Openmc for shielding calcs

Hello! I would like to calculate dose rates on the surface as well as at a few specified distances from a cylindrical reactor shield. I would like to know the gamma and neutron specific doses as well, how can i begin attacking a problem like this as i am new to this program as well as particle transport programs as a whole.

I have a few examples that might be handy

This folder has tasks that cover surface and cell dose from gamma and neutrons

best of luck