scholarly journals Radiation Risk Assessment of Soil in Idomi, Cross River State, Nigeria

2019 ◽  
Vol 7 (1) ◽  
Author(s):  
N. O. Chiaghanam ◽  
C. C. Nzotta ◽  
L. B. Enweani

In this thesis work, the radiation risk from soil samples in Idomi community located at Yakurr Local Government Area of Cross River State, Nigeria was studied. This was because of an earlier study that revealed the presence of high radioactivity in the area. This study aim to determine the background radiation levels, estimate their effective dose, the mean activity concentrations of the radionuclide and the radiological implications of the radioactivity levels in Idomi. Thirty (30) soil samples were collected and analyzed. The baseline average annual outdoor effective dose, mean activity concentration, gamma absorbed dose and radiological hazard index were studied. Results from this study indicate that three (3) radionuclide namely 40K, 238U and 232Th were present in the soil samples analyzed.  The mean activity concentrations of 40K, 238U and 232Th in the soil samples were 506.13±9.30, 41.14±3.59 and 84.52±20.88 Bqkg-1 respectively.  The calculated mean external and internal hazard index was 0.62 and 0.71 respectively. The calculated mean gamma index was 0.86. The Raeq in the soil samples was 227.34 Bqkg-1. The calculated absorbed gamma dose from the sample was 110.31nGy-1 and a mean annual outdoor effective dose of 1.35mSvy-1.  Compared with global average values of 10-200nGyh-1, 2.4 mSvy-1and Raeq of 370BqKg-1 they can be said to be within the normal range. From this study, the chances of occurrence of health effects from exposure to natural terrestrial gamma radiation in Idomi can be said to be low.  This may be possible if the baseline levels obtained from this study can be kept constant by keeping the environment free of radioactive pollution.

Author(s):  
P.M. Gyuk ◽  
J.O. Anaegbu ◽  
H.O. Aboh ◽  
R. Daniel ◽  
A. Aruwa ◽  
...  

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.


2020 ◽  
Vol 39 (1) ◽  
pp. 77 ◽  
Author(s):  
Aleksandra Angjeleska ◽  
Elizabeta Dimitrieska-Stojkovic ◽  
Zehra Hajrulai-Musliu ◽  
Radmila Črčeva-Nikolovska ◽  
Boško Boškovski

The aim of this study was to determine the activity concentrations of naturally occurring radioisotopes 226Ra, 232Th and 40K in 14 soil samples collected in the Skopje city surrounding, and to calculate the corresponding absorbed gamma dose rates. The radionuclides were measured applying a high purity Ge detector gamma-ray spectrometer with relative efficiency of 30 % at 1.33 MeV. The activity concentrations found in 14 soil samples varied in the range 24.1-41.9 Bq kg-1for 226Ra, 38.5-52.2 Bq kg-1 for 232Th, and 502-707 Bq kg-1 for40K. The mean radium equivalent (Raeq), for the area under investigation, was 143±16 Bq kg-1, while the outdoor radiation hazard index (Hex) was 0.39. The total absorbed dose rate due to three primordial radionuclides investigated lay in the range 55.3 - 79.0 nGy h-1 with mean value of 68.1±7.7 nGy h-1, yielding a total annual effective dose of (83.5±9.5) µSv y-1. The assessed radiological factors were lower than the recommended values, indicating low radiological health risk for the population living and working in the investigated area. The activity concentrations of radionuclides in soil samples were compared to the international values reported by United Nations Scientific Committee on the Effects of Atomic Radiation and previous studies on geographically close areas and some worldwide regions. 


2020 ◽  
Vol 8 (E) ◽  
pp. 678-684
Author(s):  
M. R. Usikalu ◽  
C. A. Enemuwe ◽  
R. O. Morakinyo ◽  
M. M. Orosun ◽  
T. A. Adagunodo ◽  
...  

Natural radionuclides are present in every constituent of the environment. Monitoring of environmental radionuclides is very vital to avoid exposure above the threshold limit. Due to this, the background radiation from 238U, 232Th, and 40K of Bell University of Technology and Canaan Land City was determined from 20 sample points each in the two areas using RS230 Gamma Spectrometer. The mean activity concentration of 40K, 238U, and 232Th for Bells University of Technology was 442.66 Bq/kg, 41.98 Bq/kg, and 48.35 Bq/Kg, respectively. In Canaan City, mean activity concentration of 40K, 238U, and 232Th was 373.65 Bq/kg, 18.85 Bq/kg, and 67.22 Bq/kg, respectively. The mean absorbed dose rates recorded by the spectrometer directly were 70.03 nGy/h and 66.65 nGy/h, while that estimated from the activity concentration were 67.06 and 64.89 nGy/h for Bells University and Canaan City, respectively. The measured and estimated absorbed dose rates were higher than the safe limit of 57 nGy/h. The mean values of other radiological parameters estimated, except that of the gamma index and excess lifetime cancer risk were lower when compared to the recommended limit. It could be concluded that the possibility of suffering any radiation risk is low in these two areas, but there is possibility of cancer risk for someone that has stayed in the area for 70 years and above.


Author(s):  
O. B. Olafisoye ◽  
◽  
O. O. Oguntibeju ◽  
O. A. Osibote

Hyper Pure Germanium (HPGe) radiation detector was used to estimate the activity concentration of fifteen soil and palm oil samples collected from the oil palm plantations in the southwestern, southeastern, and south southern states of Nigeria, and the risk assessments was evaluated. The activity concentrations at a soil depth 0 – 15 cm ranged from 187.4 to 514.4, 2.328 to 6.571, and 1.509 to 6.121 Bq/kg for 40K, 238U, and 232Th, respectively. The activity concentrations at a soil depth 15 – 30 cm ranged from 163.4 to 3188.8, 1.345 to 9.410, and 1.476 to 6.275 Bq/kg for 40K, 238U, and 232Th, respectively. The activity concentrations in the palm oil ranged from 122.3 to 968.0, 1.240 to 6.651, and 1.199 to 8.061 Bq/L for 40K, 238U, and 232Th. For the risk assessments of surface soil samples, the absorbed dose rate (D) ranged from 5.09 to 24.54 nGy/h, while the annual effective dose equivalent (E) ranged from 0.612 × 10-2 to 16.49 × 10-2 mSv/y. The radium equivalent, gamma absorbed dose rate, and the annual effective dose rate in the palm oil samples ranged from 9.981 to 88.00 Bq/L, 4.315 to 46.29 nGy/h, and 0.53 × 10-2 to 56.90 x 10-2 mSv/y, respectively. The activity concentrations reported for soil and palm oil samples were lower than the recommended world average values given by UNSCEAR. Hence, the hazard and risk assessments indicated a low radiation risk within the studied areas.


2018 ◽  
Vol 31 (3) ◽  
pp. 43
Author(s):  
Heiyam Najy Hady ◽  
Shahad Fadel Kadim

   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  


2018 ◽  
Vol 53 (4) ◽  
pp. 265-278 ◽  
Author(s):  
S. Penabei ◽  
D. Bongue ◽  
P. Maleka ◽  
T. Dlamini ◽  
Saïdou ◽  
...  

In order to assess the levels of natural radioactivity and the associated radiological hazards in some building materials of the Mayo-Kebbi region (Chad), a total of nineteen samples were collected on the field. Using a high resolution γ-ray spectrometry system, the activity concentrations of radium (226Ra), thorium (232Th) and potassium (40K) in these samples have been determined. The measured average activity concentrations range from 0.56 ± 0.37 Bq kg−1 to 435 ± 7 Bq kg−1, 1.3 ± 0.6 Bq kg−1 to 50.6 ± 1.1 Bq kg−1 and 4.3 ± 2.0 Bq kg−1 to 840 ± 9 Bq kg−1, for 226Ra, 232Th and 40K, respectively. The highest 226Ra average activities is found in soil brick samples of Zabili. The highest mean value of 232Th and 40K concentrations are found in soil brick samples of Madajang. The activity concentration and the radium equivalent activity (Raeq) have been compared to other studies done elsewhere in the world. Their average values are lower than most of those of countries with which the comparison has been made. Were also evaluated, the external radiation hazard index, the internal radiation hazard index, the indoor air absorbed dose rate, the outdoor air absorbed dose rate, the activity utilization index, the annual effective dose, the annual gonadal dose equivalent, the representative level index, as well as, the excess lifetime cancer risk. In accordance with the criterion of the Organization for Economic Cooperation and Development, our results show that soil brick samples of Zabili and Madajang increases the risk of radiation exposure, thereby the possibility of developing cancer by people living in this environment. Based on these findings, brick samples from Zabili and Madajang are not recommended for construction purposes. All other sample materials have properties that are acceptable for use as building materials in terms of radiation hazard.


1989 ◽  
Vol 30 (2) ◽  
pp. 201-206 ◽  
Author(s):  
K. Geterud ◽  
A. Larsson ◽  
S. Mattsson

The radiation dose to patients and personnel was estimated during 11 percutaneous renal stone extractions. For the patients the energy imparted, the mean absorbed dose to various organs, and the effective dose equivalent were estimated. For different personnel categories some organ doses and the effective dose equivalent were also estimated. Large differences in the radiation dose between patients were observed. The mean effective dose equivalent to the patient was 4.2 (range 0.6–8.3) mSv, and the energy imparted 285 (range 50–500) mJ. These figures are comparable to those reported for routine colon examination and urography. For the personnel there were also large differences between individuals and categories. The highest radiation dose was received by the radiologist. It was estimated that a radiologist who performs 150 percutaneous renal stone extractions per year will receive a yearly contribution to his/her effective dose equivalent of 2.4 mSv. Even when the contribution from other diagnostic and interventional radiologic procedures is added, the total effective dose equivalent hardly exceeds 5 mSv or 1/10 of the present dose limit for persons engaged in radiologic work. For the hands of the radiologist there is a risk of doses closer to the present limit for single organs or tissues of 500 mSv/year.


2020 ◽  
Vol 15 (1) ◽  
pp. 107-118
Author(s):  
Daniel Hatungimana ◽  
Caner Taşköprü ◽  
Mutlu İçhedef ◽  
Müslim Murat Saç ◽  
Şemsi Yazıcı ◽  
...  

ABSTRACT The aim of this study is to determine the radon and natural radioactivity concentrations of some building materials and to assess the radiation hazard associated with those mortar materials when they are used in the construction of dwellings. Radon measurements were realized by using LR-115 Type 2 solid state nuclear track detectors. Radon activity concentrations of these materials were found to vary between 130.00 ± 11.40 and 1604.06 ± 40.5 Bq m−3. The natural radioactivity in selected mortar materials was analyzed by using scintillation gamma spectroscopy. The activity concentrations for 226Ra, 232Th and 40K for the studied mortar materials ranged from ND to 48.5 ± 7.0 Bq kg−1, ND to 41.0 ± 6.4 Bq kg−1 and ND to 720.4 ± 26.8 Bq kg−1, respectively. Radium equivalent activities, external and internal hazard indexes, gamma and alpha indexes and absorbed gamma dose rates were calculated to assess the radiation hazard of the natural radioactivity in studied samples. The calculated Raeq values of all samples were found to be lower than the limit of 370 Bq kg−1 set for building materials. The estimated hazard index values were found to be under the unity and the absorbed dose rate values were also below the worldwide average of 84 nGy h−1.


Symmetry ◽  
2018 ◽  
Vol 10 (12) ◽  
pp. 746 ◽  
Author(s):  
Saifeldin Siddeeg ◽  
Mohamed Suliman ◽  
Faouzi Ben Rebah ◽  
Wissem Mnif ◽  
Amel Ahmed ◽  
...  

Various commercially imported ceramic materials used in the building of Sudanese dwellings were examined in order to determine their natural radioactivity and radiological hazard parameters. In this context, twenty-five different consignments were sampled and analyzed using (3″ × 3″) sodium iodide gamma spectrometry system NaI(Tl). The identified average activity concentrations of 238U, 232Th, and 40K were 183 ± 70, 51 ± 44, and 238 ± 77 Bq/kg dry-weights, respectively. A positive correlation between 238U and 232Th in the investigated samples was identified from the observed significant correlation (R2 = 0.8). Interestingly, a low Th/U ratio (~0.3) was recorded, which could be related to the systematic loss of thorium during the fabrication process. The measured activity concentrations for these radionuclides were comparable with the reported data obtained from similar materials used in other countries showing similarity in ceramic materials used in buildings. Five different radiation indices, such as the average radium equivalent (Raeq), the absorbed dose rate (D), the annual effective dose equivalent (AEDE), the external hazard index (Hex), and the radioactivity level index (lγ), which indicate hazardous radiation, were estimated from these measurements. The obtained results revealed average values of 274 ± 106 Bq/kg, 125 ± 48 nGy/h, 1.23 ± 0.48 mSv/y, 0.74 ± 0.29, and 0.94 ± 0.37, for Raeq, D, AEDE, Hex, and lγ, respectively. The mean values of Raeq and Hex were in good agreement with the international limits, while the means of D and lγ were higher than the universal values. Calculated AEDE in about 60% of the samples exceeded the universal limit of 1 mSv/y for the public exposure (maximum value of 2.16 mSv/y). The investigated parameters were in the same range for the majority of imported samples; however, they were slightly higher than the locally produced ceramic, highlighting the importance of monitoring imported materials for their radioactivity contents.


This work was undertaken with the purpose of measuring natural radioactivity, due to 238U, 232Th and 40K in 30 soil samples collected from two hospitals in the governorate of (AL-Najaf), in Iraq. The samples were distributed (15) samples per hospital, and Radiation risks were also calculated for all soil samples. The natural radioactivity was measured using NaI (Tl) detector, the results of the specific activity at the Al Sadr Hospital were 238U ranged from (5.89±0.36 to 21.38±0.69) (Bq/kg) with average value 12.60±0.51 (Bq/kg). 232Th from (0.44±0.06 to 14.67±0.37) (Bq/kg) with average value (4.46±0.19) (Bq/kg), and 40K from (252.14±2.54 to 478.24±3.50) (Bq/kg) with average value (346.95±289) (Bq/kg). AL-Forat AL-Aosat hospital results were 238U ranged from (0.69±0.12 to 27.63±0.74) (Bq/kg) with average value (12.84±0.51) (Bq/kg), 232Th from (1.47±0.11 to 9.3±0.31 (Bq/kg) with average value 6.19±0.24 (Bq/kg), and 40K from (192.88±2.27 to 338.52±3.08) (Bq/kg) with average value (254.29±2.54) (Bq/kg). The radiation risks calculated, Radium Equivalent (Raeq), external Hazard index (Hex), absorbed dose rate (ADr), total Annual Effective Dose Equivalent (AEDE), and the Excess Life Cancer Risk (ELCR). The results were for Al Sadr Hospital (45.7063(Bq/kg), 0.1234, 23.0648(nGy/h), 0.0283(mSV/y), 1.247439702×10-3) respectively. For AL-Forat AL-Aosat hospital were (41.2655 (Bq/kg), 0.111, 20.3772 (nGy/h), 0.0250(mSV/y)`, 1.102083688×10-3) respectively. The results in the two hospitals were compared with the global allowable values ratio within the permissible ranges specified by UNSCER, OCDE, and ICRP; we concluded that all the sites in this study are safe.


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