I am currently performing a quantitative comparison study between Geant4 and MCNP6.2 that concerns the number and nature of interactions between 14 MeV neutrons and a natural silicon target. If Geant4 easily gives the complete reaction schemes with details about all secondary products (including protons, alphas, heavy ions,...), I have some difficulties with MCNP. In the PTRAC files, I can only obtain information on the interactions via the MT code but never on the exact nature of the reaction fragments (under the format ZZZAAA for example).

For example, the following event :

9000 1 14028 101 1 1 1

0.84158E+00 0.80635E+00 0.57715E-03 0.00000E+00 0.00000E+00 -0.10000E+01 0.14000E+02 0.10000E+01 0.27800E-04

neutron interacts with a 14-Si-28 following a capture interaction (MT = 101).... If they exist, what additional options add in the PHYS or PTRAC cards to obtain the exact nature of this reaction, in terms of secondaries produced ?

In Geant4, a simple text output will give, for example:

[neutron + Si28 --> proton + Al28]

Thank you for your help.