Filters for Albedo Neutron Dosimeter: Material Selection, Calculation, Experiment

Several boron-containing materials and methods for manufacturing neutron filters for albedo neutron luminescent dosimeters are considered. For such filters, experimental and analytical methods have been used to determine the attenuation coefficients for directly incident thermal neutrons, whose impact significantly worsens the metrological characteristics and leads to an overestimation of radiation doses. It was found that filters that meet the requirements for mass thickness and attenuation coefficients can be made from borated ABS plastics, polyethylene and rubber, provided that they contain at least 20% boron carbide or boron nitride.