.ThermoSysPro.NuclearCore.NeutronKinetics

This module contains a model of the neutronic flux with six groups of delayed neutrons. Starting from the total reactivity, which is an input in the module and it is given by the sum of all the possible feedback effects (Doppler, moderator, control bars, boron and xenon), this module calculates the fission power of the reactor. The total power is the sum of the neutronic power and the residual power (which is an input of the module).

Information

ThermoSysPro Version 4.1

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