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The three-dimensional flow and temperature fields occurring in the FFTF during a flow transient followed by a reactor scram have been simulated by the COMMIX-1A computer code. The transient simulated corresponds to the tests conducted at the Hanford Engineering and Development Laboratory. The COMMIX-1A code employs the porous media formulation in which the concepts of volume porosity, surface permeability, distributed resistance, and distributed heat source are used to model a flow domain with internal structures. The governing equations for conservation of mass, momentum, and energy are solved as a boundary-value problem in space and as an initial-value problem in time. The present report presents the calculated results for the steady-state reactor full-power operation and for a transient from full flow down to natural circulation combined with a power scram.