Mostrando 6 resultados de: 6
Filtros aplicados
Publisher
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017(2)
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP(2)
International Conference on Nuclear Engineering, Proceedings, ICONE(1)
Proceedings of the ASME/JSME International Conference on Nuclear Engineering, ICONE(1)
Área de conocimiento
Dinámica de fluidos(4)
Simulación por computadora(4)
Ingeniería mecánica(1)
Simulación(1)
Origen
scopus(6)
Assessment of the reactor pressure vessel integrity in PTS conditions. Thermal hydraulic study of a safety injection in a three loop PWR plant with the finite element code N3S
ArticleAbstract: This paper explains the Research and Development program started at E.D.F about the cooling phenomenPalabras claves:Autores:Bellet S., Dominique Álvarez, Martin A., Ternon Morin F.Fuentes:scopus3D computations of the primary coolant flow in a 1300 MW PWR vessel. Normal operation steady state and free boron plugs mixing transient simulations
Conference ObjectAbstract: This paper reports a R&D action based on numerical simulations and experiments on the primary coolanPalabras claves:Autores:Dominique Álvarez, Martin A., Stelletta S.Fuentes:scopusNumerical comparison of the effect of different lower plenum flow diffusers on the core inlet flow distribution of a PWR with Code_Saturne
Conference ObjectAbstract: Reactor pressure vessel internal structures, especially those located in the lower plenum, may havePalabras claves:CFD, Code_Saturne, Flow diffuser, New Reactor Design, PIRT analysisAutores:Bellet S., Dominique Álvarez, Ge J., Howard R., Min J., Tian W., Xu T.Fuentes:scopusNumerical simulation of VVER type reactor internal flow and optimization of the flow diffuser with Code Saturne
Conference ObjectAbstract: In the pressurizer water reactor (PWR) vessel, the coolant flow field is very complex due to the prePalabras claves:CFD, Code_Saturne, Flow diffuser, PIRT, VVERAutores:Bellet S., Dominique Álvarez, Ge J., Howard R., Min J., Tian W., Xu T.Fuentes:scopusThree dimensional calculations of the primary coolant flow in a 900 MW PWR vessel. Numerical simulation of the accurate RCP start-up transient flow rate
Conference ObjectAbstract: Pointed out by the 1986 French PWR Safety studies and by a 1995 OCDE/NEA Specialist Meeting, a potenPalabras claves:Autores:Cases F., Dominique Álvarez, Martin A., Stelletta S.Fuentes:scopusThree dimensional calculations of the primary coolant flow in a 900 MW PWR vessel. Steady state and transients computations
Conference ObjectAbstract: This paper reports a Research and Development action based on numerical simulations and experimentsPalabras claves:Autores:Cases F., Dominique Álvarez, Martin A.Fuentes:scopus