A coarse-mesh code for time-dependent multigroup neutron diffusion calculation based on a direct integration scheme for the time dependence and a low order nodal flux expansion approximation for the space variables has been implemented as a fast tool for transient analysis.
Montagnini B., Raffaelli P., Sumini M., Zardini D.M. (1996). A 3D coarse-mesh time dependent code for nuclear reactor kinetic calculations. ANNALS OF NUCLEAR ENERGY, 23(6), 517-532 [10.1016/0306-4549(95)00049-6].
A 3D coarse-mesh time dependent code for nuclear reactor kinetic calculations
Sumini M.Membro del Collaboration Group
;
1996
Abstract
A coarse-mesh code for time-dependent multigroup neutron diffusion calculation based on a direct integration scheme for the time dependence and a low order nodal flux expansion approximation for the space variables has been implemented as a fast tool for transient analysis.File in questo prodotto:
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