This paper provides a Best Estimate validation calculation with a coupled thermal–hydraulic and 3D neutron kinetic model for Ascó-II Nuclear Power Plant. Common NRC codes have been used for its purpose. TRACE is the code used for the thermal–hydraulic system calculations; PARCS is the code used for the 3D neutron kinetics calculations. Cross section calculations were performed with the HELIOS lattice physics code, finally GenPMAXS was used to convert the cross section into the PARCS format. A simplified three dimensional 3D neutronics model of the Ascó II NPP is used as a core kinetics model. A 3D cylindrical thermal–hydraulic vessel plus 1D representation of th...
free text keywords: :Energies::Energia nuclear [Àrees temàtiques de la UPC], Nuclear power plants, Nuclear energy, Nuclear safety, 3D neutron kinetics, Reactor physics modeling, Best Estimate calculation, 3D NK-TH, Dynamic control rod movement, Centrals nuclears -- Mesures de seguretat, Energia nuclear, Nuclear Energy and Engineering, Neutron, Source code, media_common.quotation_subject, media_common, Nuclear power plant, law.invention, law, Control rod, Computer science, Nuclear engineering, Thermal hydraulics, Cylinder, Neutron transport, Lattice (order)
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