A thermo-fluid dynamics code with the purpose to investigate three-dimensional pressure, velocity and temperature fields inside nuclear reactors is presented in this work. The code computes pressure, velocity and temperature fields at the coarse fuel assembly level when all the sub-channel details are summarized in parametric coefficients. A 3D CFD model for an open core liquid metal reactor has been implemented on a finite element code and some preliminary tests for generic geometries are reported.
A THREE-DIMENSIONAL CFD PROGRAM FOR THE SIMULATION OF THE THERMO-HYDRAULIC BEHAVIOUR OF AN OPEN CORE LIQUID METAL REACTOR
Monti, S.
2009-03-23
Abstract
A thermo-fluid dynamics code with the purpose to investigate three-dimensional pressure, velocity and temperature fields inside nuclear reactors is presented in this work. The code computes pressure, velocity and temperature fields at the coarse fuel assembly level when all the sub-channel details are summarized in parametric coefficients. A 3D CFD model for an open core liquid metal reactor has been implemented on a finite element code and some preliminary tests for generic geometries are reported.File in questo prodotto:
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RSE-2009-085 Frontespizio.pdf.pdf
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XUNIBO-P9LU-001_rev 0.pdf
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