Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant
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2018
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International Journal of Nuclear Energy Science and Technology
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Resumo
Owing to the occurrence of nuclear accidents, worldwide nuclear
regulatory organisations included the analysis of accidents considered as design
basis accidents – Loss of Coolant Accident (large and small-break, LBLOCA
or SBLOCA) – in the safety analysis reports of nuclear facilities. In Brazil, the
tool selected by the licensing authority, Comissão Nacional de Energia Nuclear
(CNEN), is RELAP5 Code. The aim of this paper is the evaluation of the
performance of the Emergency Core Cooling System (ECCS) of Angra 2
nuclear reactor during SBLOCA. In this study, the RELAP5 code and the Code
Internal Assessment of Uncertainty (CIAU) were used to simulate and analyse
the uncertainties of the results. The postulated accident is the SBLOCA in the
hot leg connected to the ECCS described in the Final Safety Analysis Report of
Angra 2 (FSAR/A2). The results from this study were satisfactory when
compared with the FSAR/A2.
Como referenciar
BORGES, EDUARDO M.; SABUNDJIAN, GAIANE; DAURIA, FRANCESCO; PETRUZZI, ALESSANDRO. Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant. International Journal of Nuclear Energy Science and Technology, v. 12, n. 2, p. 139-160, 2018. Disponível em: http://repositorio.ipen.br/handle/123456789/29364. Acesso em: 24 Apr 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.