Use este identificador para citar ou linkar para este item: http://carpedien.ien.gov.br:8080/handle/ien/2099
Tipo: report
Título: Analysis of natural circulation in a thermal hydraulic loop similar to a passive nuclear reactor cooling system (part 2: single-phase and two-phase results)
Autor(es): Faccini, José Luiz Horacio
Sampaio, Paulo Augusto Berquó de
Moreira, Maria de Lourdes
Resumo: The main topic in this report is a new device being considered to improve nuclear reactor safety employing the natural circulation. Aware of the need for more precise and stable numerical models we developed a new computation software employing a finite element formulation. In tit a stable pressure equation is derived from the continuity equation, where all pressure contributions arising from the momentum and energy conservation equations, and the state-equation are accounted implicitly in time. The thermal equilibrium homogeneous model with the vapor velocity explicitly calculated using the Drift-Flux model is employed for a good representation of the physics of the two-phase flow. A thermal hydraulics loop in reduced scale similar to a Pressurized Water Reactor (PWR) passive heat removal system was built at IEN to obtain typical natural circulation two-phase flow data and to validate numerical models. Two experimental tests in single and two-phase flows were made to begin and to validation of the model. Comments on the results and a discussion of the importance of software validation are presented.
Palavras-chave: Two-phase flow
Natural circulation
Drift-flux
Passive systems
Similarity
Finite-element
Petrov-galerkin weighted-residual
Idioma: eng
País: Brasil
Editor: Instituto de Engenharia Nuclear
Sigla da Instituição: IEN
Tipo de Acesso: restrictAccess
URI: http://carpedien.ien.gov.br:8080/handle/ien/2099
Data do documento: Mar-2002
Aparece nas coleções:Engenharia e Segurança de Reatores Nucleares - Relatórios

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