SILVA, DAYANE F.LIMA, ANA C. de S.SABUNDJIAN, GAIANE2019-07-232019-07-232018SILVA, DAYANE F.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE. Containment pressure analysis methodology during a LBLOCA with COCOSYS code. <b>International Journal of Development Research</b>, v. 8, n. 11, p. 24166-24172, 2018. Disponível em: http://repositorio.ipen.br/handle/123456789/29933.2230-9926http://repositorio.ipen.br/handle/123456789/29933During a nuclear power plant basic design accident, the containment integrity is a determining factor for the accident severity. The pressure and temperature conditions inside the containment in case of a Large Break Loss of Coolant Accident (LBLOCA) must be verified. This paper presents a containment pressure and temperature analysis methodology of a Brazilian PWR, Angra 2, using a code that simulates guillotine rupture - RELAP5 - and the COCOSYS code, which analyzes the containment pressure from the accident conditions. The Angra 2 containment behavior results during the design basis accidents studied - primary cooling system cold and hot legs guillotine ruptures - were satisfactory when compared to those presented in the Final Safety Analysis Report (FSAR / A2) and the pressure distributions were below the containment design pressure value (6.3bar).24166-24172openAccesslblocacomputer codesaccidentscontainmentcomputerized simulationpressure dependencec codesreactor accidentsangra-2 reactorteam generatorsArtigo de periódico1180000-0001-9544-4509https://orcid.org/0000-0001-9544-4509Sem PercentilSem Percentil CiteScore