This report describes the work performed by the Gruppo di Ricerca Nucleare di San Piero a Grado (GRNSPG) of the University of Pisa (as member of CIRTEN consortium) in the frame of the “Accordo di Programma MSE-ENEA sulla Ricerca di Sistema Elettrico - Piano Annuale di Realizzazione 2013”. The objective of the performed activity was to further contribute to the qualification and improvement of the CFD/system-code coupling tool that had previously been developed in the framework of PAR 2011 and PAR 2012 by the same working group. The scientific and technological relevance of such contribution relies on the fact that the availability of qualified thermal-hydraulic analysis tools and methodologies, which combine multi-scale simulation capabilities, allows a more accurate analysis of nuclear reactor cooling systems (to support both design and safety assessment) in those cases featuring a close interaction between system-scale phenomena (e.g. the natural circulation in a nuclear reactor cooling loop) and local and inherently three-dimensional phenomena (e.g. the heat transfer between coolant and fuel rods, etc.).

Report sull’accoppiamento di codici CFD e codici di sistema

Moretti, F.
2014-09-24

Abstract

This report describes the work performed by the Gruppo di Ricerca Nucleare di San Piero a Grado (GRNSPG) of the University of Pisa (as member of CIRTEN consortium) in the frame of the “Accordo di Programma MSE-ENEA sulla Ricerca di Sistema Elettrico - Piano Annuale di Realizzazione 2013”. The objective of the performed activity was to further contribute to the qualification and improvement of the CFD/system-code coupling tool that had previously been developed in the framework of PAR 2011 and PAR 2012 by the same working group. The scientific and technological relevance of such contribution relies on the fact that the availability of qualified thermal-hydraulic analysis tools and methodologies, which combine multi-scale simulation capabilities, allows a more accurate analysis of nuclear reactor cooling systems (to support both design and safety assessment) in those cases featuring a close interaction between system-scale phenomena (e.g. the natural circulation in a nuclear reactor cooling loop) and local and inherently three-dimensional phenomena (e.g. the heat transfer between coolant and fuel rods, etc.).
Rapporto tecnico;Tecnologia dei metalli liquidi;Generation IV reactors;Calcolo parallelo
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/7733
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