Figure 1. Modeling of a stylized human phantom in MCNP 6.3 for skin dose assessment from NORM products (10.1016/j.radphyschem.2025.112756).
Figure 2. (a) Room geometry and representation of the phantom used in the MCNP simulation, (b) Modeling with centralized phantom and (c) Visualization of the particle track in the VISED software for the source used in the simulation with MCNP.
Computational Dosimetry & Human Health
Skin absorption & stylized phantoms: : In recent research published, the MCNP 6.3 code was employed to evaluate the radiological impact of NORM-containing consumer products. The study utilized mathematical stylized phantoms to simulate the topical application of products like Henna, allowing for the estimation of equivalent doses to the skin, head, and arms (10.1016/j.radphyschem.2025.112756).
Building materials & voxel phantoms: In recent research published, the MCNP 6.3 code was employed to assess the radiological impact of naturally occurring radionuclides (²²⁶Ra, ²³²Th, and ⁴⁰K) in 50 Brazilian construction materials. The study combined HPGe gamma spectrometry with Monte Carlo simulations using the ICRP 110 REX anthropomorphic voxel phantom, enabling organ-specific dose estimation for occupants of standard dwellings (In review).