Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation

BORGES, EDUARDO M.SABUNDJIAN, GAIANE2021-08-132021-08-132021BORGES, EDUARDO M.; SABUNDJIAN, GAIANE. Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation. <b>Brazilian Journal of Radiation Sciences</b>, v. 9, n. 2B, p. 1-16, 2021. DOI: <a href="https://dx.doi.org/10.15392/bjrs.v9i2B.1274">10.15392/bjrs.v9i2B.1274</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/32162.2319-0612http://repositorio.ipen.br/handle/123456789/32162The 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.1-16openAccesscladdingreactor coresvoidsheat transfercoolant circuitssblocasteady-state conditionstwo-phase floweccsreactor accident simulationSmall break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluationArtigo de periódico2B910.15392/bjrs.v9i2B.12740000-0001-9544-4509https://orcid.org/0000-0001-9544-4509Sem Percentil