Any way to get MT number for a given interaction?

Geant4 Version:

Operating System:
Ubuntu 20.04.6 LTS

CMake Version:

Hi All

I’m trying to create a simulation of a scintillating material and I’m trying to verify the reaction cross sections for incident neutrons. I currently record the recoiling particles along with the energy they deposit in the medium but there are multiple ways that a given particle can be produced, e.g. the 12C(n,alpha) and 12C(n,3 alpha) reactions.

Is there a way to record exactly which reaction is being sampled from whenever the neutrons interact with the material?

Thanks in advance