LEE, SEUNG M.LAPA, NELBIA S.SABUNDJIAN, GAIANE2020-01-152020-01-15LEE, SEUNG M.; LAPA, NELBIA S.; SABUNDJIAN, GAIANE. MELCOR simulation of a severe accident scenario derived from a small break loca in a typical PWR with passive autocatalytic recombiners. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. <b>Proceedings...</b> Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5346-5359. Disponível em: http://repositorio.ipen.br/handle/123456789/30720.http://repositorio.ipen.br/handle/123456789/30720This work presents the simulation of a severe accident scenario in a referential model of pressurized water reactor, which came about from a rupture of 20cm2 in a cold leg of a reactor cooling system. The simulation was carried out on the MELCOR code using a model elaborated by the Global Research for Safety – Germany, with the passive autocatalytic recombiners implemented in almost every compartment in the containment. The efficacy and effectiveness of this well-known mitigating measure of severe accident management are demonstrated by means of a comparison with the case previously simulated without this measure using the same model. This referential reactor is important and very useful for the independent analysis of severe accidents in the Brazilian Angra 2 nuclear power plant in virtue of the similarity between both of them, so that after some proper modifications on this referential reactor’s model, it could be applied for the study of severe accidents in the other. In this sense, the result presented in this work is to be taken as an important reference for the severe accident analysis of Angra 2.5346-5359openAccessboundary conditionscladdingloss of coolantm codesmelt-throughpwr type reactorsradiation protectionreactor accident simulationreactor cooling systemsTexto completo de evento0000-0001-9544-4509https://orcid.org/0000-0001-9544-4509