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Programa de controle de qualidade da agua em circuitos experimentais

CEGALLA, M.A.; 6o. CONGRESSO GERAL DE ENERGIA NUCLEAR (2014)

IEA-R1 primary and secondary coolant piping systems coupled stress analysis

FAINER, GERSON; FALOPPA, ALTAIR A.; OLIVEIRA, CARLOS A.; MATTAR NETO, MIGUEL; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 11th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 18th; MEETING ON NUCLEAR INDUSTRY, 3rd (Sao Paulo: ABEN, 2013, 2014)

Consequencia da operacao das bombas de refrigeracao do reator durante um acidente de perda de refrigerante primario por grande ruptura

SANTOS, G.A.; SABUNDJIAN, G.; 2o. CONGRESSO GERAL DE ENERGIA NUCLEAR (2014)

Modelo bifasico para bombas de circulacao de reatores nucleares refrigerados a agua leve pressurizada

SANTOS, G.A.; FREITAS, R.L.; 3o. ENCONTRO NACIONAL DE CIENCIAS TERMICAS (2014)

Modelagem do circuito primario de uma planta nuclear

NAKATA, H. (1993)

Desenvolvimento de um programa computacional para c??lculo do balan??o t??rmico no Circuito de Circula????o Natural CCN do IPEN/POLI durante a opera????o do circuito

CONTI, THADEU das N.; MENDES, LUIZ F.F.; SIMPOSIO INTERNACIONAL DE INICIA????O CIENT??FICA DA USP, 21. (2017)

Circuito experimental para pesquisa de sistemas de resfriamento de emergencia de reatores avancados

BAPTISTA FILHO, B.D.; GONCALVES, I.M.P.; ALMEIDA, J.C.; MACEDO, L.A.; SANTOS, S.C.; 7o. CONGRESSO GERAL DE ENERGIA NUCLEAR (2014)

ASME stress linearization and classification of a WYE piping junction

MATTAR NETO, MIGUEL; MIRANDA, CARLOS A. de J.; FALOPPA, ALTAIR A.; FAINER, GERSON; 2011 ANSYS CONFERENCE & ESSS USERS MEETING (2014)

ASME stress linearization and classification - A discussion based on a case study

MIRANDA, CARLOS A. de J.; FALOPPA, ALTAIR A.; MATTAR NETO, MIGUEL; FAINER, GERSON; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 10th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 17th; MEETING ON NUCLEAR INDUSTRY, 2nd (Sao Paulo: ABEN, 2011, 2014)

Estimative of core damage frequency in IPEN'S IEA-R1 research reactor due to the initiating event of loss of coolant clauded by large rupture in the pipe of the primary circuit

HIRATA, DANIEL M.; SABUNDJIAN, GAIANE; CABRAL, EDUARDO L.L.; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st (Sao Paulo: ABEN, 2009, 2014)

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