scholarly journals Annual effective dose and air absorbed dose based on airborne and ground gamma-ray spectrometry - Serra do Carambeí and Joaquim Murtinho granites, southern Brazil

2019 ◽  
Author(s):  
Antonelli F. ◽  
F. Ferreira
Keyword(s):  
Effective Dose ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Absorbed Dose ◽  
Gamma Ray Spectrometry ◽  
Southern Brazil

scholarly journals Naturally Occurring Radioactive Materials in Bracelets and Necklaces: Radiological Risk Evaluation

2021 ◽  
Vol 18 (21) ◽  
pp. 11170
Author(s):  
Halmat Jalal Hassan ◽  
Suhairul Hashim ◽  
Noor Zati Hani Abu Hanifah ◽  
Sib Krishna Ghoshal ◽  
Mohamad Syazwan Mohd Sanusi ◽  
...  
Keyword(s):  
Effective Dose ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Threshold Model ◽  
Negative Ions ◽  
Radioactive Material ◽  
Gamma Ray Spectrometry ◽  
Radiological Risk ◽  
Naturally Occurring ◽  
Dose Conversion Coefficient

A particular category of jewelry is one involving bracelets and necklaces that are deliberately made to contain naturally occurring radioactive material (NORM)—purveyors making unsubstantiated claims for health benefits from the release of negative ions. Conversely, within the bounds of the linear no-threshold model, long-term use presents a radiological risk to wearers. Evaluation is conducted herein of the radiological risk arising from wearing these products and gamma-ray spectrometry is used to determine the radioactivity levels and annual effective dose of 15 commercially available bracelets (samples B1 to B15) and five necklaces (samples N16 to N20). Various use scenarios are considered; a Geant4 Monte Carlo (Geant4 MC) simulation is also performed to validate the experimental results. The dose conversion coefficient for external radiation and skin equivalent doses were also evaluated. Among the necklaces, sample N16 showed the greatest levels of radioactivity, at 246 ± 35, 1682 ± 118, and 221 ± 40 Bq, for 238U, 232Th, and 40K, respectively. For the bracelets, for 238U and 232Th, sample B15 displayed the greatest level of radioactivity, at 146 ± 21 and 980 ± 71 Bq, respectively. N16 offered the greatest percentage concentrations of U and Th, with means of 0.073 ± 0.0002% and 1.51 ± 0.0015%, respectively, giving rise to an estimated annual effective dose exposure of 1.22 mSv, substantially in excess of the ICRP recommended limit of 1 mSv/year.

scholarly journals Measurement of Natural Radioactivity Level in Selected Phosphate Fertilizer Samples Collected from Iraqi Markets

2021 ◽  
Vol 24 (3) ◽  
pp. 43-49
Author(s):  
Yassamin S.Khalf ◽  
◽  
Kareem K. Mohammad ◽  
Keyword(s):  
Effective Dose ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Hazard Index ◽  
Phosphate Fertilizer ◽  
Gamma Ray Spectrometry ◽  
External Hazard Index ◽  
Activity Concentrations ◽  
Starting Point ◽  
Gamma Index

The Gamma-ray spectrometry (spectra line Gp) and a high-purity germanium (HPGe) detector were used to determine the activity concentrations of 226Ra, 232Th, and 40K in fertilizer samples. 226Ra, 232Th, and 40K activity concentrations in fertilizers and phosphate raw. In this study the gamma index(I), Radium equivalent dose(Raeq),dose rate(DR),external hazard index(Hex) internal hazard index(Hin), annual effective dose outdoor(AEDout) and annual effective dose indoor(AEDin)were found. This study could serve as a starting point for figuring out how fertilizer radiation affects human health.

scholarly journals Population doses from terrestrial gamma exposure in Serbia

2007 ◽  
Vol 15 (3-4) ◽  
pp. 78-80 ◽  
Author(s):  
Snezana Dragovic ◽  
Ljiljana Jankovic-Mandic ◽  
Milan Momcilovic ◽  
Antonije Onjia
Keyword(s):  
Effective Dose ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Hazard Index ◽  
External Source ◽  
Gamma Dose ◽  
Radiation Hazard ◽  
Gamma Ray Spectrometry ◽  
Naturally Occurring ◽  
Naturally Occurring Radionuclides

Background: Terrestrial radiation emitted from naturally occurring radionuclides, such as 40K and radionuclides from the 238U and 232Th series and their decay products represent the main external source of irradiation to the human body. The purpose of this study was to provide a preliminary assessment of the doses from terrestrial exposure of population in Serbia and to estimate a potential radiation hazard for population inhabiting investigated areas. Methods: The gamma dose rates, external hazard indexes, and annual effective doses due to terrestrial naturally occurring radionuclides (238U, 232Th and 40K) were calculated based on their activities in soil samples in Serbia as determined by gamma-ray spectrometry. Results: The total absorbed gamma dose rate due to these radionuclides varied from 16.9 to 125 nGy h-1, with a mean of 62.8 nGy h-1. Assuming a 20% occupancy factor, the corresponding annual effective dose varied from 2.07 to 15.4?10-5 Sv with the mean value of 7.7?10-5 Sv, i.e. annual effective dose was in range of the world wide average values. Conclusion: According to the values of external hazard index obtained in this study (mean Hex = 0.35), the radiation hazard was insignificant for the population living in investigated areas.

Study of the natural radioactivity of selected samples of the soil of Al-Nada district in Najaf

2018 ◽  
Vol 31 (3) ◽  
pp. 43
Author(s):  
Heiyam Najy Hady ◽  
Shahad Fadel Kadim
Keyword(s):  
Effective Dose ◽  
Gamma Ray ◽  
Background Radiation ◽  
Annual Effective Dose ◽  
Natural Radionuclides ◽  
Hazard Index ◽  
Absorbed Dose ◽  
Gamma Ray Spectrometer ◽  
External Hazard Index ◽  
Reporting Data

   This study reported activity concentration of 238 U, 232 Th, 40 K in 50 soil samples AL-Nada district - Najaf Governorate - Iraq Measurement using gamma ray spectrometer NaI (TI) (3x3). The activity concentrations of natural radionuclides are found to range from (31.319  Bq.Kg-1 to (1.1583 ± 0.0821) Bq.Kg-1with average (11.851 0.281) Bq.Kg-1 of uranium 238U.  From (1.117±0.048)  Bq.Kg-1 to  (23.948 ) Bq.Kg-1  with an  average of  (6.283 0.148 ( Bq.Kg-1 for thorium 232Th,.from(13.592±0.282) Bq.Kg-1 to (705.834 6.179) Bq.Kg-1 and average (265.494 1.445) Bq.Kg-1 potassium40K , equivalent radium  from (12.489 0.328) Bq.Kg-1 to (84.199 1.911) Bq.Kg-1 and average (40.078 0.564) Bq.Kg-1 , internal  hazard index from (0.039) Bq.Kg-1to( 0.256) Bq.Kg-1 and average( 0.139) Bq.Kg-1,external hazard index ranged from( 0.033) Bq.Kg-1 to (0.227) Bq.Kg-1 and average( 0.108) Bq.Kg-1 values  either of absorbed dose in air from (5.728 0.150) nGy/h to (42.667 0.901) nGy/h and average(19.914 0.264) nGy/h  , internal annual effective dose from (0.028 0.0005) mSv/y to (0.209 0.0044) mSv/y and average (0.097 0.0013) mSv/y, external annual effective dose from (0.0070 0.0001) mSv/y to (0.0523 0.001) mSv/y  and average (0.0244 0.0003) mSv/y The results were found to be comparable or lower than similar global reporting data. According to this, research soil The area can be considered to have a normal level of natural background radiation  

Soil mineral analysis and environmental radioactivity in Ghizer, Eastern Hindukush, Pakistan

2021 ◽  
Vol 0 (0) ◽  
Author(s):  
Mohammad Wasim ◽  
Sardar Ali Shah ◽  
Arfan Tariq ◽  
Manzoor Ali
Keyword(s):  
Effective Dose ◽  
Dose Rate ◽  
Annual Effective Dose ◽  
Hazard Index ◽  
Absorbed Dose ◽  
Gamma Ray Spectrometry ◽  
Absorbed Dose Rate ◽  
Radium Equivalent Activity ◽  
Effective Dose Rate ◽  
Annual Effective Dose Rate

Abstract Distribution of natural and anthropogenic radionuclides (226Ra, 232Th, 137Cs and 40K) was determined in 32 samples from Ghizer, an Eastern Hindukush district at an altitude of 2286 m in Pakistan using high resolution gamma-ray spectrometry. Mineralogical analysis by X-ray diffractometry identified quartz, calcite, albite and anorthite as major phases whereas actinolite, chlorite serpentine and kaolinite as minor phases. The activity concentrations for 226Ra, 232Th, 137Cs and 40K varied from 25.2 ± 1.7 to 145.3 ± 10.1 Bq kg−1, 24.9 ± 1.1 to 197 ± 9 Bq kg−1, 2.03 ± 0.21 to 16.7 ± 1.1 and 252 ± 6 to 1433 ± 35 Bq kg−1, respectively. The samples yielded average radium equivalent activity as 178.4 ± 23.3 Bq kg−1. The majority of the samples revealed external hazard index and representative level index less than one. The average air absorbed dose rate was 91.2 ± 13.6 nGy h−1 corresponding to the annual effective dose rate 111.8 ± 17.4 μSv y−1. These values were higher than the world averages for air absorbed dose rate and outdoor annual effective dose rate. Principal component analysis was applied to obtain distribution pattern within the samples and among the radionuclides.

scholarly journals Radionuclide Content and Risk Assessment of some Environmental Samples from Gold Mines at Mokuro-Ile-Ife, Osun State, Nigeria

2019 ◽  
Vol 7 (3) ◽  
Author(s):  
Oyebamiji Oyedele Oketayo ◽  
Muyiwa Joshua Adeleke ◽  
Olusola S. Ayanda
Keyword(s):  
Effective Dose ◽  
Water Samples ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Absorbed Dose ◽  
Early Years ◽  
Gold Mines ◽  
Equivalent Dose Rate ◽  
Average Value ◽  
Activity Concentrations

Mining and processing of natural resources has being in existence from the beginning of early years with little or no consideration to the possible radiation and contamination being posed into the environment. Using NaI (TI) gamma ray spectrometer, the activity concentration of naturally occurring  radionuclides were determined in soil, rock and water samples from Mokuro gold mines in Osun State, Nigeria. The average activity concentrations of  40K, 238U and 232Th in soil samples were 362.39 ± 83.88, 21.42 ± 6.68 and 17.99 ± 6.68 Bq/kg while in rock samples were 412.62 ± 91.18, 24.61 ± 8.58 and 19.40 ± 6.76 Bq/kg respectively.  For water samples, the mean activity concentrations were in the range of 8.65 ± 4.16 Bq/L, 7.71 ± 3.42 Bq/L, and 102.44 ± 30.50 Bq/L respectively. The annual effective dose contributed by 238U, 232Th and 40K varied from 0.84mSv/y to 0.93mSv/y with an average value 0.88 mSv/y while 232Th varied from 0.018 mSv/y to 0.020 mSv/y with average value 0.019 mSv/y and 40K varied from 0.22 mSv/y to 0.25 mSv/y with an average value 0.233 mSv/y. The 238U contribution to the Annual Effective Dose was very high compared with 232Th and 40K.. The calculated mean of absorbed dose (ADR), Annual Effective Dose (AED), Radium equivalent dose rate (Raeq), Internal and External Hazard Indices in the study area were less than the world averages and the limit recommended by ICRP for all water samples. The data obtained provided the baseline concentration and also indicated that continuous exploration could lead to contamination and eventually be hazardous. .

The Measurements of Natural Radioactivity, (Radon and Gamma concentrations), around the old fertilizer factory in Basrah/Iraq

2015 ◽  
Vol 7 (1) ◽  
pp. 1324-1335
Author(s):  
Jabbar H. Jebur
Keyword(s):  
Effective Dose ◽  
Radon Concentration ◽  
Gamma Ray ◽  
Annual Effective Dose ◽  
Track Detector ◽  
Exhalation Rate ◽  
Hazard Indices ◽  
Radium Equivalent ◽  
Passive Technique ◽  
Radium Activity

Radon concentration, exhalation rate, annual effective dose, radium activity, thorium, uranium potassium and radium equivalent have been measured in the present investigation for soil in the area around the old fertilizer factory in southern of Basrah Governorate. The measurements based on CR39 track detector for passive method, RAD7 for active method and NaI(Tl) for gamma concentration measurements. Average values for radon concentration in soil were 112.04±10.76 Bq/m3 using passive technique and 104.56±6.05 Bq/m3 using RAD7. From the result of the passive technique, area and mass exhalation rates and the annual effective dose were calculated. Gamma ray spectroscopy for the soil samples were performed and found that the average concentrations of 226Ra, 232Th and 40K were 50.89 Bq/kg, 21.74 Bq/kg and 640.4 Bq/kg respectively. Gamma ray hazard indices were calculated and found they are within the world average.

Assessment of Naturally Occurring Radioactive Materials (NORM) in Mining Residues and Environmental Material from Sefwi, Awaso Bauxite Mine

2021 ◽  
Author(s):  
Matjele Moipone ◽  
Oscar K. Adukpo ◽  
Joseph B. Tandoh
Keyword(s):  
Effective Dose ◽  
Water Samples ◽  
Red Mud ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry ◽  
Activity Levels ◽  
Environmental Material ◽  
Bauxite Ore ◽  
Mining Residues ◽  
Bauxite Mine

Abstract Gamma ray spectrometry was used to quantify level of NORM in mining residues sampled at Awaso bauxite mine and surrounding communities. The radionuclides of interest were 238U, 232Th and 40K and the radioactivity levels were determined in soil, bauxite ore, red mud and water samples from wells. The radioactivity concentrations in soil, bauxite ore and red mud 238U, 232Th and 40K were 18.01±1.96 Bqkg-1, 19.07±2.12 Bqkg-1 and 103.21±1.74 Bqkg-1; 39.42±4.18 Bqkg-1, 97.32±10.63 Bqkg-1 and 14.68±1.82 Bqkg-1; 44.85±4.79, 64.23±6.58 and 125.30±18.72 Bqkg-1. The activity levels for both 232U and 232Th were above world-wide average values while Potassium-40 levels were lower. The mean activity concentration values of 238U, 232Th and 40K in water samples were 1.49±0.45 Bql-1, 3.68±0.69 Bql-1 and 15.69±0.28 Bql-1 respectively and were within the world average activity concentrations except for bauxite ore and red mud. The committed effective dose was 0.74 mSv and annual effective dose estimated to be 0.136 mSv which is below recommended dose limit of 1 mSvyear-1 for public exposure.

ASSESSMENT OF NATURAL RADIOACTIVITY LEVELS AND RADIOLOGICAL HAZARDS IN BUILDING MATERIALS

2020 ◽  
Vol 188 (3) ◽  
pp. 316-321
Author(s):  
Fei Tuo ◽  
Xuan Peng ◽  
Qiang Zhou ◽  
Jing Zhang
Keyword(s):  
Building Materials ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Gamma Ray Spectrometry ◽  
Absorbed Dose Rate ◽  
Radium Equivalent Activity ◽  
Radiological Hazards ◽  
Radium Equivalent ◽  
Different Types ◽  
Radioactivity Levels

Abstract Radioactivity of 226Ra, 232Th, and 40K were measured in a total of 92 samples, including eight commonly used types of building materials that were obtained from local manufacturers and suppliers in Beijing. Concentrations were determined using high-purity germanium gamma-ray spectrometry. The 226Ra, 232Th, and 40K activity concentrations in all samples varied from 10.1 to 661, 3.3 to 555 and 3.2 to 2945 Bq per kg with an average of 127.8, 114.8, and 701.5 Bq per kg, respectively. The potential radiological hazards were estimated by calculating the absorbed dose rate (D), radium equivalent activity (Raeq), external hazard (Hex), and internal hazard (Hin) indices. The investigated building materials were classified into different types according to the radioactivity levels. Results from this research will provide a reference for the acquisition, sales, and use of building materials. Attention should be paid to the use of coal cinder brick, ceramic, and granite in the construction of dwellings.

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