Methods of calculation of radiation protection for operational safety optimization at working with radionuclide photon radiation sources

Abstract

Operational dosimetry solves the problem of implementing the principle of optimizing radiation safety, which is closely related to regulation and justification and implies a realistic achievable reduction in the dose load on a person when using ionizing radiation sources by reducing operating time, increasing the distance to radioactive material and shielding for attenuation of ionization flux. The article describes two ways of determining the thickness of shielding under necessity of making operational decision to protect a person from radionuclide source of known activity or the dose rate created by it. Based on the required multiplicity of its attenuation, which allows determining the number of half attenuation layers in the shield or its thickness, is also dependent on the energy of radiation, emitted by the source.

Devising an alternative technique to manufacture a radioisotope source of 60Co for irradiation device to ensure ornithological safety of aircraft flights

“…where d is the thickness of the nickel layer on the copper substrate, μm (d = 50 μm); v -nickel dissolution rate, μm/min (v = 10 μm/min). Due to the high activity of the irradiated target (15 mCi), creating an ambient gamma radiation dose equivalent rate of about 50 μSv/h [9,10], the dissolution of the deposited nickel layer is carried out under constant radiometric control. When the target dissolves, the following are formed:…”