Burnup
This model computes the local fuel burnup from the fission rate density. The specific power is derived from the fission rate and fuel density and is then time-integrated to obtain the burnup expressed in \(\mathrm{MWd/kg}\). The model also updates related irradiation quantities, including the irradiation time and the fraction of initial metal atoms (FIMA).
The implementation follows the steps used in Simulation::Burnup().
Inputs
The model uses the following variables:
Fission rate(history variable): fission rate density.Fuel density(sciantix variable): fuel density used to convert to specific power.Time step(physics variable): integration time step.
Specific power and burnup rate
The specific power is computed from the fission rate density using a constant conversion factor:
where
- \(\dot{F}\) is the fission rate density (Fission rate),
- \(\rho_f\) is the fuel density (Fuel density),
- \(C = 3.12 \times 10^{-17}\) is the conversion constant used in the code.
The burnup rate is then defined as:
so that burnup is expressed in \(\mathrm{MWd/kg}\).
Time integration
The burnup value is updated by time integration:
where \(\Delta t\) is the current time step (Time step). In the code, this
operation is performed using solver.Integrator.
Irradiation time
When the fission rate density is positive, the irradiation time is updated consistently with the burnup increment:
where \(\Delta B\) is the burnup increment over the current step. If the fission rate is zero, the irradiation time is kept constant.
FIMA
The Fraction of Initial Metal Atoms (FIMA) is updated as:
where
- \(U\) is the uranium inventory variable (U),
- \(\Delta t_{\mathrm{irr}}\) is the irradiation time increment.
Implementation note
In the source code, the model reference is reported as:
“The local burnup is calculated from the fission rate density.”