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Containment pressure analysis methodology during a LBLOCA with COCOSYS code

SILVA, DAYANE F.; LIMA, ANA C. de S.; SABUNDJIAN, GAIANE (2018)

An Angra 2 LBLOCA simulation model for RELAP5MOD3.3 code with uncertainty analysis

MADEIRA, ALZIRA A.; PEREIRA, LUIZ C.M.; SABUNDJIAN, GAIANE; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE (Associa????o Brasileira de Energia Nuclear, 2020)

Containment pressure analysis methodology during a LBLOCA with iteration between RELAP5 and COCOSYS

SILVA, DAYANE F.; SABUNDJIAN, GAIANE; LIMA, ANA CECILIA S.; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE (Associa????o Brasileira de Energia Nuclear, 2018)

Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant

BORGES, EDUARDO M.; SABUNDJIAN, GAIANE; DAURIA, FRANCESCO; PETRUZZI, ALESSANDRO (2018)

Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS line using melcor code

LEE, SEUNG M.; SABUNDJIAN, GAIANE; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE (Associa????o Brasileira de Energia Nuclear, 2018)

Simula????o de acidentes b??sicos de projeto, LBLOCAs, em Angra 2 com o c??digo RELAP5BR3.01/12 ??? Task 2.1

SABUNDJIAN, GAIANE (2016)

Simula????o de acidentes b??sicos de projeto, LBLOCAs, em Angra 2 com o c??digo RELAP5BR3.01/12 ??? Task 2.1

SABUNDJIAN, GAIANE (2016)

Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS injection line using MELCOR code

LEE, S.M.; LAPA, N.S.; SABUNDJIAN, G. (2019)

Fuel performance during in LBLOCA in Angra 1 Nuclear Power Plant

SABUNDJIAN, G.; CONTI, T.N.; MORANDINI, C.J.; ANDRADE, D.A.; TECHNICAL MEETING ON PROGRESS IN DEVELOPMENT AND USE OF COUPLED CODES FOR ACCIDENT ANALYSIS (2014)

Simula????o num??rica de um acidente tipo perda lenta de vaz??o em um reator nuclear de pesquisaNumerical simulation of a slow loss of flow accident in a nuclear research reactor

SCURO, NIKOLAS L. (2019)

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Containment pressure analysis methodology during a LBLOCA with COCOSYS code

An Angra 2 LBLOCA simulation model for RELAP5MOD3.3 code with uncertainty analysis

Containment pressure analysis methodology during a LBLOCA with iteration between RELAP5 and COCOSYS

Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant

Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS line using melcor code

Simula????o de acidentes b??sicos de projeto, LBLOCAs, em Angra 2 com o c??digo RELAP5BR3.01/12 ??? Task 2.1

Simula????o de acidentes b??sicos de projeto, LBLOCAs, em Angra 2 com o c??digo RELAP5BR3.01/12 ??? Task 2.1

Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS injection line using MELCOR code

Fuel performance during in LBLOCA in Angra 1 Nuclear Power Plant

Simula????o num??rica de um acidente tipo perda lenta de vaz??o em um reator nuclear de pesquisaNumerical simulation of a slow loss of flow accident in a nuclear research reactor