Determination of the Total Effective Dose of External and Internal Exposure by Different Ionizing Radiation Sources

Abstract

The purpose of the research is to develop an integrated technique for determining the effective dose (E) of external and internal exposure by different sources of ionizing radiation. The proposing technique for determining the total effective dose is based on three methods of calculation. The first one is multiplying the value of the individual dose equivalent $H_{p}(10)$ by the factor of 0.642 to account for radiation shielding by various organs and tissues and its backscattering. The second method is multiplying $H_{p}(10)$ by the conversion factor of air kerma in free air in a plate phantom, depending on the photon energy. The third method is multiplying $H_{p}(10)$ by the sum of the radiosensitivity coefficients of various organs and tissues. As a result of research, a complex method was developed for determining the total effective dose, composed of doses of cosmic radiation, external gamma-, beta- and neutron radiation, internal exposure from radionuclides, including CDP of radon and thoron, entering the body through the organs of digestion and respiration. The proposed technique for determining the total effective dose allows one to take into account the comprehensive effect of ionizing radiation sources on a person and to obtain a more accurate measure of radiation risk than the existing methods provide.

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

“…Thus, if we include the multiplications of magnitudes of each monofactor effect on its dose ratio, then in sum, we obtain a value equal to or greater than the actual effective dose received. This method became the basis of the methodology for determining the maximum effective dose [10].…”

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:…”