Is possible to separate tally result according to source distribution values?

Hello,
In a simulation with a source having a discrete energy distribution, is there a way to separate the tally result according to which energy of source distribution the source particle is coming?
Thank you in advance,
JM

There is no EnergyBornFilter in OpenMC at this time. Fortunately, it would be straightforward to get this information by replacing your 1 simulation using discrete distribution with N energies, by N simulations using a distribution with 1 energy each.

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Thank you. I will do that.