Assessment Of Effective Dose Research Articles

Assessment of committed effective dose from ingestion of 137Cs in seafood from coastal areas of Zhejiang province

Objective To investigate the contents of radionuclide 137Cs in seafood from coastal areas of Zhejiang province, and to estimate the annual committed effective dose to population in different regions from ingestion of 137Cs in seafood. Methods Three representative monitoring areas were set on the coastaline of Zhejiang province, and the locally popular seafoods were selected as monitoring objectives. The contents of radionuclide 137Cs were detected using HPGe γ spectrometry. The committed effective doses were estimated based on monitoring results and consumption data on seafoods in Zhejiang. Results The detection ratio of 137Cs in seafood produced on coastal areas of Zhejiang province was estimated to be 35.3% (36/102). Specific activity detected ranged from 0.004 to 0.140 Bq/(kg, Wet). Committed effective doses from ingestion of 137Cs in one year to the population in island region, coastal region and inland region were 3.03×10-5, 1.63×10-5, 3.38×10-6 mSv, respectively, far lower than the world committed effective dose resulting from internal exposure. Conclusions At present, the content level of 137Cs in seafood produced on the coastal areas of Zhejiang province is much lower than the national standard limit, and the dose burden to the population is very minor with no health impact to the population. Key words: Gamma spectrometer; Sea products; 137Cs; Annual committed effective dose

Assessment of annual effective dose from radium isotopes in groundwater samples in households along the lower Mekong River

In this study, the 224Ra, 226Ra, 228Ra in groundwater samples at Long Phu district were determined by HPGe detector with co-precipitation method. The median concentrations were 0.040 ± 0.005 Bq L−1, 0.039 ± 0.004 Bq L−1, and 0.049 ± 0.004 Bq L−1. Highest MDC values were 0.028 Bq L−1, 0.010 Bq L−1, 0.018 Bq L−1, respectively. It’s a strong relationship between 224Ra, 228Ra versus conductivity, salinity, TDS, SO42−. The annual effective dose of the age groups was lower than the WHO recommended value except for infants exceeding around 1.5 times. Besides, the 226Ra minimum recovery obtained was 90% with trueness 9.9% and relative percentage difference 6.1%.

Radiation effective dose assessment of [51Mn]- and [52Mn]-chloride

In order to establish the potential of [51/52Mn]Cl2 as safe PET brain tracers, the radiation effective dose (ED) of [51Mn]- and [52Mn]-chloride has been assessed by using biokinetic models in anthropomorphic phantoms. Results showed that [52Mn]-chloride releases one hundred thirty times more radiation dose (ED = 1.35 mSv/MBq) than [51Mn]-chloride (ED = 1.02E-02 mSv/MBq). Although the maximum positron energy of 52Mn allows a PET image resolution similar to that of 18F, activities below 15 MBq should be administered.

Assessment of radiological hazards and effective dose from natural radioactivity in rock samples of Hassan district, Karnataka, India

The natural primordial radionuclide activity concentrations in different types of rock samples in and around Hassan district were measured using gamma spectrometry-based high-purity Germanium detector. The average activity concentration of 226Ra, 232Th, and 40K radionuclides in rock samples varies from 29.4 ± 1.2 to 83.7 ± 1.7, 37.9 ± 1.2 to 198.4 ± 2.2, and 346.1 ± 9.0 to 1024.4 ± 19.4 Bq kg−1 with an average value of 50.9 ± 1.4, 79.6 ± 1.5, and 609.2 ± 12.8 Bq kg−1, respectively. The radiological hazard indices such as radium equivalent activity, gamma index, alpha index, external and internal health hazard indices, absorbed dose rate and annual effective doses were estimated. The average value of radium equivalent activity is less than the criterion limit of 370 Bq kg−1. The average indoor and outdoor annual effective dose values for rock samples are lower than the world average recommended value of 1 mSv y−1. The study concludes that except granite rocks, all the rock samples analyzed are safe when used as construction materials and do not pose any significant radiation hazards.

Annual effective dose and excess life time cancer risk assessment from tobacco plants

Cigarette smoking is one of the pathways that might cause radiation exposure due to the presence of radioactive elements in tobacco leaves used in the manufacture of cigarettes. From the health point of view, the knowledge of radioactivity content of the various radionuclides in tobacco leaves and their derivative products is important to assess the radiological effects associated with tobacco smoking for smokers. In this work, naturally occurring radionuclides 226Ra, 232Th and 40K and man-made 137Cs were measured in tobacco using gamma-ray spectrometry. Results show that the average concentrations of 226Ra, 232Th and 40K vary from 4.30±0.2 to 11.85±0.7 (average 8.17), 1.35±0.1 to 16.12±0.9 (average 6.08), and 565.6±15.5 to 1235.81±35 (average 908.09)Bqkg−1, respectively. 137Cs activity concentrations were ranged from 0.15±0.01 to 0.67±0.9 (average 0.44)Bqkg−1. The most important radiological parameters, including radium equivalent (Raeq), total annual effective dose (AED) and excess lifetime cancer risk (ELCR) were calculated. For smokers, the total AED resulting from activity concentrations of 226Ra, 232Th and 40K in tobacco samples ranged from 0.44 to 2.29 (average 1.39)mSvy−1, while of 137Cs varied from 0.01 to 0.04 (average 0.025)μSvy−1 and so very little is contributing to the total dose due to inhalation to smokers. ELCR was higher than the world's average of 1.45×10−3 for tobacco and coal samples. The excess lifetime cancer risk ranged from 1.55×10−3 to 8.01×10−3 with an average value of 4.88×10−3 for all tobacco samples under investigation.

Assessment of radiation effective dose from lung cancer screening pilot project in Institut Kanser Negara: A preliminary finding

The aim of this study is to evaluate effective dose received by participants from Lung Cancer Screening program in Institut Kanser Negara (IKN), Putrajaya. This retrospective study was performed between April 2016 - December 2016 where all scanning acquisition protocols and dose information from forty (40) participants were recorded and investigated. The screening process involves two types of imaging technique, the Dual Energy Subtraction (DES) Chest Xray and Low-Dose Computed Tomography (LDCT) imaging technique. Participant’s effective dose (ED) from DES and MSCT were analysed by using PCXMC (Version 2.0, Finland) and CT-EXPO (Version 2.3, Germany) software, respectively. It was observed that the mean ( ± SD) value for DES (at 60 kV), DES (at 120 kV) and MSCT examinations were 0.006 ± 0.005 mSv, 0.018 ± 0.005 mSv and 1.558 ± 0.129 mSv, respectively. In a whole, the total cumulative ED values for participants were ranged from 1.376 mSv to 1.986 mSv. It was summarized that both optimized techniques were useful for screening needs and the ED value from this study were lower when compared to other established reference.

Isotopes of 210Po and 210Pb in Hazel bolete (Leccinellum pseudoscabrum) \u2013 bioconcentration, distribution and related dose assessment

The hazel bolete Leccinellum pseudoscabrum (Kallenb.) Mikšík 2017 specimens and beneath soil layer (0–10 cm) have been examined on the occasion of 210Po and 210Pb activity concentrations, the nuclide bioaccumulation potential by species and distribution in fruit bodies. Mushrooms and forest soils came from six geographically distant locations in the northern and central parts of Poland. The threat to humans from 210Po and 210Pb contained in mushrooms has been also assessed. The absolute values of the 210Po radioactivity, respectively, in caps and stems of fruit bodies were in the range 0.74 ± 0.06–8.59 ± 0.36 Bq kg−1 dry biomass and from 0.81 ± 0.06–8.23 ± 0.37 Bq kg−1 dry biomass, while the values of the 210Pb radioactivity in caps and stems were in the range 0.61 ± 0.04–6.33 ± 0.22 Bq kg−1 dry biomass and 0.83 ± 0.04–4.59 ± 0.24 Bq kg−1 dry biomass, respectively. A potential related effective dose assessment showed that mushrooms L. pseudoscabrum can contribute at 0.89–10.3 μSv kg−1 db from 210Po decay and 0.42–4.37 μSv kg−1 db from 210Pb decay.

A modelling approach to assess the environmental/radiological impact of C-14 release from radioactive waste repositories

Assessments of the environmental impact of C-14 disposal often assume that C-14 is converted into gases that are able to migrate to the surface, where they pose a radiological risk. However, uncertainties, associated with the long-term release of C-14 from graphite and the evolution in the post-closure environment of a geological disposal facility (GDF), exist. In this paper, an integrated modelling framework has been developed to investigate these uncertainties. The modelling framework consists of a biogeochemical near field model which interfaces with a geosphere/biosphere model and it is verified by comparing the results to those obtained from other models. A sensitivity analysis discloses that a faster mid chain scission rate of stopped cellulose about four orders of magnitude assesses a twice higher effective dose. In another scenario, which is related to the control of microbial activity by pH and the availability of carbon dioxide to microbes, the effective dose is two orders of magnitude higher compared with a reference scenario. This modelling work illustrates also the importance of far field parameters, such as the rock permeability and the release area of gas pathway, to the assessment of effective dose.

On uranium 234U and 238U radionuclides in calcium and magnesium supplements and the potential effective radiation dose assessment to the consumers

ABSTRACTIn this survey the concentrations of the radioactive nuclides uranium 234U and 238U were determined in the most popular calcium and magnesium supplements for adults in Poland. It was also investigated whether the supplements contain uranium isotopes and could be a potential source in the human diet and have an influence on the value of effective radiation doses to the consumers. The analyzed calcium and magnesium pharmaceuticals contained organic or inorganic compounds, several of natural origin as mussel’s shells, fish extracts, or sedimentary rocks. As results showed, 234U and 238U concentrations in natural origin calcium and magnesium supplements were significantly higher than in other, synthetic ones. The highest 234U and 238U activity concentrations were determined in tablets from mussel’s shells. The radiochemical hazard was assessed and the highest annual radiation dose was found in 234U and 238U present in supplements produced from shells or dolomite rock.

RADIATION SITUATION AT THE SITE OF THE FORMER LERMONTOV ALMAZ PRODUCTION ASSOCIATION

In the article there are presented data of the study of the radiation situation on the territory and at premises of the “Electric Mechanical Plant” Company, one of the units of the former uranium mining and milling facility of the former Lermontov Almaz Production Association. At the area of waste rock dumps and off-balance ores, the radiation situation was shown to meet requirements of health regulations SP LKP-91.The radiation situation in 14 out of 15 observed workshops and office premises meets the requirements for the limitation of the public exposure to natural radiation sources in occupational conditions established by health regulations and norms SanPiN 2.6.1.2800-10. In one building (warehouse premises), the requirements for equivalent equilibrium volumetric activity of radon (EEVA) in indoor air are exceeded. Based on the annual EEVA of radon values the assessment of effective doses in the work of the personnel over the one shift, was shown to be overestimated up to 7 times due to the daily variation of radon volumetric activity concentration.

The upgraded GLE database includes assessment of radiation exposure at flight altitudes

The exposure to radiation due to cosmic rays at cruising aviation altitudes is an important topic in the field of space weather. While the effect of galactic cosmic rays can be easily assessed on the basis of recent models, assessments of the absorbed dose during strong solar particle events is rather complicated. A specific interest are events with energy about GeV/nucleon, which produce an atmospheric cascade registered by ground based detectors e.g. neutron monitors. Those events are known as ground level enhancements (GLEs) and can significantly enhance the radiation exposure at flight altitudes over the polar regions. A recent upgrade of the existing GLE database provides information on the estimated solar protons energy/rigidity spectra, the corresponding computed effective doses and the used bibliography. Using information retrieved from this upgrade we performed statistical analysis of maximum effective doses at commercial flight altitude of 35 kft during several GLEs, where the necessary information as energy/rigidity spectra of the solar protons is available. For the computations a recent model for assessment of effective dose due to cosmic ray particles was employed. A highly significant correlation between the maximum effective dose rate and neutron monitor peak count rate increase during GLEs is observed. Here, we propose to use the maximal count rate increase as a proxy for assessment of the effective dose at flight altitude during strong solar particle events.

Assessment of Equivalent Radium Activity and Annual Effective Dose Due to Building Materials in Côte D’Ivoire by Gamma Spectrometry: Cases of Cement

Radioactivity is a natural phenomenon present in the universe. So, because of human life solidarity with a habitat, we are permanently in contact, especially through building materials. The objective of this work is the determination of the used cement radioactivity level in the buildings in Cote d'Ivoire. Thus, samples of grey and white cement currently used on Ivorian territory were taken. In order to determine the radioactivity level of this cement, samples were analyzed by using gamma spectrometry chain which contains a NaI (Tl) scintillation detector designed by the German manufacturer LD-DIDACTIC, coupled to a multichannel analyzer (AMC) using a Cassy Lab software. Thus, the specific activity of the primordial radionuclides 226Ra, 232Th and 40K, was able to be determined. The average values obtained are 29.66 Bq/kg, 34.88 Bq/kg and 178.424 Bq/kg respectively for 226Ra, 232Th and 40K. All average values are below the limit values recommended by UNSCEAR. However, we evaluated the radiological parameters such as the equivalent radium activity and the annual effective dose in order to translate the specific activity in terms of harmfulness. Values obtained for these parameters are below those recommended by ICRP and UNSCEAR. These results show that the risk incurred by the use of these different brands of cement is low.

Использование объемной имитационной модели как способ оценки эффективной дозы назальных спреев оксиметазолина

Использование объемной имитационной модели как способ оценки эффективной дозы назальных спреев оксиметазолина

Assessment of Natural Radioactivity Level and Annual Effective Dose of Amber Rice Samples Cultivated in the South of Iraq

In this work, the activity concentrations of naturally occurring radioactive material including 238U, 232Th, and 40K were measured of some amber rice samples cultivated in southern Baghdad and Al Najaf governorate and used in Baghdad governorate, Iraq in 2018, using gamma-ray spectrometer with NaI (Tl) detector. The results show that the activity concentrations for 238U ranged from (2.68 to 10.81) Bq/kg with average 5.94 Bq/kg, 232Th ranged from (B.D.L to 3.37) Bq/kg with average 2.65 Bq/kg, and for 40K ranged from (4.48 to 35.7) Bq/kg with average 16.84 Bq/kg. The annual effective dose from rice consumption by adults for 238U, 232Th, and 40K ranged from (0.41 to 1.6) x10-5 Sv/y with average 0.9 x10-5 Sv/y, (B.D.L to 0.42) x10-5 Sv/y with average 0.2 x10-5 Sv/y, and (0.17 to 1.2) x10-5 Sv/y with average 0.45 x10-5 Sv/y respectively. All values of the average specific activities are less than the global average values of ICRP, and the annual effective dose from rice consumption by adults was lower than the permissible limit of (1 m Sv/y) recommended by the International Commission on Radiological Protection.

Effective dose assessment in body organs after injection of 131I-MIBG

Introduction: Development of a novel radiopharmaceutical needs assessment of its biological- distribution in animal models, most commonly mice prior to its common application. This study describes the biodistribution and absorbed dose prediction 131I-MIBG in human organs after injection in mice. Materials and Methods: In this research, 131I-MIBG radiopharmaceutical was injected to mice. After 4, 12, 24, and 48 hours post injection, the mice sacrificed and its organs dissected and counted by well detector. Then with having the Injected dose per gram of organs, absorbed dose of organs was calculated by MCNP simulation code and MIRD methods. Results: The results showed that the intestine and thyroid organs absorbed the least and most dose after injection of 131I-MIBG in mice. Conclusion: Many studies have demonstrated the usefulness of using animal distribution as a model for absorbed dose estimations in humans. Radiation dosimetry for 131I-MIBG was estimated for humans based on the biodistribution data in normal mice. The obtained results by MIRD and MCNP had shown close results.

319. Effective Dose Assessment on an Hybrid Equipment: Results and challenges to integrate with MDCT

Purpose The aim of this study was to measure, monitor and report effective dose in nuclear medicine and to assess current challenges in integrating these measures with CT. Methods In 2014 we connected a CT-PET to a dose tracking software and started to collect dose data from CT modality; in late 2015 the software was upgraded to a version which includes a nuclear medicine module for dose tracking. Data from the PET part of the scanner, in terms of administered activity and effective dose, were also collected. Results Data from 12000 CT doses and 3700 PET doses were collected, mostly from: Whole Body (WB) 18F-FDG (63.2%), WB 11C-Choline (12.8%), WB 68Ga-DOTATOC (5.5%), Head 11C-Methionine for a total of 18.4% of the whole activity of the scanner. CT mean DLP (mGy∗cm) data values were (range between brackets): WB 18F-FDG 1486.3 (76.1-7700.9), WB 11C-Choline 2451.9 (290.9-5023.1), WB 68Ga-DOTATOC 1183.8 (41.0-3728.4) and Head 11C-Methionine 766.7 (52.3-2326.9). Mean effective doses (mSv) were: WB 18F-FDG 15.3 ± 4.7, WB 11C-Choline 26.5 ± 5.6, WB 68Ga 13.4 ± 3.7 and Head 11C-Methionine 1.2 ± 0.7. Mean administered activities (MBq) and effective doses (mSv) for radiopharmaceuticals used in PET were: WB 18F-FDG 335.9-6.4, Head 11C-Methionine 294.6-2.5, WB 68Ga-DOTATOC 168.3-3.5 and WB 11C-Choline 322.2–1.5. The mean total effective doses (mSv) due to both modality were: WB 18F-FDG 21.7 ± 4.9, Head 11C-Methionine 3.7 ± 0.8, WB 11 C-Choline 27.9 ± 5.6 and WB 68Ga-DOTATOC 16.9 ± 2.8. Conclusions The implementation of a dose tracking system to nuclear medicine is of great value for accurate and regular recording, reporting and analysis of patient’s effective doses. It can help to improve the evaluation of radiation exposures in the clinical practice.

OA202] Recent update of typical effective doses received by patients at diagnostic and interventional radiology procedures and its impact on assessment of collective effective dose to population in bulgaria

Purpose Performance of regular national patient dose surveys is required by European and International Basic Safety Standards and by National law. Third national patient dose survey (TNS) was conducted in 2016–2017 with aim of updating information on radiation exposure to patients at different diagnostic and interventional radiology (DIR) procedures. The purpose of this work is to assess and update typical effective doses received by patients at various diagnostic and interventional radiology procedures (DIR) and to find its impact on assessment of collective effective dose to population. Methods Values of typical patient doses (TPD) are based on data obtained during TNS. Typical effective dose (TED) for each procedure was calculated using conversion coefficients (CC) from TPD to effective dose (E) with dimensions: (mSv. Gy - 1 . cm - 2 ) for radiography, fluoroscopy and interventional procedures; and (mSv. mGy - 1 . cm - 1 ) for Computed tomography procedures respectively. Values of CCs are based on UNSCEAR recommendations, as for Chest radiography an own CC assessment is made based on kerma area product values and respective E values calculated using PCXMC software. Total collective effective dose to Bulgarian population ( S E ) and the effective dose per capita were calculated based on the number of the most frequent DIR procedures and the TED per procedure. Results TED are updated for 16 of most common DIR procedures of which: 5 are radiography; 4 – fluoroscopy; 4 – computed tomography; 2 – interventional cardiology and one is for mammography respectively. For year 2016 SE is assessed to 5868 man.Sv which relates to mean effective dose of 0.82 mSv per capita. It is 16.8% higher than its relevant assessment based on older information for not updated typical patient doses obtained during previous national survey performed in 2007. An increase of 84% in S E is observed for the period of 2007 to 2016 year, as dynamics of collective effective doses is analysed and discussed. Conclusions Updated assessments of TEDs and SE due to DIR procedures are elaborated. Regular patient dose surveys are important for update of National Diagnostic Reference Levels (NDRLs) as well as for obtaining more realistic and precise assessment of collective effective dose to population due to diagnostic radiology procedures.

P080] Assessment of effective dose in hybrid imaging

Purpose The aim of this study is to assess the typical doses associated with PET/CT examination in a large population and to evaluate the difference of effective dose estimation in fixed vs patient-adapted activity utilizing the same imaging protocols. Doses differences in the urinary bladder are also estimated for PET examination. Methods and materials DoseWatch™ tracking system was utilized to collect patient information and to measure effective dose (for WB 18 F-FDG PET/CT) and organ dose data (for PET only) associated with a fixed activity by retrospectively analyzing existing data. For CT examination DLP values and effective dose data was collected; for PET examination DoseWatch™ provides the administered activity, the effective and the organ doses, based on ICRP 106. Effective and organ dose (for PET only) in a PET/CT examination where the administered activity is adapted to the patient’s weight will be estimated from the same database using a theoretical calculation. The dose in the urinary bladder is also assessed on theoretical calculations. Results Dose data from 6900 CT and 1700 WB 18F-FDG PET were collected. CT mean DLP (mGy*cm) data values were: 1481.3 (76.1–7700.9) and mean effective doses (mSv): 15.2 ± 4.9. Mean administered activities (MBq) and effective doses (mSv) for 18F-FDG PET are: 333.9–6.4. The mean total effective doses (mSv) due to both modality are: 21.5 ± 5.2. equivalent doses (mSv) to urinary bladder are: 43.7 ± 5.8. Conclusions The implementation of a dose tracking system in nuclear medicine is of great value for accurate and regular recording, reporting and analysis of patient’s effective doses.

Estimation of effective radiation dose for households living in rare earth mines in Nam Xe, Lai Chau province

According to the United Nations Scientific Council on the Effects of Atomic Radiation (UNSCEAR), the global average dose level for the community is 2.4mSv/year. People living in the areas with high levels of radiation will cause adverse effects on their health. There are two main components that cause the dose of radiation, mainly due to the inhalation of radon and the extra dose of gamma radiation. The paper presents the results of assessment of natural effective radiation doses on the basis of the projected outpatient dosimetry in 70 households living in Mau and Mo village of Nam Xe, Phong Tho distrist, Lai Chau province.

Upgrade of GLE database: Assessment of effective dose rate at flight altitude

A new database for assessment of radiation doses at cruise flight altitude in the Earth atmosphere, related to ground level enhancement (GLE) events is created under VarSiTi/SCOSTEP support and incorporated to the International ground level enhancement (GLE) database (gle.oulu.fi). The upgraded database provides, for each GLE event, where possible, information on the estimated energy/rigidity spectra of solar energetic particles and the corresponding computed effective doses at cruise flight altitude of 35 kft (10,668 m above sea level). The computations are performed for various reconstructions of solar energetic particles spectra, available in literature, thus for some events there are several results. Computations were performed using a recent model for assessment of effective dose due to cosmic ray particles, applied specifically in the polar region, where the exposure is maximal. This upgrade allows one to estimate the radiation effects at cruise flight altitude caused by major GLE events over several decades.