This study provides new, essential data and models for the monoenergetic neutron removal cross-section required for neutron shielding. A Monte Carlo model using CERN FLUKA code was developed to calculate the energy-dependent removal cross-section for elements commonly used in radiation shielding materials. Neutron energies ranging from 0.5 to 20 MeV including the fusion neutrons at 2.5 and 14.1 MeV were analyzed to generate the required data. Unlike previous approaches, which often rely on approximations or limited datasets, this study provides comprehensive and precise models that describe energy-dependent removal cross-sections as functions of atomic weight and total neutron cross-section. The new models were successfully applied to neutron energies of 2.5 MeV and above, with enhanced accuracy for fission neutrons. The calculated removal cross-section data were compared with prior measurements and calculations, demonstrating the model’s capability to accurately predict the energy-dependent removal cross-sections for shielding materials such as iron, graphite, aluminum, lead, barite concrete, borosilicate glass, and polyethylene.