Methods for simulating the flow of a fluid in a vessel of a nuclear reactor and for calculating the mechanical deformation of assemblies of a nuclear reactor core, and associated computer program products

Methods for simulating the flow of a fluid in a vessel of a nuclear reactor and for calculating the mechanical deformation of assemblies of a nuclear reactor core, and associated computer program products

The method includes determining an additional volume inside the vessel, the additional volume being outside the core volume, axially at one end thereof and axially delimited by two interfaces, one of which is the first or second interface; and the computing, for the additional volume and using the e...

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Bibliographische Detailangaben
Hauptverfasser: Galpin, Jérémy, Mery De Montigny, Elodie, Chazot, Benjamin, Salaün, Hubert, Goreaud, Nicolas
Format: Patent
Sprache:eng
Schlagworte:
CALCULATING
COMPUTING
COUNTING
ELECTRIC DIGITAL DATA PROCESSING
GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC
GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS
NUCLEAR ENGINEERING
NUCLEAR PHYSICS
NUCLEAR POWER PLANT
PHYSICS
REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGYGENERATION, TRANSMISSION OR DISTRIBUTION
TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE
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Beschreibung
Zusammenfassung:The method includes determining an additional volume inside the vessel, the additional volume being outside the core volume, axially at one end thereof and axially delimited by two interfaces, one of which is the first or second interface; and the computing, for the additional volume and using the equations, the pressure and speed, from an initial value of the speed or pressure in each of the interfaces of the additional volume.