ANA CECILIA DE SOUZA LIMA
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Artigo IPEN-doc 25715 Containment pressure analysis methodology during a LBLOCA with COCOSYS code2018 - SILVA, DAYANE F.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANEDuring 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).Artigo IPEN-doc 24025 Containment pressure analysis methodology during a LBLOCA with iteration between RELAP5 and COCOSYS2017 - SILVA, DAYANE F.; SABUNDJIAN, GAIANE; LIMA, ANA CECILIA S.Artigo IPEN-doc 21033 Methodology of a PWR containment analysis during a thermal-hydraulic accident2015 - SILVA, DAYANE F.; SABUNDJIAN, GAIANE; LIMA, ANA C.S.