Dear experts,
I carried out additional simulations with Voxel phantom and same neutron source geometry and I kept all other cards similar to the above inputs. This resulted nearly similar results as given in reference of ICRP 116. With voxel phantom, I could get expected dose deposition for all energies and organs.
Hence, is the discrepancy due to mesh geometry? Can you please guide if any additional card needs to be added for neutron dosimetry in mesh phantom?
Regards,
Riya