title: Shielding for thermal neutrons.
abstract: The problem of calculating the neutron capture gamma-ray dose rate due to thermal neutron capture in a boron or cadmium rectangular shield is considered. An example is given for shielding for a door at the exit of medical accelerator room maze in order to determine the optimum location of lead relative to the borated polyethylene.
authors.affiliation: McCall Associates, Woodside, California 94062, USA.
authors.forename: R C
authors.initials: RC
authors.lastname: McCall
mesh_terms: D001895:Boron; D002104:Cadmium; D004867:Equipment Design; D005214:Fast Neutrons / Q000627:therapeutic use; D005720:Gamma Rays; D006801:Humans; D009502:Neutrons / Q000627:therapeutic use; D016273:Occupational Exposure / Q000517:prevention & control; D010315:Particle Accelerators; D011835:Radiation Protection
chemical_list: D002104:Cadmium; D001895:Boron