Small break loss of coolant accident of 200 cm?? in cold leg of primary loop of Angra2 nuclear power reactor evaluation

dc.creatorBORGES, EDUARDO M.
dc.creatorSABUNDJIAN, GAIANE
dc.date2021
dc.date2021-08-13T19:09:05Z
dc.date2021-08-13T19:09:05Z
dc.date.accessioned2023-09-28T14:19:04Z
dc.date.available2023-09-28T14:19:04Z
dc.identifier2319-0612
dc.identifierhttp://repositorio.ipen.br/handle/123456789/32162
dc.identifier2B
dc.identifier9
dc.identifier10.15392/bjrs.v9i2B.1274
dc.identifier0000-0001-9544-4509
dc.identifierSem Percentil
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/9002384
dc.descriptionThe aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 200cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core.
dc.format1-16
dc.relationBrazilian Journal of Radiation Sciences
dc.rightsopenAccess
dc.sourceMeeting on Nuclear Reactor Physics and Thermal Hydraulics (ENFIR), 21st; Meeting on Nuclear Industry (ENIN), 6th, October 21-25, 2019, Santos, SP
dc.subjectcladding
dc.subjectreactor cores
dc.subjectvoids
dc.subjectheat transfer
dc.subjectcoolant circuits
dc.subjectsbloca
dc.subjectsteady-state conditions
dc.subjecttwo-phase flow
dc.subjecteccs
dc.subjectreactor accident simulation
dc.titleSmall break loss of coolant accident of 200 cm?? in cold leg of primary loop of Angra2 nuclear power reactor evaluation
dc.typeArtigo de peri??dico
dc.coverageN


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