Containment pressure analysis methodology during a LBLOCA with COCOSYS code
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2018
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International Journal of Development Research
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Resumo
During a nuclear power plant basic design accident, the containment integrity is a determining
factor for the accident severity. The pressure and temperature conditions inside the containment in
case of a Large Break Loss of Coolant Accident (LBLOCA) must be verified. This paper presents
a containment pressure and temperature analysis methodology of a Brazilian PWR, Angra 2,
using a code that simulates guillotine rupture - RELAP5 - and the COCOSYS code, which
analyzes the containment pressure from the accident conditions. The Angra 2 containment
behavior results during the design basis accidents studied - primary cooling system cold and hot
legs guillotine ruptures - were satisfactory when compared to those presented in the Final Safety
Analysis Report (FSAR / A2) and the pressure distributions were below the containment design
pressure value (6.3bar).
Como referenciar
SILVA, DAYANE F.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE. Containment pressure analysis methodology during a LBLOCA with COCOSYS code. International Journal of Development Research, v. 8, n. 11, p. 24166-24172, 2018. Disponível em: http://repositorio.ipen.br/handle/123456789/29933. Acesso em: 27 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.