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A CFD analysis of blockage length on a partially blocked fuel rod

SCURO, N.L.; UMBEHAUN, P.E.; ANGELO, E.; ANGELO, G.; ANDRADE, D.A. (2019)

CFD analysis of blockage length on a partially blocked fuel rod

SCURO, NIKOLAS L.; ANGELO, GABRIEL; ANGELO, EDVALDO; ANDRADE, DELVONEI A. de; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE (Associa????o Brasileira de Energia Nuclear, 2018)

CFD analysis of blockage length on a partially blocked fuel rod

SCURO, N.L.; ANGELO, G.; ANGELO, E.; ANDRADE, D.A.; 60 YEARS OF IEA-R1: INTERNATIONAL WORKSHOP ON UTILIZATION OF RESEARCH REACTORS (Instituto de Pesquisas Energ??ticas e Nucleares, 2018)

Estudo experimental do efeito da razão de bloqueio em canal aerodinâmico sobre o Número de Strouhal e o fenômeno da biestabilidade no escoamento em cilindrosExperimental study of the effect of blockage ratio in aerodynamic channel on strouhal number and on the bistability phenomenon of the flow in cylinders

Silveira, Rodrigo Santiago (2011)

Analise teorica dos experimentos GE-8-21 e GE-1004-3 com o codigo termohidraulico ATHLET

GEBRIM, A.N.; 9o. ENCONTRO NACIONAL DE FISICA DE REATORES E TERMOHIDRAULICA (p. 383-386, 2014)

Estimative of core damage frequency in IPEN's IEA-R1 research reactor due to the initiating events of loss of low caused by channel blockage and loss of coolant caused by large rupture in the pipe of the primary circuit - PSA level 1

HIRATA, DANIEL M.; SABUNDJIAN, GAIANE; 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)

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A CFD analysis of blockage length on a partially blocked fuel rod

CFD analysis of blockage length on a partially blocked fuel rod

CFD analysis of blockage length on a partially blocked fuel rod

Analise teorica dos experimentos GE-8-21 e GE-1004-3 com o codigo termohidraulico ATHLET

Estimative of core damage frequency in IPEN's IEA-R1 research reactor due to the initiating events of loss of low caused by channel blockage and loss of coolant caused by large rupture in the pipe of the primary circuit - PSA level 1

Study of the densification of uranium-erbium system

Desempenho de gotejadores com uso de esgoto doméstico tratado

Critical velocity experimental assessment in flat plate fuel element for nuclear research reactor

Desempenho de gotejadores com uso de esgoto doméstico tratado

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A CFD analysis of blockage length on a partially blocked fuel rod

CFD analysis of blockage length on a partially blocked fuel rod

CFD analysis of blockage length on a partially blocked fuel rod

Analise teorica dos experimentos GE-8-21 e GE-1004-3 com o codigo termohidraulico ATHLET

Estimative of core damage frequency in IPEN's IEA-R1 research reactor due to the initiating events of loss of low caused by channel blockage and loss of coolant caused by large rupture in the pipe of the primary circuit - PSA level 1

Study of the densification of uranium-erbium system

Desempenho de gotejadores com uso de esgoto doméstico tratado

Critical velocity experimental assessment in flat plate fuel element for nuclear research reactor

Desempenho de gotejadores com uso de esgoto doméstico tratado