.relation.pasarela S\325807 es_ES
dc.description.references Fiorini, G. L., & Vasile, A. (2011). European Commission – 7th Framework Programme. Nuclear Engineering and Design, 241(9), 3461-3469. doi:10.1016/j.nucengdes.2011.01.052 es_ES
dc.description.references Lázaro, A., Ammirabile, L., Bandini, G., Darmet, G., Massara, S., Dufour, P., … Stempniewicz, M. (2014). Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking. Nuclear Engineering and Design, 266, 1-16. doi:10.1016/j.nucengdes.2013.10.019 es_ES
dc.description.references Lazaro, A., Schikorr, M., Mikityuk, K., Ammirabile, L., Bandini, G., Darmet, G., … Stempniewicz, M. (2014). Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis. Nuclear Engineering and Design, 277, 265-276. doi:10.1016/j.nucengdes.2014.02.029 es_ES
dc.description.references D. Blanchet, L. Buiron, ESFR Working horse description, European Sodium Fast Reactor Consortium? Deliverable SP2.1.2.D1, 2009 es_ES
dc.description.references Mikityuk, K. (2009). Heat transfer to liquid metal: Review of data and correlations for tube bundles. Nuclear Engineering and Design, 239(4), 680-687. doi:10.1016/j.nucengdes.2008.12.014 es_ES
dc.description.references NRC, inTrace v5.0 Theory manual, Field Equations, Solution Methods, and Physical Models(Office for Nuclear Regulatory Research, Washington, 2012), Chap. 10 es_ES


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