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Simulation of a SBLOCA in a hot leg. Scaling considerations andapplication to a nuclear power plant

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Simulation of a SBLOCA in a hot leg. Scaling considerations andapplication to a nuclear power plant

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dc.contributor.author Querol Vives, Andrea es_ES
dc.contributor.author Gallardo Bermell, Sergio es_ES
dc.contributor.author Verdú Martín, Gumersindo Jesús es_ES
dc.date.accessioned 2016-05-05T09:29:48Z
dc.date.available 2016-05-05T09:29:48Z
dc.date.issued 2015-03
dc.identifier.issn 0029-5493
dc.identifier.uri http://hdl.handle.net/10251/63690
dc.description.abstract The main goal of this work is to study the physical phenomena observed during a Small Break Loss-Of-Coolant Accident transient performed in a small-scale Integral Test Facility and to determine the capabilityof the thermal hydraulic code TRACE5 to reproduce these phenomena in a scale-up model. The accidentscenario analyzed is based on Test 1.2 in the frame of the OECD/NEA ROSA Project, which simulatesa 1% hot leg Small Break Loss-Of-Coolant Accident in the Large Scale Test Facility of the Japan AtomicEnergy Agency. During this test, natural circulation in primary loops occurs, cooling the core during someminutes. This is an important phenomenon, which needs to be checked by means of different TRACE5models. With this aim, Test 1 2 has been simulated using a TRACE5 model reproducing the geometricaland thermal hydraulic features of Large Scale Test Facility. In order to determine if this phenomenon canbe reliably extrapolated to a scale-up plant, a new TRACE5 model has been developed. The geometricalfeatures of this scale-up model are determined using a fixed scaling ratio respect to the original LSTFfeatures. On the other hand, 4 and 3-loop standard Westinghouse PWR models are used in order tosimulate the same transient and compare the behaviour of the main thermal hydraulic variables withthose obtained in the Large Scale Test Facility model and in the Large Scale Test Facility scale-up model.Results show that both Large Scale Test Facility and the scale-up models present the same behaviourduring the whole transient. Important discrepancies are found in the results corresponding to 4 and3-loop PWR TRACE5 models. In both models, natural circulation is not properly reproduced. Trying toimprove the simulation results, the nodalizations of U-tubes and pressure vessel were tested. Resultsstate that the nodalization of U-tubes clearly affects the natural circulation simulation. However, thevessel nodalization effect is not as important. es_ES
dc.description.sponsorship This work contains findings produced within the OECD-NEA ROSA Project. This work is partially supported by the Grant-in-Aid for Scientific Research of the Spanish Ministerio de Educacion (Grant number: AP2009-2600), the Spanish Ministerio de Ciencia e Innovacion under Projects ENE2011-22823 and ENE2012-34585 and the Generalitat Valenciana under Projects PROMETEO/2010/039 and ACOMP/2013/237. en_EN
dc.language Inglés es_ES
dc.publisher Elsevier es_ES
dc.relation.ispartof Nuclear Engineering and Design es_ES
dc.rights Reserva de todos los derechos es_ES
dc.subject SMALL-BREAK LOCA es_ES
dc.subject ROSA-IV LSTF es_ES
dc.subject ORIENTATION es_ES
dc.subject TRANSIENT es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title Simulation of a SBLOCA in a hot leg. Scaling considerations andapplication to a nuclear power plant es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1016/j.nucengdes.2014.10.006
dc.relation.projectID info:eu-repo/grantAgreement/ME//AP2009-2600/ES/AP2009-2600/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/GVA//ACOMP%2F2013%2F237/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/MICINN//ENE2011-22823/ES/VALIUN-3D: VERIFICACION, VALIDACION, MEJORA Y CUANTIFICACION DE INCERTIDUMBRE EN CODIGOS 3D-NTH PARA ANALISIS DE SEGURIDAD/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/MINECO//ENE2012-34585/ES/Desarrollo de una plataforma multifísica de altas prestaciones para simulaciones Termohidráulico-Neutrónicas en ingeniería nuclear/ es_ES
dc.relation.projectID info:eu-repo/grantAgreement/GVA//PROMETEO%2F2010%2F039/ES/ANITRAN: METODOLOGIA DE ANALISIS DE INCERTIDUMBRES APLICADA A TRANSITORIOS DE PLANTAS NUCLEARES/ 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 Querol Vives, A.; Gallardo Bermell, S.; Verdú Martín, GJ. (2015). Simulation of a SBLOCA in a hot leg. Scaling considerations andapplication to a nuclear power plant. Nuclear Engineering and Design. 283:81-99. https://doi.org/10.1016/j.nucengdes.2014.10.006 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion http://dx.doi.org/10.1016/j.nucengdes.2014.10.006 es_ES
dc.description.upvformatpinicio 81 es_ES
dc.description.upvformatpfin 99 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 283 es_ES
dc.relation.senia 292157 es_ES
dc.contributor.funder Ministerio de Ciencia e Innovación es_ES
dc.contributor.funder Generalitat Valenciana es_ES
dc.contributor.funder Ministerio de Economía y Competitividad es_ES
dc.contributor.funder Ministerio de Educación es_ES


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