Investigation of neutron shielding properties depending on number of boron atoms for colemanite, ulexite and tincal ores by experiments and FLUKA Monte Carlo simulations

241Am–Be source and three samples including different amounts of boron atoms per unit volume called colemanite, ulexite and tincal were used in total macroscopic cross section experiments. Also FLUKA Monte Carlo code was used to simulate total macroscopic cross sections, absorbed doses and deposited energies by low energy neutron interactions. Besides half value layers of samples were calculated and compared to paraffin. As a result, ascending concentration of boron atoms can enhance neutron shielding property of samples. ► Neutron shielding capacities of colemanite, ulexite and tincal were investigated. ► Neutron total macroscopic cross section measurements were performed. ► FLUKA Monte Carlo code was used in simulations of shielding parameters. ► Results were evaluated as boron contents of samples.