Radiological Risk Assessment of Radon Gas in Bricks Samples in Iraq

2020 ◽  
Author(s):  
Ali Abid Abojassim
Keyword(s):  
Risk Assessment ◽  
Annual Effective Dose ◽  
Radiological Protection ◽  
Human Beings ◽  
Radiological Risk ◽  
United Nations Scientific Committee ◽  
Lifetime Cancer Risk ◽  
Average Value ◽  
Permissible Limits ◽  
Radon Gas

Abstract In this research , radon concentrations (222Rn) in brick samples that are available in Iraqi markets were measured using solid state nuclear track (CR-39). Also, uranium-238 (238U), radium-226 (226Ra) were calculated in all samples under study together with some radiation parameters such as exhalation of radon gas rate (FO), annual effective dose (DRn ) and Excess lifetime cancer risk (ELCR). It was found that, the average value of 222Rn, 238U and 226Ra concentrations in studied samples were 48.75± 10.61Bq/m3, 0.084± 0.02 ppm and 115.57± 29.60 mBq/kg respectively. Also, it was found that the average of each of FO, DRn and ELCR were 27.54± 5.99 µBq.m-2.h-1, 0.88± 0.17 nSvy-1, and (3.01± 0.65)×10-3, respectively. After data analysis, the resulted data were examined and compared with the global average and the permissible limits which recommended by the international scientific agencies such as International Commission on Radiological Protection (ICRP 2010), United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR 2017), Organization for Economic Cooperation and Development (OECD2009). It was found that radiation levels from brick samples used in local markets for most models fell within the permissible limits and may not cause any danger to human beings.

scholarly journals Radiological risk assessment of some consumed cigarettes and hookah in Iraq

2020 ◽  
Vol 8 (2) ◽  
pp. 60
Author(s):  
Sahar Amin ◽  
Azhar Haleem ◽  
Ola Mahmood
Keyword(s):  
Lung Cancer ◽  
Risk Assessment ◽  
Risk Factor ◽  
Annual Effective Dose ◽  
Energy Concentration ◽  
Radon Progeny ◽  
Radiological Risk ◽  
Cigarette Tobacco ◽  
Average Value ◽  
The People

The main purposes of the research are to assess the radiological risk due to smoking cigarettes and hookah and their impacts on the people health. Radon levels were measured in 28 consumed brands of cigarettes and 10 brands of hookah consumed Iraq using CR-39 solid state nuclear track detectors (SSNTDs). The results showed that the 222Rn concentration in cigarette tobacco samples ranged from 138.9 to 781.2 Bqm-3 with average value of 318.0 Bqm-3. The radon concentrations emerged from 11brands of the investigated samples was significantly higher than the recommended value. While, its concentration in hookah ranged from 633.6 Bqm-3 to 416.6 Bqm-3 with average value of 509.5 Bqm-3. The Potential Alpha Energy Concentration (PAEC) in terms of (WL) units, Exposure to radon progeny (EP), and the annual effective dose (AED) in terms of (mSv/y) units were also obtained. Lung cancer cases per year per million people (CPPP) are also evaluated with an average value of 144.4 per million people. The result indicates that the average values of PAEC, EP and AED were within the recommended range values given by UNSCEAR, NCRP and ICRP respectively. The radioactive impact of smoking is considered as a risk factor for lung cancer.

scholarly journals Measurement of Indoor Radon Gas Concentration in same Region of Baghdad Governorate Using CR-39 Nuclear Track Detector

2017 ◽  
Vol 14 (4) ◽  
pp. 688-691 ◽  
Author(s):  
Baghdad Science Journal
Keyword(s):  
Effective Dose ◽  
Radon Concentration ◽  
Annual Effective Dose ◽  
Indoor Radon ◽  
Track Detector ◽  
Nuclear Track Detector ◽  
Gas Concentration ◽  
Alpha Emitters ◽  
Average Value ◽  
Radon Gas

In this research the activity of radon gas in air in Baghad governorate,Iraq, using “alpha-emitters track registration (CR-39) track detector were measured. This measurement was done for selected areas from Baghdad Governorate, The results obtained shows that the highest average concentrations for Rn-222 is (179.077 Bq/m^3) which was recorded within Al-Shaaib city and less average concentrations was (15.79 Bq/m^3) in the nearby residential area of Baghdad International Airport and the overall average concentrations is (86.508 Bq/m^3) for these regions. Then the radon concentration was measured annual effective dose calculated from radon concentration and found in range from 0.4031 mSv/y to 4.5179 mSv /y with an average value of 2.1824 mSv/y. The annual effective dose of radon was within the allowed international limits.

scholarly journals Radon study around earthquake affected areas of Nepal

BIBECHANA ◽  
2021 ◽  
Vol 18 (2) ◽  
pp. 61-67
Author(s):  
Bipin Rijal ◽  
Nigam S. Silwal ◽  
Govinda Chaudhary ◽  
Pitamber Shrestha ◽  
Buddha R. Shah
Keyword(s):  
Solid State ◽  
Annual Effective Dose ◽  
Indoor Radon ◽  
Track Detector ◽  
Kathmandu Valley ◽  
Radiological Protection ◽  
Nuclear Track Detector ◽  
Lifetime Cancer Risk ◽  
Radiological Health ◽  
Radon Concentrations

Indoor radon concentrations were measured in dwellings of the earthquake-affected areas of Kathmandu valley, Gorkha, and Sindhupalchowk districts of Nepal using passive radon dosimeter LR115, a Solid State Nuclear Track Detector, SSNTD. The radon concentrations in dwellings of Kathmandu valley ranged from 11±6 Bq/m3 to 135±26 Bq/m3 with a mean of 67.63 Bq/m3. For  Gorkha, it ranged from 18±7 Bq/m3 to 363±65 Bq/m3 with an average of 104.64 Bq/m3 while minimum, maximum and average radon concentrations for Sindhupalchowk were 14±6 Bq/m3, 397±71 Bq/m3, and 78.46 Bq/m3 respectively. The average annual effective dose to the inhabitants of Kathmandu valley, Gorkha, and Sindhupalchowk districts was calculated as 1.46 mSv/y, 2.26 mSv/y, and 1.69 mSv/y respectively. These annual doses were well below the action level of 10 mSv/y recommended by the International Commission on Radiological Protection which implies no significant radiological health hazards. Also, Excess Lifetime Cancer Risk and Lungs Cancer Cases per year per million people were determined. BIBECHANA 18 (2) (2021) 61-67

scholarly journals Measurement of indoor radon concentrations in different dwellings in Arar, Saudi Arabia

2018 ◽  
Vol 33 (3) ◽  
pp. 293-300
Author(s):  
Ayman Abdalla ◽  
Samy El-Gamal
Keyword(s):  
Annual Effective Dose ◽  
Indoor Radon ◽  
Geometric Mean ◽  
International Committee ◽  
Geometric Standard Deviation ◽  
Cancer Risks ◽  
Indoor Radon Concentration ◽  
Lifetime Cancer Risk ◽  
Average Value ◽  
Radon Concentrations

Indoor radon concentrations in 33 dwellings in Arar city were measured using a CR-39 detector. This work is the first in the region and was done to assess the health risks. The exposure time was about 4 months, from May to September 2017. It was found that the indoor radon concentration changed in the range from 7.7 to 89.1 Bqm-3 with an overall average of 44.05 ? 6.21 Bqm-3 while the geometric mean is 39.51 Bqm-3 with a geometric standard deviation of 1.67. These values are within the acceptable level set by the International Committee for Radiation Protection. The annual effective dose received by the population of Arar was reported and it varied in the range 0.16 -1.82 mSv with an average value of 0.9 ? 0.16 mSv and the geometric mean is 0.81 mSv. The exposure to radon progeny was studied where the minimum, maximum, average, and geometric mean of exposure are 0.83?10-3, 9.63?10-3, 4.76 ? 0.67? 10-3 and 5.05?10-3 WLM, respectively. Finally, for the estimation of cancer risks, the excess lifetime cancer risk was investigated. Its average value was 3.7?10-3 which is relatively higher.

scholarly journals Evaluation of background radiation level and excess lifetime cancer risk in Doon valley, Garhwal Himalaya

2021 ◽  
Author(s):  
Tushar Kandari ◽  
Prakhar Singh ◽  
Poonam Semwal ◽  
Ankur Kumar ◽  
A. A. Bourai ◽  
...  
Keyword(s):  
Cancer Risk ◽  
Background Radiation ◽  
Mean Value ◽  
Garhwal Himalaya ◽  
Gamma Ray Spectrometry ◽  
Human Beings ◽  
Lifetime Cancer Risk ◽  
Doon Valley ◽  
Average Value ◽  
Excess Lifetime Cancer Risk

AbstractRadionuclides such as Ra-226, Th-232 & K-40 occurs naturally in the earth crust from its creation and are main contributor to the dose received by human beings. The present study was carried-out in the Doon valley which is outlined in the Main Boundary Thrust (MBT) region of Garhwal Himalaya in Uttarakhand, India. The collected soil/rock samples were analyzed by NaI(Tl) Gamma ray spectrometry for the analysis of radionuclides and hence measuring the various health hazard indices and Excess lifetime cancer risk. Radionuclide (226Ra, 232Th & 40K) content were found to vary from 47 ± 9 to 442 ± 50 Bq Kg−1, 45 ± 17 to 101 ± 16 Bq Kg−1 & 320 ± 281 to 947 ± 197 Bq Kg−1 respectively and were higher than the world average values which are 35 Bq Kg−1, 30 Bq Kg−1 and 400 Bq Kg−1 respectively. Higher radionuclide content contributes to higher amount of absorbed doses which was found to vary from 93 to 259.6 ηGyh−1 with a mean value of 112.5 ηGyh−1 and Gamma index which found to vary from 0.73 to 1.92 with a mean value of 0.96. Lastly, on the basis of annual effective doses received to humanoid, Excess lifetime cancer risk was measured which varies from 0.48 × 10–3 to 1.34 × 10–3 with an average value of 0.65 × 10–3 and was much below the world’s average value of 1.45 × 10–3.

scholarly journals The Dependence of Volumetric Radon Activity in Indoor Air on Environmental Conditions

2020 ◽  
Vol 71 (7) ◽  
pp. 197-209
Author(s):  
Ingrida Pliopaite Bataitiene ◽  
Raimondas Grubliauskas ◽  
Raimondas Buckus ◽  
Tatjana Juzsakova ◽  
Igor Cretescu
Keyword(s):  
Indoor Air ◽  
Residential Buildings ◽  
Indoor Radon ◽  
Environmental Parameters ◽  
Exposure Level ◽  
Human Beings ◽  
Radiological Risk ◽  
Radon Activity ◽  
Average Value ◽  
Average Activity

The radon isotope, 222Rn, has a significant impact on human beings due to the irradiation caused illnesses. The article deals with the process of radon entering into residential buildings and its residential exposure level related to changes in environmental parameters such as temperature, pressure and moisture content. Dependence of the indoor radon activity on environmental factors has been studied at three sites: two multi-storey and one low-rise buildings in autumn (September � November 2014) period. During the study period radon activity values in low-rise house constructed in 2009, in Lithuania at Ukmerge district, Jogvil� village, ranged from 73 � 13 to 747 � 134 Bq m-3 and the average value was 382 � 76 Bq m-3. This value is higher than the allowed average activity value of 300 Bq m-3 and could present a radiological risk for inhabitants if the above mentioned parameters are not taken into account.

scholarly journals Measurements of Radon Concentrations and Dose Assessments in Physics Department-Science College-Al-Mustansiriyah University, Baghdad, Iraq

2015 ◽  
Vol 60 ◽  
pp. 83-93 ◽  
Author(s):  
Iman Tarik Al-Alawy ◽  
Haider Rayed Fadhil
Keyword(s):  
Effective Dose ◽  
Building Materials ◽  
Annual Effective Dose ◽  
Indoor Radon ◽  
Alpha Particles ◽  
Energy Concentration ◽  
Nuclear Track Detector ◽  
Average Value ◽  
Radon Gas ◽  
Physics Department

Measurements of radon gas concentrations with their progeny and the annual effective dose indoor the building of Al-Mustansiriyah University College of Science-Physics Department have been carried out by using time-integrated passive radon dosimeters solid state nuclear track detector CR-39 technique. The detectors with 1cm x1cm have been distributed over 70 places and suspended for sitting (1m) and standing (1.75m) positions in each location under study. The dosimetric measurements are made over a period of 90 days from 30 January 2014 to 30 April 2014. The calibration process has been done using radium-226 source with known activity radiation. It has found that the indoor radon gas concentrations varing from 37.488±6.123Bg/m3 to 58.670±7.660Bg/m3 with an average value 51.398±7.156Bg/m3 at 1m , and varing from 35.964±5.997Bg/m3 to 56.994±7.549Bg/m3 with an average value 47.057±6.847Bg/m3 at 1.75m which are within the worldwide limits 148Bg/m3 (EPA, 2003) and 200-300Bg/m3 (ICRP, 2009). The annual effective dose of the inhalation exposure to radon gas has been estimated and this vary from 0.394mSv/y to 0.617mSv/y with an average value 0.540mSv/y at 1m, and varing from 0.378mSv/y to 0.599mSv/y with an average value 0.495mSv/y at 1.75m which are within the worldwide permissible limist 3-10mSv/y (ICRP, 1993). The potential alpha energy concentration found to vary from 4.053mWL to 6.343mWL with an average value 5.557mWL at 1m and vary from 3.888mWL to 6.162mWL with an average value 5.087mWL at 1.75m which are less than the recommended value 53.33mWL (UNSCEAR, 1993). The lung cancer cases per million person per year vary from 7.093 to 11.101 per million person per year with an average value 9.725 per million person per year at 1m and vary from 6.805 to 10.784 per million person per year with an average value 8.904 per million person per year which are less than the recommended range 170-230 per million person per year (ICRP, 1993). The number of decays per-minute using swabs measurements technique have been used for selected units within two swabs from building materials walls for each unite, with area of 100cm2 using Ludlum 3030, the average of three swabs measurements have been calculated. Hence, the effectiveness of emitted alpha particles from the walls has been calculated to be varied from 0.00000 to 0.02222Bq/cm2 with an average value 0.01169Bq/cm2 at 1m and 0.01015Bq/cm2 at 1.75m respectevily which are within the permissible limit 0.04Bq/cm2 (Danial, 2010).

ASSESSMENT OF INDOOR GAMMA RADIATION AND DETERMINATION OF EXCESS LIFETIME CANCER RISK IN TEHRAN IN WINTER AND SPRING 2017

2018 ◽  
Vol 184 (2) ◽  
pp. 148-154 ◽  
Author(s):  
Marjan Hashemi ◽  
Leila Akhoondi ◽  
Mohammad Hossien Saghi ◽  
Akbar Eslami
Keyword(s):  
Cancer Risk ◽  
Gamma Radiation ◽  
Dose Rate ◽  
Annual Effective Dose ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Lifetime Cancer Risk ◽  
Average Value ◽  
Excess Lifetime Cancer Risk

Abstract Natural radiation is a feature of the environment in which we live. One of the contributions of human exposure to ionizing radiation due to natural sources arises from gamma radiation. Therefore, present study was aimed to evaluate and map indoor gamma dose rate in Tehran. The corresponding annual effective dose (AED) and excess lifetime cancer risk (ELCR) were also calculated. All measurements were performed by a Geiger Muller detector in 43 dwellings in Tehran. The average indoor gamma dose rate in Tehran was appointed as 343.2 nGy/h. AED and ELCR were calculated as 2.4 mSv and 10.3 × 10−3, respectively. The evaluated indoor gamma dose rate and calculated AEDs and lifetime cancer risk were found higher than the world average value.

scholarly journals Risk assessment of metals from shallow groundwater in Lianhuashan District, China

2020 ◽  
pp. 5-15
Author(s):  
Hui Tian ◽  
Xiujuan Liang ◽  
Yan Gong ◽  
Shimin Ma ◽  
Zhuang Kang ◽  
...  
Keyword(s):  
Risk Assessment ◽  
Drinking Water ◽  
Hazard Index ◽  
Shallow Groundwater ◽  
Carcinogenic Risk ◽  
Dermal Absorption ◽  
Lifetime Cancer Risk ◽  
Permissible Limits ◽  
Adults And Children ◽  
Absorption Pathways

The present study was conducted to investigate trace metal (Fe, Mn, Cd, Pb, Zn, Cu, Al, As, Se, Hg, Sr, Ba, Li, Co, B, Ni, Ag, Mo and Cr) concentrations of drinking water samples in Lianhuashan District, China. Furthermore, the study aimed to ascertain carcinogenic and non-carcinogenic health risks of metals by ingestion and dermal absorption pathways to the local residents. Metal concentrations were compared with permissible limits set by the Chinese Standards, USEPA and WHO. The average concentrations of the analyzed elements are in the order of Fe > Sr > Mn > Al > Ba > Mo > Zn > B > Li > Pb > Cr > Ni > Cu > Ag > Co > As > Se > Cd > Hg. The results indicate that the concentrations of Cd, Zn, Cu, Ni, Se, Hg, Ba and Cr were lower than their respective permissible limits, whereas the concentrations of Fe, Mn, Pb, Al, As and Mo at some sampling sites exceeded the permissible limits. The total hazard index (HQtotal) of the metals (Cd, Zn, Cu, Al, Se, Hg, Sr, Ba, B, Ni, Ag, Cr) calculated through ingestion and dermal absorption pathways for adults and children were found to be lower than unity, indicating that the metals would not pose any adverse effect and non-carcinogenic health risk to the habitants. The results of carcinogenic risk assessment indicate that the Excess Lifetime Cancer Risk (ingestion and dermal exposure pathways) of metals exposure was in accordance to the acceptable lifetime risks for carcinogens in drinking water (10−6–10−4). Both non-carcinogenic and carcinogenic risks were mainly attributed to the ingestion pathways.

scholarly journals Assessment of background ionizing radiation dose levels in quarry sites located in Ebonyi State, Nigeria

2020 ◽  
Vol 24 (10) ◽  
pp. 1821-1826
Author(s):  
E.O. Echeweozo ◽  
F.O. Ugbede
Keyword(s):  
Radiation Dose ◽  
Ionizing Radiation ◽  
Effective Dose ◽  
Dose Rate ◽  
Annual Effective Dose ◽  
Nuclear Radiation ◽  
Radiological Protection ◽  
Continuous Exposure ◽  
Average Value ◽  
Dose Levels

The study presents a radiometric survey of Background Ionizing Radiation (BIR) dose levels in ten quarry sites located in Ebonyi State, Nigeria. In-situ BIR dose rate measurements, by means of nuclear radiation survey meter, at 1 m above ground level were carried out at the excavation section (ES) and quarrying section (QS) of the investigated quarry sites. The obtained results indicated dose rates ranging from from 0.14 to 0.18 μSv/h with mean of 0.15±0.01 μSv/h at the ES and 0.16 to 0.19 μSv/h with mean value of 0.18±0.01 μSv/h at the QS. While the values obtained at the QS are respectively higher than those measured at the ES, they are all higher than the worldwide average value of 84 nSv/h signifying BIR elevated environments. The estimated mean annual effective dose (AED) and excess lifetime cancer risk (ELCR) are 0.27±0.03 mSv/y and 0.94×10–3 respectively at the ES and 0.31±0.02 mSv/y and 1.07×10–3 at the QS. The obtained AED values for all the sites are well above the outdoor worldwide average value of 0.07 mSv/y but lower than the International Commission on Radiological Protection recommended permissible limits of 1.0 mSv/y for the general public. Generally, the BIR levels of the quarry sites are within acceptable limits and no immediate radiological health threat may be derived from the current levels. However, long-term health effects due to continuous exposure to low-level radiation doses may manifested in future over a lifetime exposure of 70 years as indicated by the ELCR values. Keywords: Background ionizing radiation, Dose rate, Annual effective dose, Quarry site, Ebonyi State

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