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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(1)
International Conference on Nuclear Engineering, Proceedings, ICONE(1)
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:scopusDesign investigation on flow diffuser with code-saturne - CFD simulation analysis
Conference ObjectAbstract: The flow rate distribution at the entrance of the core plays a key role for reactor design since itPalabras claves:Autores:Bellet S., Chen G., Dominique Álvarez, Howard R., Min J., Xu T.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:scopus