[The 1st radiation protection decree and its significance for the physician].
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Some aids of collective and individual radioprotection of the medical personnel during a conduction of intracavitary gammatherapy are evaluated. The characteristics of the production equipment (a semi-automatic protection line, a set for radiation following the principle of simple afterloading, remote afterloading) are given, and their operation principles are described. The materials concerning the radiation-hygienic analysis of the medical personnel labour conditions are reported. Measures providing their reliable protection during manipulations with radioactive sources are delineated.
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I review recent work at Los Alamos undertaken to evaluate neutron, proton, and photonuclear cross-sections up to 150 MeV (to 250 MeV for protons), based on experimental data and nuclear model calculations. These data are represented in the ENDF format and can be used in computer codes to simulate radiation transport. They permit calculations of absorbed dose in the body from therapy beams, and through use of kerma coefficients allow absorbed dose to be estimated for a given neutron energy distribution. In radiation protection, these data can be used to determine shielding requirements in accelerator environments and to calculate neutron, proton, gamma-ray, and radionuclide production. Illustrative comparisons of the evaluated cross-section and kerma coefficient data with measurements are given.
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