Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant

dc.creatorBORGES, EDUARDO M.
dc.creatorSABUNDJIAN, GAIANE
dc.creatorDAURIA, FRANCESCO
dc.creatorPETRUZZI, ALESSANDRO
dc.date2018
dc.date2018-12-12T18:09:22Z
dc.date2018-12-12T18:09:22Z
dc.date.accessioned2023-09-28T14:09:03Z
dc.date.available2023-09-28T14:09:03Z
dc.identifier1741-6361
dc.identifierhttp://repositorio.ipen.br/handle/123456789/29364
dc.identifier2
dc.identifier12
dc.identifieraguardando
dc.identifierSem Percentil
dc.identifier22.00
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/8999606
dc.descriptionOwing to the occurrence of nuclear accidents, worldwide nuclear regulatory organisations included the analysis of accidents considered as design basis accidents ??? Loss of Coolant Accident (large and small-break, LBLOCA or SBLOCA) ??? in the safety analysis reports of nuclear facilities. In Brazil, the tool selected by the licensing authority, Comiss??o Nacional de Energia Nuclear (CNEN), is RELAP5 Code. The aim of this paper is the evaluation of the performance of the Emergency Core Cooling System (ECCS) of Angra 2 nuclear reactor during SBLOCA. In this study, the RELAP5 code and the Code Internal Assessment of Uncertainty (CIAU) were used to simulate and analyse the uncertainties of the results. The postulated accident is the SBLOCA in the hot leg connected to the ECCS described in the Final Safety Analysis Report of Angra 2 (FSAR/A2). The results from this study were satisfactory when compared with the FSAR/A2.
dc.format139-160
dc.relationInternational Journal of Nuclear Energy Science and Technology
dc.rightsclosedAccess
dc.subjectreactor safety
dc.subjectregulations
dc.subjectpower reactors
dc.subjectinternational regulations
dc.subjectloss of coolant
dc.subjectsbloca
dc.subjectlbloca
dc.subjectcomputer codes
dc.subjectradiation protection
dc.subjecteccs
dc.subjectsafety analysis
dc.subjectrisk assessment
dc.subjectangra-2 reactor
dc.titleUncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant
dc.typeArtigo de peri??dico
dc.coverageI


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