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Publisher
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP(1)
International Conference on Nuclear Engineering, Proceedings, ICONE(1)
Origen
scopus(2)
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:scopus