Abstract

Abstract Nuclear power accidents have demonstrated the need for reliable passive dosemeters that can estimate the doses from effluent gamma emitters with a wide range of energies, and give information on the energy distribution of the environmental gamma radiation. For this purpose, experimentally obtained energy responses from a TL dosemeter combination consisting of five CaSO4:Dy dosemeters with different filters were used as input for the SAND II computer code (Spectrum Analysis by Neutron Detectors) that had been adapted to evaluate the energy distribution of environmental gamma radiation and related doses. The dosemeters were exposed to radiation from the natural environment as well as that produced by artificial sources, and the estimated gamma ray energy distributions and doses were tested against results from measurements made with a sodium iodide spectrometer and a high pressure ionisation chamber.

Full Text
Published version (Free)

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call