Dear Cihangir,
for question 2, currently I am using source distributions from ORIGEN already (or maybe .f71 files from criticality calculation).
Please correct if I made a mistake:
Currently I applied the source distribution in a "source region" using .f71 file as an input.
Neutrons may activate some of the shielding material and that material could decay. Does the decay products participate in the shielding calculation?
Or maybe consider this example(although not an activation example):
consider neutron hitting a Boron Layer. SCALE calculates the gamma from "10B(n,α)7Li" reaction as you replied above.
Does SCALE also consider photons created by (n,γ) from 7Li? Because Li was not defined initially in the geometry, and my source from .f71 is only applied in the source region and not in shielding material.
Thank you,
Zeyu Chen