code to find the neutron flux value, atomic density and burn-up level through depletion time (burn-up time)

User Support
1

Dear,
All

is there an openmc code to find the neutron flux value, atomic density and burn-up level through depletion time (burn-up time) ?

Thx,
Aul

2

Hi Aul

Yes there is depletion available in OpenMC

Here is an example

https://docs.openmc.org/en/latest/examples/pincell-depletion.html

Best

Jon