Este é um artigo publicado em acesso aberto (Open Access) sob a licença Creative Commons Attribution, que permite uso, distribuição e reprodução em qualquer meio, sem restrições desde que o trabalho original seja corretamente citado.Simulação do acidente de perda de refrigerante na linha do sistema de resfriamento de emergência do núcleo conectada à perna fria do circuito primário de ANGRA 2Simulation of the loss of coolant accident in the emergency core cooling system line connected to cold leg of the primary loopof ANGRA 2
ABSTRACTDue to the occurrence of nuclear accidents, worldwide nuclear regulatory organizations included the analysis of accidents considered as design basis accidents -Loss of Coolant Accident (large and small-break LOCA) -in the safety analysis reports of nuclear facilities . In Brazil, the tool selected by the licensing authority, Comissão Nacional de Energia Nuclear (CNEN), is the Reactor Excursion and Leak Analysis Program Code (RELAP5). The aim of this paper is the evaluation of the performance of the Emergency Core Cooling System (ECCS) of Angra 2 nuclear reactor during Small Break LOCA (SBLOCA). The methodology used to develop this study considered: the rupture area is 380 cm 2 , considered a Small Break LOCA (SBLOCA) described in Chapter 15 of the Final Safety Analysis Report of ANGRA 2 -FSAR/A2.The initial and boundary conditions adopted to the simulation are descried in the FSAR/A2. The results show that the a
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.
Este é um artigo publicado em acesso aberto (Open Access) sob a licença Creative Commons Attribution, que permite uso, distribuição e reprodução em qualquer meio, sem restrições desde que o trabalho original seja corretamente citado.
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