Small break loss of coolant accident of 200 cm² in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation
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Data
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2019
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INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Resumo
The 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.
Como referenciar
BORGES, EDUARDO M.; SABUNDJIAN, GAIANE. Small break loss of coolant accident of 200 cm² in cold leg of primary loop of ANGRA 2 nuclear power reactor evaluation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 5479-5490. Disponível em: http://repositorio.ipen.br/handle/123456789/30728. Acesso em: 28 Mar 2024.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.