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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: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:scopus