Calculation of Internal Dose and Possible Limits for Intakes of Radionuclides in Case of Plutonium Wounds

2021 ◽  
Vol 65 (6) ◽  
pp. 27-37
Author(s):  
A. Molokanov ◽  
B. Kukhta ◽  
B. Galushkin
Keyword(s):  
Effective Dose ◽  
Systemic Circulation ◽  
Medical Intervention ◽  
Internal Exposure ◽  
Internal Dose ◽  
Regulatory Requirements ◽  
Biokinetic Model ◽  
Prognostic Assessment ◽  
Calculated Dose ◽  
Expert Analysis

Purpose: Assessment of the degree of compliance with the principles of radiation safety and regulatory requirements in case of plutonium wounds. Material and methods: Using a wound intake of plutonium by a worker as an example, issues of the formation of the internal dose due to the wound intake and formal comparison of calculated dose values with regulatory requirements are considered. The calculations are carried out using expert analysis of the experimental data on the urine excretion of plutonium during the observation period of 7 years based on the ICRP model for direct intake into blood. In addition, calculations are carried out using prognostic assessment of the same dose values based on the biokinetic model for radionuclide-contaminated wounds published by NCRP Report No 156 together with the above model of the ICRP for plutonium compounds Strong, Colloids, Particles and Fragment. Results: Based on the calculations, possible annual limits on intakes (ALI) of radionuclides in case of plutonium wounds are derived. As criteria for determining the ALI, dose values were taken that due to the uptake of the radionuclide into the systemic circulation from the wound for any calendar year considered for 50 years after the wound intake of selected plutonium compound. Namely, the committed effective dose; the effective dose implemented in a year and the organ annual equivalent dose (to bone surface and liver). Conclusion: Based on the analysis of the above calculations, the authors formulated the formation features of the employee’s internal exposure due to wound intake of plutonium and recommendations for determining the value of plutonium intake in the wound, evaluating the effectiveness of decorporation therapy and determining the type of radionuclide compound. This allows one to more accurately assess the degree of compliance with regulatory requirements and make an informed decision on the necessary measures of medical intervention and their urgency.

scholarly journals Alpha Spectrometry of Radon Short-Lived Progeny in Drinking Water and Assessment of the Public Effective Dose: Results from the Cilento Area, Province of Salerno, Southern Italy

Materials ◽  
2020 ◽  
Vol 13 (24) ◽  
pp. 5840
Author(s):  
Enver Faella ◽  
Simona Mancini ◽  
Michele Guida ◽  
Albina Cuomo ◽  
Domenico Guida
Keyword(s):  
Drinking Water ◽  
Effective Dose ◽  
Health Hazard ◽  
Age Groups ◽  
Internal Exposure ◽  
Threshold Values ◽  
Campania Region ◽  
Radon Activity ◽  
National Regulation ◽  
South Italy

Radon is a naturally occurring radioactive gas present in the hydrosphere, lithosphere and atmosphere abundantly. Its ionizing radiation provides the largest human internal exposure by inhalation and ingestion to natural sources, constituting a serious health hazard. The contribution to total exposure is mainly due to inhalation, as ingestion by food or drinking water is typically very small. However, because of public health concerns, the contributions from all these sources are limited by regulations and remedial action should be taken in the event that the defined threshold values are overcome. In this paper, the first campaign of measurements to control the radon activity concentration in drinking water from public water supplies in the province of Salerno, south Italy, is described. The results represent a main reference for the area, as it was never investigated before. The purpose of this survey was to contribute to data compilation concerning the presence of radon-222 in groundwater in the Campania region and to determine the associated risk for different age groups. The maximum radon activity concentrations and the related total annual public effective dose turned out to be lower than the threshold values (100 Bq/l and 0.1 mSv/y, respectively) indicated by international guidelines and the national regulation, showing that the health risks for public consumption can be considered negligible.

DETERMINATION OF THE TOTAL EFFECTIVE DOSE OF EXTERNAL AND INTERNAL EXPOSURE BY DIFFERENT IONIZING RADIATION SOURCES

2019 ◽  
Vol 187 (1) ◽  
pp. 129-137
Author(s):  
V A Kudryashev ◽  
D S Kim
Keyword(s):  
Ionizing Radiation ◽  
Effective Dose ◽  
Radiation Risk ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
The Body ◽  
Internal Exposure ◽  
Complex Method ◽  
Radiation Sources ◽  
Total Effective Dose

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.

Internal Dose for Ingestion of Molybdenum Radionuclides Based On A Revised Biokinetic Model

2000 ◽  
Vol 78 (1) ◽  
pp. 46-52 ◽  
Author(s):  
Augusto Giussani ◽  
Marie Claire Cantone ◽  
Daniela de Bartolo ◽  
Paul Roth ◽  
Eckhard Werner
Keyword(s):  
Internal Dose ◽  
Biokinetic Model

scholarly journals INFLUENCE OF THE CONSUMPTION OF DIFFERENT FOODSTUFFS ON THE INTERNAL EXPOSURE DOSE FORMATION IN THE ADULT POPULATION OF THE RUSSIAN FEDERATION AFTER THE ACCIDENT AT THE CHERNOBYL NPP

2018 ◽  
Vol 11 (2) ◽  
pp. 53-59 ◽  
Author(s):  
A. A. Bratilova ◽  
G. Ya. Bruk
Keyword(s):  
Russian Federation ◽  
Adult Population ◽  
Exposure Dose ◽  
Internal Exposure ◽  
Internal Dose ◽  
Chernobyl Npp ◽  
Region Data ◽  
The Russian Federation ◽  
The Impact

An The article is devoted to the peculiarities of the internal exposure dose formation in the adult population of the internal dose forming of the adult population of Russian Federation due to consumption of different foodstuffs in the remote period after the accident on at the Chernobyl NPP. Estimation of the impact of different foodstuffs is carried out in the forming of the mentioned doses; the foodstuffs mainly contributing in the internal dose forming formation are revealed. Based on the Bryansk region data, the comparing was fulfilled of the current food rations of population with the previous rations – of during the initial and intermediate postaccidental periods. It is illustrated how the differences in food rations affect the levels of exposure of the local inhabitants, which is necessary for the appropriate assessment of the internal exposure doses for population living in the contaminated territories.

scholarly journals Uncertainty quantification of bioassay functions for the internal dosimetry of radioiodine

2020 ◽  
Vol 61 (6) ◽  
pp. 860-870
Author(s):  
Tae-Eun Kwon ◽  
Yoonsun Chung ◽  
Jaeryong Yoo ◽  
Wi-Ho Ha ◽  
Minsu Cho
Keyword(s):  
Measurement Data ◽  
Dose Assessment ◽  
Internal Dosimetry ◽  
High Dose ◽  
Radiological Protection ◽  
Retention Function ◽  
Internal Dose ◽  
Actual Measurement ◽  
Monte Carlo Simulation Technique ◽  
Biokinetic Model

Abstract Bioassay functions, which are provided by the International Commission on Radiological Protection, are used to estimate the intake activity of radionuclides; however, they include considerable uncertainties in terms of the internal dosimetry for a particular individual. During a practical internal dose assessment, the uncertainty in the bioassay function is generally not introduced because of the difficulty in quantification. Therefore, to clarify the existence of uncertainty in the bioassay function and provide dosimetrists with an insight into this uncertainty, this study attempted to quantify the uncertainty in the thyroid retention function used for radioiodine exposure. The uncertainty was quantified using a probabilistic estimation of the thyroid retention function through the propagation of the distribution of biokinetic parameters by the Monte Carlo simulation technique. The uncertainties in the thyroid retention function, expressed in terms of the scattering factor, were in the ranges of 1.55–1.60 and 1.40–1.50 for within 24 h and after 24 h, respectively. In addition, the thyroid retention function within 24 h was compared with actual measurement data to confirm the uncertainty due to the use of first-order kinetics in the biokinetic model calculation. Significantly higher thyroid uptakes (by a factor of 1.9) were observed in the actual measurements. This study indicates that consideration of the uncertainty in the thyroid retention function can avoid a significant over- and under-estimation of the internal dose, particularly when a high dose is predicted.

scholarly journals Environmental radiation monitoring residential areas in the region of Ukrainian Polissya

2016 ◽  
pp. 145-152
Author(s):  
H. Chobot’ko
Keyword(s):  
Irradiation Dose ◽  
Forest Products ◽  
Radiation Monitoring ◽  
Internal Exposure ◽  
Internal Dose ◽  
Residential Areas ◽  
Environmental Radiation ◽  
137Cs Content ◽  
Definition Of

The paper presents a theoretical analysis and established regularities to identify critical ecosystems and factors that determine the irradiation dose of the population of the Ukrainian Polissya rural residential areas, radioactively contaminated by the Chernobyl accident. It was determined that the definition of critical ecosystems as an essential component of the radiation monitoring should include several basic stages of analysis of factors determining the dose for the region population: first of all, defining the role of forests and forest products in the formation of population doses; defining the contribution and the role of pastures and hayfields in the formation of the region population dose through contamination of milk and meat; defining the actual population diets, which largely determine the doses value; establishing the role of garden products in the formation of the region population doses; establishing the role of countermeasures in the formation of the region population doses. The establishment of these regularities is necessary to determine the critical ecosystems and the factors that determine the value of population doses of Ukrainian Polissia residential areas contaminated with radionuclides due to the CNPP accident. At the prospect it is necessary to plan the research that would consist of two parts : the radiation-hygienic (detection of features of diet and 137Cs internal exposure doses received by residents of Ukrainian Polissya abundant areas due to food consumption) and predictive (mathematical modeling of 137Cs content in forest food products, that significantly affect the population internal dose). The combination of these two parts will help to predict exposure of people as well as specific risks to their health.

scholarly journals 241Am on the territories adjacent to the Belarusian sector of the Chernobyl NPP resettlement zone: soil contamination, foodstuffs and population internal dose assessment

2019 ◽  
Vol 12 (2(св)) ◽  
pp. 75-82
Author(s):  
E. K. Nilova ◽  
V. N. Bortnovsky ◽  
S. A. Tagai ◽  
N. V. Dudareva ◽  
L. V. Zhukova
Keyword(s):  
Soil Contamination ◽  
Nuclear Power ◽  
Specific Activity ◽  
Selective Extraction ◽  
Food Samples ◽  
Dose Assessment ◽  
Internal Exposure ◽  
Internal Dose ◽  
137Cs Content ◽  
Radiochemical Method

241Am is the only radionuclide of Chernobyl radioactive fallout the content of which until 2058 continues to increase. The purpose of this work is to assess the 241Am internal exposure doses of residents of settlements on the territory adjacent to the resettlement lands of the Chernobyl nuclear power plant. To achieve this goal the current levels of 241Am and accompanying 137Cs content in the soil and foodstuffs were determined at the private settlements of the Bragin district of Gomel region of Belarus. 241Am (Eγ 59.6 keV) content in soil samples and 137Сs (Eγ 661 keV) content in soil/food samples were determined by gamma spectrometry. Determination of 241Am specific activity in food samples was performed by the radiochemical method using selective extraction-chromatographic resins. With an average level of 1.3 kBq/m2 , the maximum soil contamination density of 241Am can reach 3.6 kBq/m2 , and for 137Cs it is one or two orders of magnitude higher and ranges from 50 kBq/m2 to 350 kBq/m2 . The maximum specific activity of 241Am in products is determined in samples of leafy parsley – 33 mBq/kg, and in samples of potatoes, beets, onions per feather – not exceed 5 mBq/kg. The content of accompanying 137Cs in samples of plant products is in the range of 3-12 Bq/kg. In estimation of the internal dose of exposure by the food chain it is conservatively assumed that the population receives all the main components of the diet in their own farmstead. Calculation of the dose of internal exposure during inhalation is made under the assumption that the population performs work in the garden 4 hours a day for 7 months. The total expected dose of internal exposure from 241Am residents of settlements is dominated by the inhalation component, while the oral route is dominant in the formation of the total dose of internal exposure from concomitant 137Сs, which is 20 or more times higher than 241Am.

scholarly journals Radiation monitoring of drinking water in the vicinity of the Beloyarsk NPP

2021 ◽  
Vol 14 (1) ◽  
pp. 86-101
Author(s):  
A. V. Panov ◽  
A. V. Trapeznikov ◽  
A. V. Korzhavin ◽  
I. V. Geshel ◽  
S. V. Korovin ◽  
...  
Keyword(s):  
Drinking Water ◽  
Effective Dose ◽  
Water Consumption ◽  
Radiation Safety ◽  
Tap Water ◽  
Natural Radionuclides ◽  
Control Level ◽  
Internal Exposure ◽  
Water Wells ◽  
Average Effective Dose

The article provides a radiation-hygienic assessment of the current state of drinking water supply sources for the population in the observation area of the the Beloyarsk NPP and the Institute of Nuclear Materials. We determined the content of natural (234U, 238U, 226Ra, 228Ra, 210Po, 222Rn, 210Pb, 228Th, 230Th, 232Th) and technogenic (3H, 14C, 60Co, 90Sr, 134Cs, 137Cs, 238Pu, 239,240Pu, 241Am) radionuclides in drinking water of tap water, water boreholes and water wells in test settlements located at different distances and directions from radiation hazardous facilities. Results of monitoring of water sources in 2012–2013 and 2019 showed the radiation safety of drinking water in the vicinity of the Beloyarsk NPP according to several criteria. Thus, the maximum levels of the gross specific alpha-activity of radionuclides in water samples were 3.9 times lower than the control level (0.2 Bq/kg), the gross specific beta-activity was 5.7 times lower than the control level (1 Bq/ kg). Over the entire observation period, none of the drinking water samples exceeded the control levels both for individual radionuclides and for the sum of the ratios of specific activities to control levels. The content of natural and artificial radionuclides in drinking water near the Beloyarsk NPP decreases in the following order: water wells > water boreholes > tap water. For the past 20 years, there was a decrease in tritium specific activity in drinking water of the Beloyarsk NPP region by 20–35%, depending on the source of water supply. It was noted that the launch of the BN-800 reactor also did not lead to an increase in the content of other artificial radionuclides (90Sr, 137Cs) in groundwater. The average annual effective dose of internal exposure of the population due to drinking water consumption in the vicinity of the Beloyarsk NPP is 0.05 mSv, according to conservative estimates – 0.07 mSv, which is below the radiation safety threshold (0.1 mSv/a) recommended by the WHO. Natural radionuclides play the primary role in the formation of the annual average effective dose for internal irradiation (98.9%) due to drinking water consumption on the considered territories. 210Po makes the largest contribution to the dose from natural radioisotopes – 43%, somewhat less is made by 210Pb – 25%. The third place in the dose formation from natural radionuclides belongs to 234U (8%), 228Ra (7%), 226Ra (6%) and 230Th (6%). The contribution of other natural radioisotopes in the formation of the internal radiation dose from drinking water consumption does not exceed 2-3%. The contribution of technogenic radionuclides to the annual average effective dose from the consumption of drinking water is negligible (about 1%). Of the technogenic components, 90Sr (60%), 3H (20%), and 241Am (12%) play the most significant role in the formation of the internal exposure dose.

Modeling study of the atmospheric transport of radioactivity after wildland fires and a dust storm in the Chernobyl Exclusion Zone in April 2020

2021 ◽  
Author(s):  
Mykola Talerko ◽  
Tatiana Lev ◽  
Ivan Kovalets ◽  
Mark Zheleznyak ◽  
Yasunori Igarashi ◽  
...  
Keyword(s):  
Effective Dose ◽  
Forest Fires ◽  
Dust Storm ◽  
Emission Factor ◽  
Atmospheric Transport ◽  
Internal Exposure ◽  
Radioactive Aerosol ◽  
Wildland Fires ◽  
Exclusion Zone ◽  
Chernobyl Npp

<p>In April 2020, the largest forest fire occurred in the Chernobyl Exclusion Zone (ChEZ) in its history. The results of modeling the atmospheric transport of radioactive aerosols released into the atmosphere as a result of wildland fires in the ChEZ and around it are presented. The atmospheric transport model LEDI, developed at the Institute for Safety Problems of NPPs, and the Atmospheric Dispersion Module of the real -time online decision support system for offsite nuclear emergency RODOS, which development was funded by the EU, were used. The <sup>137</sup>Cs activity concentration in the surface air is calculated on a regional scale (in Ukraine) and a local scale (within the ChEZ). The <sup>137</sup>Cs activity in the surface air of Kyiv (115 km from the ChEZ borders) is found to have reached 2–4 mBq m<sup>−3</sup> during the period April 3–20. The modeling results are generally consistent with measured data pertaining to radioactive contamination in Kyiv, within the ChEZ, and areas around four operating nuclear power plants in Ukraine.</p><p>A method for estimating the radionuclide activity emissions during wildland fires in radioactively contaminated areas is proposed. This method is based on satellite data of the fire radiative power (FRP), the radionuclide inventory in the fire area, and an emission factor for radioactive particles. A method was applied for forest fires in the ChEZ in April 2020. Preliminary estimations of an emission factor are made using FRP values obtained from NASA's MODIS and VIIRS active fire products.</p><p>On April 16, 2020, a strong dust storm was observed in the ChEZ, which coincided with the period of intense wildland fires. The additional <sup>137</sup>Cs activity raised by the dust storm from burned areas in the meadow biocenoses was estimated to be about 162 GBq, i.e. up to 20% of the total activity emitted into the air during the entire period of forest fires on April 3-20, 2020. According to the modeling results, during April 16-17, the input of resuspension of radioactive particles due to a dust storm was up to 80-95% of the total <sup>137</sup>Cs activity in the surface air near the Chernobyl NPP. In Kyiv, this value decreased to only about 4%.</p><p>The total effective dose to the population of Kyiv during the fire period is estimated to be 5.7 nSv from external exposure and the inhalation of <sup>137</sup>Cs and <sup>90</sup>Sr, rising to 30 nSv by the end of 2020. This is about 0.003% of the annual permissible level of exposure of the population. A committed effective dose up to 200-500 nSv is estimated for the personnel of the Chernobyl NPP from the radioactive aerosol inhalation during the 2020 forest fires, which is not more than 0.05% of the established control levels of internal exposure for them.</p>

Sign in / Sign up

Export Citation Format

Share Document