A contribution to the calibration procedure for radiation protection dosimeters using a 252Cf neutron source

A detailed analysis was made of the mixed (n,γ) field of the 252Cf neutron source used for secondary standardization of neutron radiation. Neutron spectra obtained experimentally from two Cf sources were compared with those calculated using the Monte Carlo method. Neutron fluence was measured using solid state track detectors with fission radiators in free-air geometry or on the surface of the BOMAB phantom. Detectors were irradiated either using an unshielded Cf source or with the same source located in a polyethylene or iron ball 100 mm in diameter. Tissue kerma was evaluated from all measured and calculated spectra for different conditions of irradiation. (M.D.)