OpenMC for the study of radiation shields (gamma and neutrons)

I’m a new learner and I want to know if this program is suitable for radiation shielding applications because I see all the explanations and research about reactors and related topics.

I work in materials science, specifically working on glass as a radiation shield.

it can indeed with correct geometries and tallies. just curious what kind of glass you are exploring ?

Thank you for your reply. I work on borate glass with the addition of some heavy elements to the Borat matrix.