Hi,
I was reading how to get the total absorption reaction rate in the section “Specifying tallies” in OpenMC Documentation. In the website it says that the absorption tally does not count reactions that produce secondary neutrons.
In my tests doing the “Total Reaction Rate - Total Scattering Reaction Rate” is equal the absorption mean value. So it shows that the absorption rate counts reactions like fission. Am i missunderstanding something? For me seems like that description in the website is not helping at all. My results are similar between MCNP and OpenMC. Im just asking this because im curious right now.
Thanks guys.