METHODOLOGICAL RECOMMENDATIONS FOR MEASUREMENTINDIVIDUAL EQUIVALENT DOSES OF IRRADIATIONBY NEUTRON RADIATION OF STAFF OF BALAKOV NPP

The experimental and calculated results of determining correction factors for dosimeters used for individual dosimetric monitoring at the Balakovo NPP are presented.

INHALATION OF TRANSURANIC ELEMENTS IN CASE OF EMERGENCIES IN THE EXCLUSION ZONE OF THE CHERNOBYL NPP

Relevance. In the radioactive contamination territory, any work must be carried out with mandatory individual dosimetric monitoring of participants using all the irradiation pathways. However, at present, the control of personnel exposure through the respiratory organs is not carried out due to the lack of methodological and technical support.Intention. To estimate the irradiation doses of personnel expected as a result of inhalation of transuranic elements during fires in the Belarusian sector of the Chernobyl exclusion zone.Methodology. The objects of research are aerosol particles containing 137Cs, 90Sr, 238Pu, 239Pu, 240Pu, 241Pu and 241Am, formed as a result of high temperature sublimation and combustion of forest materials. The subject of research is the irradiation doses of personnel as a result of inhalation intake of 137Cs, 90Sr, 241Am, 238Pu, 239Pu, 240Pu and 241Pu during fire fighting.Results and Discussion. The expected doses of internal irradiation in fire extinguishing participants in the Belarusian sector of the Chernobyl exclusion zone due to inhalation of transuranic elements were estimated. The assessments were carried out both by direct measurements of the volume activity of radionuclides in the breathing zone of fire fighting participants and via calculations. It is shown that the contribution of 137Cs to the “inhalation” dose of personnel can be only 1 %. It is established that in the Belarusian sector of the Chernobyl exclusion zone the contribution of transuranic elements to the expected effective dose of internal radiation is about 60 %. Radiation doses of personnel expected as a result of inhalation of radionuclides did not exceed 0.1 mSv per year, which is significantly less than the control level established in the Polesye State Radiation Ecological Reserve for personnel (5 mSv per year).Conclusion. The proposed methods make it possible to conservatively assess the expected inhalation doses in personnel in case of fire fighting in the exclusion zone of the Chernobyl nuclear power plant, as well as to ensure their accounting for individual dosimetric control.

THERMOLUMINESCENT DETECTORS FOR SURVEILLANCE STUDIES OF RADIATION EXPOSURE OF THE POPULATION

Luminescent glow occurring in a substance exposed to ionizing radiation (IR) in the process of heating, thermoluminescence (TL) is now an effective method of registration of radiation-absorbed doses. It is important to be aware that the correct absorbed dose when exposed to mixed radiation with unknown characteristics is determined in the material of detector as well as in materials similar in composition (Z eff) and density [1-3]. In this connection, it is expedient to use different types of detectors for solution of different dosimetric problems. This study gives a comparison of the performance characteristics of TLD-K thermoluminescent detectors [4, 5], made of sodium silicate glass ceramic with the characteristics of IR detectors made of luminophors based on lithium fluoride monocrystals containing impurities of titanium and magnesium (TLD -100) [6, 7] and an anion of defective aluminum oxide (TLD-500) [8-11] widely used in thermoluminescence dosimetry. Comparison of a number of parameters that are relevant to the use of detectors in dosimetric monitoring of environment favors TLD-K detectors. The studies were carried out on the territory of the Kemerovo region.