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).
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ThermoSysPro Version 4.1
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.ThermoSysPro.NuclearCore.NeutronKinetics