Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
4925777 | Nuclear Engineering and Design | 2017 | 13 Pages |
Abstract
Within the FP7 European project THINS (Thermal Hydraulics of Innovative Nuclear Systems), numerical tools for the simulation of the thermal-hydraulics of next generation rector systems were developed, applied and validated for innovative coolants. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH participated in THINS with activities related to the development and validation of computational fluid dynamics (CFD) and coupled System Thermal Hydraulics (STH) - CFD codes. High quality measurements from the L-STAR and TALL-3D experiments were used to assess the numerical results. Two-equation eddy viscosity and scale resolving turbulence models were used in the validation process of ANSYS CFX for gas and liquid metal flows with conjugate heat transfer. This paper provides a brief overview on the main results achieved at GRS within the project.
Keywords
CIPLBEURANSCHTIPTGRsPRTSASSSTBottom plateSTHILWOECD/NEALESDNSCelKarlsruhe Institute of TechnologyLaser Doppler anemometryConjugate heat transferLDAThermocoupleShear Stress TransportCFDComputational fluid dynamicsRANSReynolds averaged Navier–StokesLead-bismuth eutecticLarge Eddy SimulationDirect Numerical SimulationTurbulent Prandtl numberCADcomputer aided designThermal-hydraulicKit
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
A. Papukchiev, S. Buchholz,