Estimative of core damage frequency in IPEN's IEA-R1 research reactor due to the initiating events of loss of low caused by channel blockage and loss of coolant caused by large rupture in the pipe of the primary circuit - PSA level 1

dc.creatorHIRATA, DANIEL M.
dc.creatorSABUNDJIAN, GAIANE
dc.creatorINTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 10th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 17th; MEETING ON NUCLEAR INDUSTRY, 2nd
dc.date2014-11-17T18:09:57Z
dc.date2014-11-18T18:01:28Z
dc.date2015-04-02T05:57:55Z
dc.date2014-11-17T18:09:57Z
dc.date2014-11-18T18:01:28Z
dc.date2015-04-02T05:57:55Z
dc.dateOctober 24-28, 2011
dc.date.accessioned2023-09-28T13:19:15Z
dc.date.available2023-09-28T13:19:15Z
dc.identifierhttp://repositorio.ipen.br/handle/123456789/16245
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/8993349
dc.publisherSao Paulo: ABEN, 2011
dc.rightsopenAccess
dc.subjectdamage
dc.subjectdepressurization systems
dc.subjectdeterministic estimation
dc.subjectfault tree analysis
dc.subjectflow blockage
dc.subjectiear-1 reactor
dc.subjectloss of coolant
dc.subjectloss of flow
dc.subjectnuclear damage
dc.subjectpipes
dc.subjectprimary coolant circuits
dc.subjectprobabilistic estimation
dc.subjectreactor operation
dc.subjectreactor shutdown
dc.subjectrisk assessment
dc.subjectsafety analysis
dc.subjectsafety injection
dc.subjecteccs
dc.titleEstimative of core damage frequency in IPEN's IEA-R1 research reactor due to the initiating events of loss of low caused by channel blockage and loss of coolant caused by large rupture in the pipe of the primary circuit - PSA level 1
dc.typeTexto completo de evento
dc.coverageI


Este ítem pertenece a la siguiente institución