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dc.contributor.author | Lorduy, M. | es_ES |
dc.contributor.author | Querol, A. | es_ES |
dc.contributor.author | Gallardo Bermell, Sergio | es_ES |
dc.contributor.author | Verdú Martín, Gumersindo Jesús | es_ES |
dc.date.accessioned | 2022-04-29T18:04:17Z | |
dc.date.available | 2022-04-29T18:04:17Z | |
dc.date.issued | 2021-11-30 | es_ES |
dc.identifier.uri | http://hdl.handle.net/10251/182307 | |
dc.description.abstract | [EN] The inspections performed in Davis Besse and the South Texas Project Unit-I reactors pointed out safety issues regarding the structural integrity of the Pressure Vessel (PV). In these inspections, two anomalies were found: a wall thinning and degradation in the PV upper head of the Davis Besse reactor and a small amount of residue around two instrument-tube penetration nozzles located in the PV lower plenum of the South Texas Project Unit-I reactor. The evolution of these defects could have resulted in Small Break Loss-Of-Coolant Accidents (SBLOCA) if they had not been detected in time. In this frame, the OECD/NEA considered the necessity to simulate these accidental sequences in the OECD/NEA ROSA Project using the Large Scale Test Facility (LSTF). This work is focused on simulating different hypothetical accidental scenarios in the PV using the thermalhydraulic code TRACE5. These simulations allow studying the break localization influence in the transient and the effectiveness of the accident management (AM) actions considered mitigating the consequences of these hypothetical accidental scenarios. | es_ES |
dc.description.sponsorship | This work contains findings that were produced within the OECD-NEA ROSA Project. The authors are grateful to the Management Board of the ROSA Project for their consent to this publication and thank the Spanish Nuclear Regulatory Body (CSN) for the technical and financial support under the agreement STN/1388/05/748 | es_ES |
dc.language | Inglés | es_ES |
dc.publisher | Sociedade Brasileira de Proteção Radiológica | es_ES |
dc.relation.ispartof | Brazilian Journal of Radiation Sciences | es_ES |
dc.rights | Reserva de todos los derechos | es_ES |
dc.subject | SBLOCA | es_ES |
dc.subject | AM actions | es_ES |
dc.subject.classification | INGENIERIA NUCLEAR | es_ES |
dc.subject.classification | ESTADISTICA E INVESTIGACION OPERATIVA | es_ES |
dc.title | Break location influence in pressure vessel SBLOCA scenarios | es_ES |
dc.type | Artículo | es_ES |
dc.relation.projectID | info:eu-repo/grantAgreement/CONSEJO DE SEGURIDAD NUCLEAR//STN%2F1388%2F2005%2F748//ANALISIS Y SIMULACION DE LOS EXPERIMENTOS OECD PKL Y ROSA OECD. APLICACION A LAS CC.NN. ESPAÑOLAS (SUBPROYECTO 2)/ | 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 | Lorduy, M.; Querol, A.; Gallardo Bermell, S.; Verdú Martín, GJ. (2021). Break location influence in pressure vessel SBLOCA scenarios. Brazilian Journal of Radiation Sciences. 8(3B):1-17. http://hdl.handle.net/10251/182307 | es_ES |
dc.description.accrualMethod | S | es_ES |
dc.relation.publisherversion | https://www.bjrs.org.br/revista/index.php/REVISTA | es_ES |
dc.description.upvformatpinicio | 1 | es_ES |
dc.description.upvformatpfin | 17 | es_ES |
dc.type.version | info:eu-repo/semantics/publishedVersion | es_ES |
dc.description.volume | 8 | es_ES |
dc.description.issue | 3B | es_ES |
dc.identifier.eissn | 2319-0612 | es_ES |
dc.relation.pasarela | S\432970 | es_ES |
dc.contributor.funder | CONSEJO DE SEGURIDAD NUCLEAR | es_ES |