modelNeutronKinetics
Neutronic power evolution by neutron kinetics
Information
# 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\\)
## Copyright © EDF 2002 - 2026
## ThermoSysPro Version 4.2
Parameters
| Type | Name | Default | Description |
|---|
| ThermoSysPro.Units.SI.Time | Tlife | 20e-6 | Average lifetime of the prompt neutrons in the core (s) |
| Real | Kfuel | 1 | Ratio between the power produced in the fuel and the total power |
| Real[6] | Lambda | {0.0124, 0.0305, 0.111, 0.301, 1.14, 3.01} | Radioactivity constants of the groups of the delayed neutrons (1/s) |
| Real[6] | Beta | {0.00021, 0.00142, 0.00128, 0.00257, 0.00075, 0.00027} | Fraction of delayed neutrons in each group with respect to the total number of neutrons emitted per fission |
| Real | Ptot0 | 524e6 | Initial power of the core |
