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dc.contributor.author | Peña-Monferrer, Carlos | es_ES |
dc.contributor.author | Pellacani, F. | es_ES |
dc.contributor.author | Chiva Vicent, Sergio | es_ES |
dc.contributor.author | Barrachina Celda, Teresa María | es_ES |
dc.contributor.author | Miró Herrero, Rafael | es_ES |
dc.contributor.author | Macián-Juan, R. | es_ES |
dc.date.accessioned | 2015-03-27T18:05:39Z | |
dc.date.issued | 2012 | |
dc.identifier.issn | 1137-2885 | |
dc.identifier.uri | http://hdl.handle.net/10251/48423 | |
dc.description.abstract | [EN] A computational code system called Coupled Solver ANSYS CFX/PARCS (CSAP) based on coupling the 3D neutron diffusion code PARCS v2.7 and the ANSYS CFX 13.0 Computational Fluid Dynamics (CFD) code has been developed as a tool for nuclear reactor systems simulations. This paper presents the coupling methodology between the CFD and the neutronic code. The methodology to simulate a 3D-neutronic problem coupled with 1D thermalhydraulics is already a mature technology, being part of the regular calculations performed to analyze different kinds of Reactivity Insertion Accidents (RIA) and asymmetric transients in Nuclear Power Plants, with state-of-the-art coupled codes like TRAC-B/NEM, RELAP5/PARCS, TRACE/PARCS, RELAP3D, RETRAN3D, etc. The transport of neutrons depends on several parameters, like fuel temperature, moderator temperature and density, boron concentration and fuel rod insertion. These data are calculated by the CFD code with high local resolution and used as input to the neutronic code to calculate a 3D nodal power distribution that will be returned and remapped to the CFD code control volumes (cells). Since two different nodalizations are used to discretize the same system, an averaging and interpolating procedure is needed to realize an effective data exchange. These procedures have been developed by means of the ANSYS CFX “User Fortran” interface; a library with several subroutines has been developed for calculation and synchronization purposes. The data exchange is realized by means of the Parallel Virtual Machine (PVM) software package. In this contribution, steady-state and transient results of a quarter of PWR fuel assembly with cold water injection are presented and compared with obtained results from a RELAP5/PARCS v2.7 coupled calculation. A simplified model for the spacers has been included. A methodology has been introduced to take into account the pressure drop and the turbulence enhancement produced by the spacers. | es_ES |
dc.description.sponsorship | This research was supported by the “Plan Nacional de I+D+i” Project EXPERTISER ENE2010-21368-C02-01 and ENE2010-21368-C02-02. | |
dc.language | Inglés | es_ES |
dc.publisher | Sne | es_ES |
dc.relation.ispartof | Nuclear Espana | es_ES |
dc.rights | Reserva de todos los derechos | es_ES |
dc.subject | CFX | es_ES |
dc.subject | PARCS | es_ES |
dc.subject | RELAP | es_ES |
dc.subject | Coupling | es_ES |
dc.subject | TH/N | es_ES |
dc.subject | CSAP | es_ES |
dc.subject.classification | ESTADISTICA E INVESTIGACION OPERATIVA | es_ES |
dc.subject.classification | INGENIERIA NUCLEAR | es_ES |
dc.title | CFD-Neutronic coupled calculation of a PWR fuel assembly considering pressure drop and turbulence produced by spacer grids | es_ES |
dc.type | Artículo | es_ES |
dc.type | Comunicación en congreso | |
dc.embargo.lift | 10000-01-01 | |
dc.embargo.terms | forever | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/MICINN//ENE2010-21368-C02-01/ES/REALIZACION Y MODELACION DE EXPERIMENTOS DE EFECTOS SEPARADOS CON FLUJO BIFASICO RELEVANTES PARA LA SEGURIDAD DE REACTORES NUCLEARES/ | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/MICINN//ENE2010-21368-C02-02/ES/REALIZACION Y MODELACION DE EXPERIMENTOS DE EFECTOS SEPARADOS CON FLUJO BIFASICO RELEVANTES PARA LA SEGURIDAD DE REACTORES NUCLEARES. CONTRIBUCION UJI/ | |
dc.rights.accessRights | Abierto | es_ES |
dc.contributor.affiliation | Universitat Politècnica de València. Instituto de Ingeniería Energética - Institut d'Enginyeria Energètica | es_ES |
dc.contributor.affiliation | Universitat Politècnica de València. Departamento de Estadística e Investigación Operativa Aplicadas y Calidad - Departament d'Estadística i Investigació Operativa Aplicades i Qualitat | 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 | Peña-Monferrer, C.; Pellacani, F.; Chiva Vicent, S.; Barrachina Celda, TM.; Miró Herrero, R.; Macián-Juan, R. (2012). CFD-Neutronic coupled calculation of a PWR fuel assembly considering pressure drop and turbulence produced by spacer grids. Nuclear Espana. 52-61. http://hdl.handle.net/10251/48423 | es_ES |
dc.description.accrualMethod | S | es_ES |
dc.relation.conferencename | 38 Reunión Anual de la Sociedad Nuclear Española | |
dc.relation.conferencedate | October 17-19, 2012 | |
dc.relation.conferenceplace | Cáceres, Spain | |
dc.description.upvformatpinicio | 52 | es_ES |
dc.description.upvformatpfin | 61 | es_ES |
dc.type.version | info:eu-repo/semantics/publishedVersion | es_ES |
dc.relation.senia | 241321 | |
dc.contributor.funder | Ministerio de Ciencia e Innovación |