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RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions

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RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions

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dc.contributor.author Villanueva López, José Felipe es_ES
dc.contributor.author Carlos Alberola, Sofía es_ES
dc.contributor.author Sánchez Sáez, Francisco es_ES
dc.contributor.author Martón Lluch, Isabel es_ES
dc.contributor.author Martorell Alsina, Sebastián Salvador es_ES
dc.date.accessioned 2018-09-30T04:30:50Z
dc.date.available 2018-09-30T04:30:50Z
dc.date.issued 2017 es_ES
dc.identifier.issn 1687-6075 es_ES
dc.identifier.uri http://hdl.handle.net/10251/108647
dc.description.abstract [EN] Nuclear power plant risk has to be quantified in full power and in other modes of operation. This latter situation corresponds to low power and shutdown modes of operation in which the residual heat removal (RHR) system is required to extract the heat generated in the core. These accidental sequences are great contributors to the total plant risk. Thus, it is important to analyze the plant behavior to establish the accident mitigation measures required. In this way, PKL facility experimental series were undertaken to analyze the plant behavior in other modes of operation when the RHR is lost. In these experiments, the plant configurations were changed to analyze the influence of steam generators secondary side configurations, the temperature inside the pressurizer, and the inventory level on the plant behavior. Moreover, different accident management measures were proposed in each experiment to reach the conditions to restart the RHR. To understand the physical phenomena that takes place inside the reactor, the experiments are simulated with thermal-hydraulic codes, and this makes it possible to analyze the code capabilities to predict the plant behavior. This work presents the simulation results of four experiments included in PKL experimental series obtained using RELAP5/Mod3.3. es_ES
dc.description.sponsorship This study is part of the work developed by the Polytechnic University of Valencia within a project of the OECD, in which authors are participating under the leadership of the Consejo de Seguridad Nuclear (STN/4524/2015/640). The authors thank PKL III, especially AREVA, program organizers for the information supplied.
dc.language Inglés es_ES
dc.publisher Hindawi Limited es_ES
dc.relation.ispartof Science and Technology of Nuclear Installations es_ES
dc.rights Reserva de todos los derechos es_ES
dc.subject Midloop es_ES
dc.subject PKL es_ES
dc.subject RELAP5 es_ES
dc.subject.classification ESTADISTICA E INVESTIGACION OPERATIVA es_ES
dc.subject.classification INGENIERIA NUCLEAR es_ES
dc.title RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions es_ES
dc.type Artículo es_ES
dc.identifier.doi 10.1155/2017/6140323 es_ES
dc.relation.projectID info:eu-repo/grantAgreement/CSN//STN%2F4524%2F2015%2F640/ es_ES
dc.rights.accessRights Abierto 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 Villanueva López, JF.; Carlos Alberola, S.; Sánchez Sáez, F.; Martón Lluch, I.; Martorell Alsina, SS. (2017). RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions. Science and Technology of Nuclear Installations. 2017:1-11. https://doi.org/10.1155/2017/6140323 es_ES
dc.description.accrualMethod S es_ES
dc.relation.publisherversion https://doi.org/10.1155/2017/6140323 es_ES
dc.description.upvformatpinicio 1 es_ES
dc.description.upvformatpfin 11 es_ES
dc.type.version info:eu-repo/semantics/publishedVersion es_ES
dc.description.volume 2017 es_ES
dc.relation.pasarela S\326202 es_ES
dc.contributor.funder Consejo de Seguridad Nuclear es_ES


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