Study of shielding characteristics of certain materials. I

The results are presented of measurements of neutron spectra and gamma radiation from the 252Cf source for various practically used shielding materials. Used for shielding was a Pb plate 100 mm in thickness, a Bi sphere with a wall 80 mm thick, an Fe box with a 40 mm wall, a polyethylene box of 40 to 90 mm in wall thickness and a boron content of 1.5 to 5.0% and the combinations of these shieldings. The effect is discussed of the materials used for shielding and their geometrical configuration on changes in neutron and gamma radiation spectra from this source as the basis for the interpretation of data from personnel dosemeters with regard to radiation protection. (Ha)