Modeling radiation protection of containers for transporting isotopes with high-energy beta irradiation

Abstract

At research nuclear reactors, isotopes are accumulated for various purposes including sources of beta radiation. For transportation use containers made of heavy materials (for example lead, tungsten). They have good protective properties but when braking beta radiation, powerful secondary gamma radiation can occur. To solve this problem, the mechanism of the occurrence of bremsstrahlung is considered. A model of the process is described its regularity is formulated, and the dependence of the electron energy loss in the material is derived. The diagram of radiation, ionization and total losses for tungsten are given. The maximum thicknesses of materials are determined, at which the kinetic energy of an electron is completely consumed. The calculated part of the energy transferred to the bremsstrahlung. Based on the obtained data, the option of creating protection when dealing with beta sources is proposed.At research nuclear reactors, isotopes are accumulated for various purposes including sources of beta radiation. For transportation use containers made of heavy materials (for example lead, tungsten). They have good protective properties but when braking beta radiation, powerful secondary gamma radiation can occur. To solve this problem, the mechanism of the occurrence of bremsstrahlung is considered. A model of the process is described its regularity is formulated, and the dependence of the electron energy loss in the material is derived. The diagram of radiation, ionization and total losses for tungsten are given. The maximum thicknesses of materials are determined, at which the kinetic energy of an electron is completely consumed. The calculated part of the energy transferred to the bremsstrahlung. Based on the obtained data, the option of creating protection when dealing with beta sources is proposed.