STATISTICAL ESTIMATION OF RADIOLOGICAL HAZARDS FROM RADIONUCLIDE CONTENTS IN BUILDING MATERIALS

2019 ◽  
Author(s):  
O O Adewoyin ◽  
M Omeje ◽  
E S Joel ◽  
O A Odetunmibi
Keyword(s):  
Statistical Estimation ◽  
Building Materials ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry ◽  
Radium Equivalent Activity ◽  
Mean Values ◽  
Average Value ◽  
Radiological Hazards ◽  
Radium Equivalent ◽  
Safe Limit

Abstract Thirteen (13) types of building tiles and Sharp sand commonly used for building purposes were collected for their radionuclide contents analysis using gamma ray spectrometry. The average value of the Radium equivalent activity is 208.81 Bq/kg for all samples considered was found to be lower than the recommended safe limit of 370 Bq/kg. Similarly, both external and internal hazard indices (Hex and Hin) were noted to have mean values of 0.57 and 0.73, respectively, which were lower than the recommended safe standard of 1. More so, the average absorbed gamma dose rate was observed to be 94.31 nGy/h, much higher than the recommended safe limit of 59 nGy/h.

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.

The Radioactivity Levels and Safety Assessment of Building Materials in Nanjing, Jiangsu Province, China

2011 ◽  
Vol 243-249 ◽  
pp. 6913-6918
Author(s):  
Jian Lu ◽  
Hao Yang ◽  
Ming Li Zhang
Keyword(s):  
Building Materials ◽  
Gamma Ray ◽  
Natural Radionuclides ◽  
Jiangsu Province ◽  
Internal Exposure ◽  
External Exposure ◽  
Exposure Index ◽  
Radium Equivalent Activity ◽  
Radium Equivalent ◽  
Radioactivity Levels

In order to invetigate the natural radioactivity levels of typical building materials in Nanjing, Jiangsu Province,China, the specific activities of natural radionuclides (226Ra,232Th and40K) in samples of building materials were measured by ORTEC HPGe gamma ray spectrometer. And the radium equivalent activity, the internal and external exposure index, and relative annual effective dose equivalents were also claculated. The average concentrations of all the samples ranged from 64 to 318.79 Bq·kg-1, 11.35 to 144.83 Bq·kg-1and 92.57 to 951.68 Bq·kg-1for226Ra,232Th and40K, respectively. Their average values were in the ranges: 0.33-1.50 for the internal exposure index (Ira); 0.29-1.51 for the external exposure index (Ir); 0.34-1.74 mSv·a-1 for HEextand 0.36-1.76 mSv·a-1for HEint. The average radium equivalent activity varied from 106.49 to 541.77 Bq·kg-1. According to the standard, most samples were in a lower radioactivity level expect a few of artificial tiles. But, we must perfect detection and management system of many materials to ensure radiation safety and physical health.

scholarly journals ESTIMATION ON THE RADIOLOGICAL LEVEL OF NATURAL OCCURRING RADIONUCLIDES PRESENT IN FLOODED SOIL SAMPLES IN KADUNA NORTH, NIGERIA

2017 ◽  
Vol 5 (10) ◽  
pp. 81-91
Author(s):  
P.M. Gyuk ◽  
J.O. Anaegbu ◽  
H.O. Aboh ◽  
R. Daniel ◽  
A. Aruwa ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Background Radiation ◽  
Absorbed Dose ◽  
Soil Samples ◽  
Gamma Ray Spectrometry ◽  
Published Data ◽  
Absorbed Dose Rate ◽  
Radium Equivalent Activity ◽  
Activity Concentrations ◽  
Radium Equivalent

The background radiation of the areas was collected at random for each point using a rados survey meter. The detectors (two rados survey meter were used) were placed 1 meter above the ground with the operator positioned a few meters away. Three (3) readings were taking from each detector in other to reduce error or reach accuracy in obtaining the background readings from each randomly selected point where soil samples were later collected. In the current study, the concentration levels of naturally occurring radioactive materials (NORMs) of 40K, 232Th, and 238U in the surface soil samples of selected areas in kigo road new extension Kaduna north, Kaduna in Nigeria were studied. The collected soil samples were analyzed by means of gamma-ray spectrometry. The mean activity concentrations of the natural occurring radionuclides of  226Ra, 232Th and 40K in the soil samples were estimated to be 62, 78.35, 227.17 Bq/kg respectively for kigo road new extension respectively. Radium equivalent activity, absorbed dose rate, annual effective dose equivalent were also calculated for assessment of radiological risk. External hazard value (Hex) is between 0.3163 and 0.9557 and Internal hazard value is between 0.4462 and 1.1618. The worldwide average activity concentrations of 226Ra, 232Th and 40K in soil samples from various studies around the world have values of 37, 30 and 400 Bq/kg respectively [UNSCEAR, 2000]. The values compared well with published data from UNSCEAR shows Ra-226, Th-232 from the location are well above the standards while K-40 below the risk value.

Assessment of Radiological Significance of the Wastes Generated from the Triple Super Phosphate (TSP) Fertilizer Factory, Chittagong, Bangladesh

2012 ◽  
Vol 36 (1) ◽  
pp. 79-88 ◽  
Author(s):  
MA Samad ◽  
MI Ali ◽  
D Paul ◽  
SMA Islam
Keyword(s):  
Gamma Ray ◽  
Hazard Index ◽  
Liquid Waste ◽  
Radiation Hazard ◽  
Gamma Ray Spectrometry ◽  
Radium Equivalent Activity ◽  
Average Value ◽  
Liquid Samples ◽  
Activity Concentrations ◽  
Academy Of Sciences

The activity concentration of 226Ra, 232Th and 40K was determined in solid and liquid samples collected from the TSP Fertilizer Factory, Chittagong, Bangladesh. A total of 18 samples of seven different kinds (including liquid and solid wastes) were collected and analyzed by gamma ray spectrometry technique using a high purity germanium (HPGe) detector of 40% relative efficiency. The analysis of the liquid waste samples showed that the average activity concentrations of 226Ra and 232Th were 6.26 ± 0.63 and 10.01 ± 1.39 Bq/L, respectively and no 40K was detected in any of the liquid samples. In the solid waste samples the average value of activity concentrations of 226Ra, 232Th and 40K were 187.49 ± 4.88, 70.06 ± 11.76 and 655.94 ± 110.24 Bq/kg, respectively. Considering the stored wastes as a part of the ambient environment of the factory, radium equivalent activity, radiation hazard index and external annual effective dose to the worker and public due to these wastes were also calculated and compared with world average values. DOI: http://dx.doi.org/10.3329/jbas.v36i1.10923 Journal of Bangladesh Academy of Sciences, Vol. 36, No. 1, 79-88, 2012

Assessment of radiation hazards due to exposure to radionuclides in marble and ceramic commonly used as decorative building materials in Egypt

2016 ◽  
Vol 26 (3) ◽  
pp. 317-326 ◽  
Author(s):  
Nabil M. Hassan ◽  
N. A. Mansour ◽  
M. Fayez-Hassan ◽  
Samar Fares
Keyword(s):  
Building Materials ◽  
Gamma Spectroscopy ◽  
Hazard Indices ◽  
Radium Equivalent Activity ◽  
Radiation Hazards ◽  
Radiological Hazards ◽  
Ceramic Samples ◽  
Standard Guideline ◽  
Radium Equivalent ◽  
Effective Doses

The concentrations of 238 U (226Ra), 232Th, and 40K for the commonly used decorative building materials (15 marble and 15 ceramic) in Egypt were measured using gamma spectroscopy system. Radionuclides concentrations in marble samples were ranged from: ND to 49.92 ± 7.74 Bq kg−1 for 226Ra, 8.30 ± 1.70 to 119.52 ± 16.00 Bq kg−1 for 232Th, and 32.60 ± 4.25 to 2238.33 ± 242.66 Bq kg−1 for 40K while in ceramic samples the concentration ranged from: 28.42 ± 5.41 to 118.70 ± 20.34 Bq kg−1 for 226Ra, 30.65 ± 5.49 to 114.15 ± 18.78 Bq kg−1 for 232Th, and 389.54 ± 49.57 to 1069.83 ± 124.50 Bq kg−1 for 40K, respectively. These results imply that radium and thorium concentrations were below the worldwide recommended values but potassium was above the standard guideline. Radiological hazards indices of radium equivalent activity (Raeq), external and internal hazard indices: Hex and Hin, respectively, and annual effective doses of the investigated materials due to the presence of those radionuclides were calculated and had values less than the worldwide recommended values of 370 Bq kg−1, unity and 1 mSv y−1, respectively. Therefore, the studied types of marble and ceramic can be safely used as decorative building materials.

scholarly journals 232Th, 226Ra, and 40K activities and associated radiological hazards in building materials of Islamabad capital territory, Pakistan

2012 ◽  
Vol 27 (4) ◽  
pp. 392-398 ◽  
Author(s):  
Saeed Rahman ◽  
Muhammad Rafique
Keyword(s):  
Effective Dose ◽  
Dose Rate ◽  
Building Materials ◽  
Annual Effective Dose ◽  
Absorbed Dose ◽  
Absorbed Dose Rate ◽  
Radium Equivalent Activity ◽  
Radiological Hazards ◽  
Radium Equivalent ◽  
The Mean

Radioactivity levels in building materials, collected from the Islamabad capital territory have been determined by using a gamma spectrometric technique. Measured specific activities of 226Ra, 232Th, and 40K in material samples ranged from 8 ? 1 to 116 ? 6 Bq/kg, 9 ? 1 to 152 ? ? 5 Bq/kg, and 29 ? 6 to 974 ? 23 Bq/kg, respectively. The radium equivalent activity, absorbed dose rate, annual effective dose, and gamma index were evaluated from the measured amounts of radioactivity to assess the radiation hazard associated with the studied building materials. The mean radium equivalent activity, the absorbed dose rate and annual effective dose estimated ranged from 81 ? 6 to 221 ? 11 Bq/kg, 38 ? 3 to 104 ? 5 nGy/h, and 0.23 ? 0.02 to 0.64 ? 0.03 mSv, respectively. The ranges of the calculated Raeq were found to be lower than the values recommended for construction materials (370 Bq/kg). The mean values of the internal and external hazard indices were found in the range of 0.30 ? 0.02 to 0.78 ? 0.05 and 0.22 ? 0.02 to 0.60 ? 0.03, respectively. The results of the materials examined indicate no significant radiological hazards arise from using such material in building construction.

RADIATION EXPOSURE FROM NATURAL RADIONUCLIDES IN BUILDING MATERIALS

2018 ◽  
Vol 185 (1) ◽  
pp. 49-57 ◽  
Author(s):  
M J Madruga ◽  
C Miró ◽  
M Reis ◽  
L Silva
Keyword(s):  
Building Materials ◽  
Gamma Ray ◽  
Health Hazard ◽  
Natural Radionuclides ◽  
Mean Value ◽  
Radium Equivalent Activity ◽  
Dose Rates ◽  
Radium Equivalent ◽  
Radiological Health ◽  
Hazard Parameters

Abstract Building materials from Iberian Peninsula (Portugal and Spain) were collected and analysed for 226Ra, 232Th and 40K using HPGe gamma-ray spectrometers. The results show that the highest mean value of 226Ra and 232Th activities are 2168 and 390 Bq kg−1, respectively, measured in zircon. For 40K, this value is 1290 Bq kg−1, measured in granite. The mean concentrations of the three radionuclides in the different building materials, excluding the zircon and the industrial by-products (ashes, gypsum and phosphogypsum), are 62, 31 and 519 Bq kg−1 for 226Ra, 232Th and 40K, respectively. The radiological health hazard parameters: radium equivalent activity (Raeq), activity concentration index (I) absorbed and effective dose rates, associated with these radionuclides, were evaluated. These values are within the EU recommended limits in building materials, except for same samples of aggregates, granites, ceramics, phosphogypsum and zircon. This study will contribute for the worldwide data pooling on the radioactivity of the building materials.

scholarly journals Assessment of Natural Radioactivity Levels and Radiation Hazards in Agricultural and Virgin Soil in the State of Kedah, North of Malaysia

2016 ◽  
Vol 2016 ◽  
pp. 1-9 ◽  
Author(s):  
Ghazwa Alzubaidi ◽  
Fauziah B. S. Hamid ◽  
I. Abdul Rahman
Keyword(s):  
Gamma Ray ◽  
Agricultural Soils ◽  
Soil Depth ◽  
Hazard Index ◽  
Absorbed Dose ◽  
Gamma Ray Spectrometry ◽  
Virgin Soil ◽  
Radium Equivalent Activity ◽  
Mean Values ◽  
The Mean

The activity concentrations of naturally occurring radionuclides226Ra,232Th, and40K were determined in 30 agricultural and virgin soil samples randomly collected from Kedah, north of Malaysia, at a fertile soil depth of 0–30 cm. Gamma-ray spectrometry was applied using high-purity germanium (HPGe) gamma-ray detector and a PC-based MCA. The mean radioactivity concentrations of226Ra,232Th, and40K were found to be 102.08 ± 3.96, 133.96 ± 2.92, and 325.87 ± 9.83 Bq kg−1, respectively, in agricultural soils and 65.24 ± 2.00, 83.39 ± 2.27, and 136.98 ± 9.76 Bq kg−1, respectively, in virgin soils. The radioactivity concentrations in agricultural soils are higher than those in virgin soils and compared with those reported in other countries. The mean values of radium equivalent activity (Raeq), absorbed dose ratesD(nGy h−1), annual effective dose equivalent, and external hazard index (Hex) are 458.785 Bq kg−1, 141.62 nGy h−1, and 0.169 mSv y−1, respectively, in agricultural soils and 214.293 Bq kg−1, 87.47 nGy h−1, and 0.106 mSv y−1, respectively, in virgin soils, with averageHexof 0.525. Results were discussed and compared with those reported in similar studies and with internationally recommended values.

Distribution of natural radioactivity and radiological hazard using a NaI(Tl) gamma-ray spectrometric system

2016 ◽  
Vol 40 (4) ◽  
pp. 324-333
Author(s):  
M Abu Shayeb ◽  
A Majid ◽  
S Zobidi
Keyword(s):  
Gamma Ray ◽  
Hazard Index ◽  
Absorbed Dose ◽  
Gamma Ray Spectrometry ◽  
Absorbed Dose Rate ◽  
Radium Equivalent Activity ◽  
Naturally Occurring ◽  
Naturally Occurring Radionuclides ◽  
Radium Equivalent ◽  
Spectrometric System

The concentrations of 226Ra, 232Th, and 40K are measured in the material collected from two locations. The collected materials are analyzed using gamma-ray spectrometry. The activity concentration of the naturally occurring radionuclides 226Ra, 232Th, and 40K in building material varies from 12.6 to 121.4, 13.6 to 142, and 69.5 to 620.6 Bq kg−1, respectively. The radium equivalent activity, absorbed dose rate, annual effective dose, and hazard index are also calculated.

Natural radioactivity in some building materials and assessment of the associated radiation hazards

2018 ◽  
Vol 106 (1) ◽  
pp. 79-86
Author(s):  
Amira Kasumović ◽  
Ema Hankić ◽  
Amela Kasić ◽  
Feriz Adrović
Keyword(s):  
Building Materials ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Absorbed Dose Rate ◽  
Radium Equivalent Activity ◽  
Radiation Hazards ◽  
Eu Member States ◽  
Gamma Ray Spectrometer ◽  
Radioactive Nuclides ◽  
Specific Activities

AbstractThe results of the specific activities of232Th,226Ra and40K measured in samples of commonly used building materials in Bosnia and Herzegovina are presented. Measurements were performed by gamma-ray spectrometer with coaxial HPGe detector. The surface radon exhalation and mass exhalation rates for selected building materials were also measured. The determined values of specific activities were in range from 3.16±0.81 Bq kg−1to 64.79±6.16 Bq kg−1for232Th, from 2.46±0.95 Bq kg−1to 53.89 ±3.67 Bq kg−1for226Ra and from 28.44±7.28 Bq kg−1to 557.30±93.38 Bq kg−1for40K. The radium equivalent activity, the activity concentration index, the external and internal hazard indices as well as the absorbed dose rate in indoor air and the corresponding annual effective dose, due to gamma-ray emission from the radioactive nuclides in the building material, were evaluated in order to assess the radiation hazards for people. The measured specific activities of the natural radioactive nuclides in all investigated building materials were compared with the published results for building materials from other European countries. It can be noted that the results from this study are similar to the data for building materials from neighbouring countries and for building materials used in the EU Member States. The radiological hazard parameters of the building materials were all within the recommended limits for safety use.

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