RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop

dc.creatorBORGES, EDUARDO M.
dc.creatorSABUNDJIAN, GAIANE
dc.creatorBRAZ FILHO, FRANCISCO A.
dc.creatorGUIMAR??ES, LAMARTINE N.F.
dc.creatorINTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.date2020-01-15T18:32:25Z
dc.date2020-01-15T18:32:25Z
dc.dateOctober 21-25, 2019
dc.date.accessioned2023-09-28T14:13:50Z
dc.date.available2023-09-28T14:13:50Z
dc.identifierhttp://repositorio.ipen.br/handle/123456789/30727
dc.identifier0000-0001-9544-4509
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/9000954
dc.descriptionThe aim of this paper was to simulate and evaluate the basic design accident of 80 cm?? small break loss of coolant accident (SBLOCA) in the cold leg of the primary loop of the Angra2 nuclear power plant. In this simulation, it was verified that the actuation logics of the Angra2 Reactor Protection System (RPS) and the Emergency Core Cooling System (ECCS) used in this simulation worked correctly, maintaining core integrity with acceptable temperatures throughout the event. The results obtained were satisfactory when compared with those presented by the Angra2 Final Safety Analysis Report (FSAR/A2).
dc.format5469-5478
dc.publisherAssocia????o Brasileira de Energia Nuclear
dc.rightsopenAccess
dc.subjectactuators
dc.subjectangra-2 reactor
dc.subjectboundary conditions
dc.subjectprimary coolant circuits
dc.subjectr codes
dc.subjectreactor accident simulation
dc.subjectreactor cooling systems
dc.subjectreactor cores
dc.subjectreactor protection systems
dc.subjectsafety analysis
dc.subjectsbloca
dc.subjectsteady-state conditions
dc.subjectvoid fraction
dc.titleRELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop
dc.typeTexto completo de evento
dc.coverageI
dc.localRio de Janeiro


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