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Publisher
International Conference on Nuclear Engineering, Proceedings, ICONE(2)
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP(1)
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Física aplicada(2)
Ciencias de la computación(1)
Otras ramas de la ingeniería(1)
Química física(1)
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scopus(3)
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: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