In the present work a neutronic model for the solution of two-dimensionl steady-state multigroup diffusion problems in nuclear reactor core is developed.The module can produce both direct fluxes as well as adjoint neutron importances.
Neutronic Methods for Core Calculations of the LFR Innovative Reactor
2008-12-23
Abstract
In the present work a neutronic model for the solution of two-dimensionl steady-state multigroup diffusion problems in nuclear reactor core is developed.The module can produce both direct fluxes as well as adjoint neutron importances.File in questo prodotto:
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