Neutronic power evolution by neutron kinetics
# Point Kinetics Model
This module contains a model of the neutronic power with six groups of delayed neutrons (it could be easily changed to 8 groups if needed).
Starting from the total reactivity (model input from the *ReactivityFeedbacks* module), this module calculates the time evolution of the fission power of the reactor.
The total power take into account also the residual power (which is computed and provided by the *DeecayHeat* module).
The default values for \\(Tlife\\) (*prompt neutron lifetime*), \\(Beta\\) (*delayed neutron fraction*) and \\(lambda\\) (*decay constant*), valid for U235, are taken from *S. Marguet, La physique des réacteurs nucléaire, Ed. Lavoisier, 2013*.
The equations can also be derived from the same source, setting:
- \\(n(t)\\) proportional to \\(Pneut\\)
- \\(C_i(t)\\) proportional to \\(Pdelay\\)
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