# Assessment of Levels of Natural Radioactivity in Sand Samples Collected from Ekalakala in Machakos County, Kenya

Authors: Lucia Nyiva Munyao; Daniel Kipngetich Ketui; Calford Otieno; Margaret Wairimu Chege
Journal: The Scientific World Journal
 (2020)

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## Abstract

Construction sand is naturally polluted with radionuclides of terrestrial origin. In this study, specific activities of238U, 232Th, and 40K in 30 sand samples collected along the Ekalakala River, Machakos County, Kenya, were measured using a high-purity germanium γ-ray spectrometer. The specific activities ranged between 9.7 Bqkg−1 and 24.0 Bqkg−1, 11.5 Bqkg−1 and 26.2 Bqkg−1, and 820 Bqkg−1 and 1850 Bqkg−1 for 238U, 232Th, and 40K, respectively. While the mean specific activities for 238U and 232Th were less than half of the world average values of 33 Bqkg−1 and 45 Bqkg−1, respectively, the average specific activity of 40K was significant since it was three times the global mean value of 420 Bqkg−1. A calculated absorbed radiation dose rate for the sand varied between 46.8 nGyh−1 and 94.2 nGyh−1 with a mean of 68.5 ± 13.3 nGyh−1. This is not significantly different from the world average dose rate of 60 nGyh−1 for geological samples. The AEDR and Hex had maximum values of 0.29 mSvy−1 and 0.52, respectively, both within the recommended limits of radiation exposure for members of the general public. Based on these results, the sand from Ekalakala River does not pose significant health implication to the sand harvesters as well as the inhabitants of the houses constructed using this sand.


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## Body

## 1. Introduction

Sand mining is a well-known and booming economic activity in various regions of Kenya such as Machakos County [1]. This is as a result of the rapid economic expansion in most of the neighbouring cities and towns such as Nairobi, Thika, and Machakos, which has in turn resulted in an increased demand for the commodity in the construction industry. Sand is famously known as a construction material among other materials such as stones, gravel, and cement [2–4]. Just like any other type of geological materials, it naturally contains primordial radioactive nuclides 238U, 232Th, and 40K [5] which may not only contribute to external and internal radiation exposure to sand harvesters but also to the residents of the neighbouring towns. The risk posed by radiation exposure of terrestrial and extraterrestrial origin depends on, among other factors, the duration of exposure [6, 7]. Due to this, sand harvesters may be at a higher risk since they may be exposed to ionizing radiation both at work and in their homes. The risk also depends on the concentration of the primordial radionuclides [8] in the sand. Despite the continued harvesting and use of the construction sand from Ekalakala, there is no information about the radioactivity levels of the sand and possible health effects associated with continuous exposure of the sand harvesters as well as inhabitants of houses built using this sand. However, studies on construction sand obtained from other parts of Kenya have been carried out [5,9], and the values obtained are within the range of values obtained in this study. Moreover, comparison has been done on the values of 238U, 232Th, and 40K obtained in this study with other values obtained in Kenya [5,10,11] and different parts of the world [12–14] as shown in Figure 1. This study sought to fill the gap in determining the radiation exposure levels associated with construction sand from Ekalakala, by determining the specific activities of 238U, 232Th, and 40K in construction sand samples, evaluating the radiation absorbed dose rate as well as determining both the annual effective dose rate and the external hazard index. The results from this study seeks to provide knowledge and data on exposure levels associated with radionuclides in the construction sand and also avail the baseline information for future monitoring of the construction sand. They are as well vital in regulatory and advisory policy making for the public safety due to radiation exposure. Generally, this study acts as an eye opener to both the residents and local authorities to know that sand harvesting can attract more serious implications if not well monitored.Figure 1
Comparison of the specific activity of238U, 232Th, and 40K obtained in this study with values obtained in other parts of Kenya and the world. The specific activity of 40K has been scaled down by a factor of 10 for clear display of 238U and 232Th levels [5,10–15].


## 2. Materials and Methods

### 2.1. Study Area

Machakos County is in the former eastern province of Kenya, it ranges between latitudes 0° 45ʹ South and 1°31ʹ South and stretches along longitudes 36°45ʹ East to 37°45ʹ East. Its altitude is 1000–1600 metres above sea level. It covers an area of 6,208 km2 and has a population of 1,098,584 with 264,500 [16] households. Sand samples were collected along Ekalakala River through the Isyukoni village eight kilometers from the Ekalakala market (Figure 2). Ekalakala River originates from the Aberdares forest and has several names from its origin. In Kiambu County, River Thika combines with River Sagana to form River Chania in Thika which in turn stretches to River Ianguni in Machakos County and then to Ekalakala River which pours its waters into Masinga dam.Figure 2
Location of sampling sites along Ekalakala River.


### 2.2. Sample Collection and Preparation

A total of 30 sand samples each of mass 500 g were collected using a hand trowel into clean plastic containers. 15 of the samples were collected from depths of between 0 m and 0.3 m. Another set of 15 samples were collected directly beneath the first set at depths of between 0.3 m and 0.5 m. All samples were prepared for analysis at the Institute of Nuclear Science and Technology (INST), University of Nairobi, Kenya. In the laboratory, each sample was sieved so as to get rid of any unwanted materials including vegetation, stones, and debris. The samples were totally dried in an oven at 105°C for a day until a uniform weight was attained [4,17,18] so as to fully get rid of any water content. Dry sand was thereafter crushed and pulverized to uniformity, and then it was sieved using a 2 mm mesh sieve. 300 g of each sample was measured and put in standard gas tight plastic containers. The caps of these containers were carefully lined using an aluminium foil before sealing so as to ensure that 222Rn does not escape. Dimensions of the containers as well as the mass of the samples were similar to the IAEA reference used for efficiency calibration. All the containers were carefully labeled and stored in a cool dry place for a period of 30 days after which radioactivity was measured. This allowed radionuclides 238U and 232Th, radon and thoron, and short-lived radon and thoron progeny to attain secular equilibrium with each other [19,20].


## 2.1. Study Area

Machakos County is in the former eastern province of Kenya, it ranges between latitudes 0° 45ʹ South and 1°31ʹ South and stretches along longitudes 36°45ʹ East to 37°45ʹ East. Its altitude is 1000–1600 metres above sea level. It covers an area of 6,208 km2 and has a population of 1,098,584 with 264,500 [16] households. Sand samples were collected along Ekalakala River through the Isyukoni village eight kilometers from the Ekalakala market (Figure 2). Ekalakala River originates from the Aberdares forest and has several names from its origin. In Kiambu County, River Thika combines with River Sagana to form River Chania in Thika which in turn stretches to River Ianguni in Machakos County and then to Ekalakala River which pours its waters into Masinga dam.Figure 2
Location of sampling sites along Ekalakala River.


## 2.2. Sample Collection and Preparation

A total of 30 sand samples each of mass 500 g were collected using a hand trowel into clean plastic containers. 15 of the samples were collected from depths of between 0 m and 0.3 m. Another set of 15 samples were collected directly beneath the first set at depths of between 0.3 m and 0.5 m. All samples were prepared for analysis at the Institute of Nuclear Science and Technology (INST), University of Nairobi, Kenya. In the laboratory, each sample was sieved so as to get rid of any unwanted materials including vegetation, stones, and debris. The samples were totally dried in an oven at 105°C for a day until a uniform weight was attained [4,17,18] so as to fully get rid of any water content. Dry sand was thereafter crushed and pulverized to uniformity, and then it was sieved using a 2 mm mesh sieve. 300 g of each sample was measured and put in standard gas tight plastic containers. The caps of these containers were carefully lined using an aluminium foil before sealing so as to ensure that 222Rn does not escape. Dimensions of the containers as well as the mass of the samples were similar to the IAEA reference used for efficiency calibration. All the containers were carefully labeled and stored in a cool dry place for a period of 30 days after which radioactivity was measured. This allowed radionuclides 238U and 232Th, radon and thoron, and short-lived radon and thoron progeny to attain secular equilibrium with each other [19,20].


## 3. Experimental Techniques

### 3.1. Radioactivity Measurement

For the detection of radioactivity in the sand samples, a high-purity germaniumγ-ray detector, model number CPVD530–3018 SN 2489, was used. It was vertically mounted and stored in a 10 cm thick cylindrical lead shield which helped to lower the environmental background radiation. It was cooled using liquid nitrogen. The detector used is coaxial with a diameter of 57.4 mm, a length of 56.9 mm, and a volume of 144 cm3. It was connected to an uninterrupted power supply and operated at 3200 volts. It had 31.6% detection efficiency and a detector resolution (FWHM) of 1.8 keV at the 1.33 MeV of 60Co. Energy calibration of the detector was done using gamma energies 1330 keV and 1170 keV from 60Co and 60 keV from 241Am, while efficiency calibration was done using certified reference materials: RGU-1, RGTh-1, RGK-1, and IAEA soil 375. Samples were run for 36,000 seconds (10 hours), time considered adequate for counting sample radionuclide activity for each sample. 232Th specific activity was determined from the net intensity of radiation from energy photo peaks 238 keV of 212Pb and 911 keV of 228Ac. 238U was obtained from the 352 keV line of 214Pb and 609 keV of 214Bi. Finally, for 40K, it was obtained from its own gamma line of 1460 keV [21]. Specific activity (C) in Bqkg−1 was calculated using the following equation [22,23]:(1)C=AEρ×γ×T×MS,where A (count/s) is the net area under the photopeak for each sample, Eρ is the detection efficiency at a specific gamma energy, T (s) is the counting time, MS (kg) is the mass of samples, and γ is the gamma yield at a specific gamma energy. The lowest limits of detection in Bqkg−1 of the detector used were 4.1, 4.6, and 43.9 for 238U, 232Th, and 40K, respectively.


### 3.2. Absorbed Dose Rate Calculation

Dose rate is the dose of ionising radiation per unit time. The SI unit is gray per hour (Gyh−1). It was determined using the following formula [24]:(2)D˙=0.427CU+0.622CTh+0.0432CK,where CU, CTh, and CK are the specific activity in Bqkg−1 of 238U, 232Th, and 40 K, respectively, in the sand samples. 0.427, 0.662, and 0.043 are the dose conversion factors that convert the specific activity of 238U, 232Th, and 40 K into dose.


### 3.3. Annual Effective Dose Rate Calculation

AEDR is the equivalent biological effect representing the deposit of a joule of radiation energy per kilogram of a human body in a year. It was obtained by making use of the following equations [15,25–27]:(3)indoor AEDR=D˙×8760×0.7×0.6×10−6,(4)outdoor AEDR=D˙×8760×0.7×0.4×10−6,where D˙ is the dose rate, 8760 are the hours in a year, 0.7 SvGy−1 is the conversion coefficient that changes absorbed dose in the air to the effective dose, and 10−6 is a factor that converts nano into milli [22,28]. Finally, 0.6 and 0.4 are the estimated average indoor and outdoor occupancy factors in Kenya [5,7,29]. This takes into account the fact that Kenyans spent 40% of their time outside because the weather is favourable and 60% of their time is spent indoors. The SI unit of annual effective dose rate is mSvy−1.


### 3.4. External Hazard Index

The external hazard index resulting from exposure to gamma rays is determined by [30](5)Hex=CU370+CTh259+CK4910,where CU, CTh, and CK are the values of specific activity (BqKg−1) of 238U, 232Th, and 40K radionuclides, respectively. The value of this index should be lower than one. Values above unity make the hazard unacceptable to members of the general public [31].


## 3.1. Radioactivity Measurement

For the detection of radioactivity in the sand samples, a high-purity germaniumγ-ray detector, model number CPVD530–3018 SN 2489, was used. It was vertically mounted and stored in a 10 cm thick cylindrical lead shield which helped to lower the environmental background radiation. It was cooled using liquid nitrogen. The detector used is coaxial with a diameter of 57.4 mm, a length of 56.9 mm, and a volume of 144 cm3. It was connected to an uninterrupted power supply and operated at 3200 volts. It had 31.6% detection efficiency and a detector resolution (FWHM) of 1.8 keV at the 1.33 MeV of 60Co. Energy calibration of the detector was done using gamma energies 1330 keV and 1170 keV from 60Co and 60 keV from 241Am, while efficiency calibration was done using certified reference materials: RGU-1, RGTh-1, RGK-1, and IAEA soil 375. Samples were run for 36,000 seconds (10 hours), time considered adequate for counting sample radionuclide activity for each sample. 232Th specific activity was determined from the net intensity of radiation from energy photo peaks 238 keV of 212Pb and 911 keV of 228Ac. 238U was obtained from the 352 keV line of 214Pb and 609 keV of 214Bi. Finally, for 40K, it was obtained from its own gamma line of 1460 keV [21]. Specific activity (C) in Bqkg−1 was calculated using the following equation [22,23]:(1)C=AEρ×γ×T×MS,where A (count/s) is the net area under the photopeak for each sample, Eρ is the detection efficiency at a specific gamma energy, T (s) is the counting time, MS (kg) is the mass of samples, and γ is the gamma yield at a specific gamma energy. The lowest limits of detection in Bqkg−1 of the detector used were 4.1, 4.6, and 43.9 for 238U, 232Th, and 40K, respectively.


## 3.2. Absorbed Dose Rate Calculation

Dose rate is the dose of ionising radiation per unit time. The SI unit is gray per hour (Gyh−1). It was determined using the following formula [24]:(2)D˙=0.427CU+0.622CTh+0.0432CK,where CU, CTh, and CK are the specific activity in Bqkg−1 of 238U, 232Th, and 40 K, respectively, in the sand samples. 0.427, 0.662, and 0.043 are the dose conversion factors that convert the specific activity of 238U, 232Th, and 40 K into dose.


## 3.3. Annual Effective Dose Rate Calculation

AEDR is the equivalent biological effect representing the deposit of a joule of radiation energy per kilogram of a human body in a year. It was obtained by making use of the following equations [15,25–27]:(3)indoor AEDR=D˙×8760×0.7×0.6×10−6,(4)outdoor AEDR=D˙×8760×0.7×0.4×10−6,where D˙ is the dose rate, 8760 are the hours in a year, 0.7 SvGy−1 is the conversion coefficient that changes absorbed dose in the air to the effective dose, and 10−6 is a factor that converts nano into milli [22,28]. Finally, 0.6 and 0.4 are the estimated average indoor and outdoor occupancy factors in Kenya [5,7,29]. This takes into account the fact that Kenyans spent 40% of their time outside because the weather is favourable and 60% of their time is spent indoors. The SI unit of annual effective dose rate is mSvy−1.


## 3.4. External Hazard Index

The external hazard index resulting from exposure to gamma rays is determined by [30](5)Hex=CU370+CTh259+CK4910,where CU, CTh, and CK are the values of specific activity (BqKg−1) of 238U, 232Th, and 40K radionuclides, respectively. The value of this index should be lower than one. Values above unity make the hazard unacceptable to members of the general public [31].


## 4. Results and Discussion

Primordial radionuclides238U, 232Th, and 40K were identified in the 30 sand samples. Values of standard deviation of the corresponding averages have been expressed as errors in all tables. The maximum value of 238U for samples collected between 0 m and 0.3 m was 25.2 ± 0.8 Bqkg−1, while the minimum value was 7.9 ± 3 Bqkg−1 with a mean of 13.6 ± 4.8 Bqkg−1 as shown column 2 in Table 1. For sand samples obtained between 0.3 m and 0.5 m, the specific activity ranged from 9.5 ± 0.8 Bqkg−1 to 22.7 ± 1 Bqkg−1 with an overall value of 14.9 ± 3.6 Bqkg−1 as indicated in Table 1 (column 3). Though the mean specific activity of 238U for sand samples collected at a depth of 0.3 m–0.5 m was higher than that collected at a depth of 0 m–0.3 m, there was an insignificant difference existing between the two sets of data. Further comparison of the specific activity of 238U with depth is displayed in Figure 3(a).Table 1
Specific activity in Bqkg−1 for 238U in sand samples collected at depths 0 m–0.3 m and 0.3 m–0.5 m from Ekalakala River.
Sample
Specific activity (Bqkg−1)
0 m–0.3 m
0.3 m–0.5 m
1
14 ± 1.4
16 ± 5.0
2
15 ± 1.5
12 ± 0.6
3
11.0 ± 0.6
9.5 ± 0.8
4
11.7 ± 0.1
13.4 ± 2.1
5
13.2 ± 0.1
19.9 ± 0.8
6
8.6 ± 1.0
10.7 ± 0.3
7
9.2 ± 0.8
13.3 ± 2.0
8
21.3 ± 1.3
19.4 ± 1.1
9
19.4 ± 0.6
16 ± 3.3
10
7.9 ± 3.0
13 ± 0.5
11
11.2 ± 0.2
17.4 ± 0.1
12
25.2 ± 0.8
22.7 ± 1.0
13
15.7 ± 0.3
12.2 ± 0.2
14
10.3 ± 0.8
13.6 ± 0.4
15
10.4 ± 1.1
15 ± 1.2
Minimum
7.9 ± 3.0
9.5 ± 0.8
Maximum
25.2 ± 0.8
22.7 ± 1.0
Mean
13.6 ± 4.8
14.9 ± 3.6Figure 3
Comparison of the distribution of (a)238U, (b) 232Th, and (c) 40K radionuclides for sand samples collected at a depth of 0 m and 0.3 m and those collected at a depth ranging from 0.3 m to 0.5 m.
(a)
(b)
(c)Specific activity of232Th for sand samples collected at a depth of 0 m–0.3 m in Bqkg−1 ranged between 11.1 ± 3.1 and 28.5 ± 3.7 with an average of 16.8 ± 4.4 which is slightly lower than the average activity of the same radionuclide obtained for samples collected at a depth ranging between 0.3 m and 0.5 m as indicated in Table 2. The maximum specific activity of sand samples collected at a depth of 0.3 m–0.5 m in Bqkg−1 was 29.9 ± 1.4 with a minimum of 9.95 ± 2.1 and an average of 17.8 ± 4 as indicated in Table 2 (column 3). Distribution of 232Th at various sampling points is displayed in Figure 3(b). The difference existing between the specific activity of 232Th for sand samples obtained from a depth of 0 m–0.3 m and those collected at a depth of 0.3 m–0.5 m was found to be insignificant.Table 2
Specific activity of232Th present in sand samples collected at depths of 0 m–0.3 m and 0.3 m–0.5 m from Ekalakala River.
Sample
Specific activity (Bqkg−1)
0 m–0.3 m
0.3 m–0.5 m
1
15.9 ± 1.7
21.1 ± 2.8
2
17.1 ± 1.1
15.1 ± 0.9
3
13.7 ± 0.8
10.1 ± 0.5
4
16.9 ± 2.1
19.0 ± 2.2
5
25.5 ± 2.3
29.9 ± 1.4
6
13.1 ± 2.5
9.95 ± 2.1
7
14.1 ± 4.1
16.7 ± 4.4
8
17.2 ± 2.7
22.0 ± 2.4
9
20.3 ± 0.3
18.5 ± 3.8
10
12.8 ± 2.4
14.7 ± 1.3
11
11.1 ± 3.1
14.9 ± 0.9
12
28.5 ± 3.7
23.3 ± 5.5
13
20.2 ± 4.8
17.1 ± 2.9
14
14.5 ± 2.4
17.5 ± 0.4
15
14.5 ± 1.9
17.0 ± 1.1
Minimum
11.1 ± 3.1
9.95 ± 2.1
Maximum
28.5 ± 3.7
29.9 ± 1.4
Mean
16.8 ± 4.4
17.8 ± 4.9For40K, the specific activity of samples collected between 0 m and 0.3 m ranged between 800 ± 60 Bqkg−1 and 1880 ± 30 Bqkg−1 with a mean value of 1300 ± 300 Bqkg−1 as indicated in Table 3 (column 2). The measured activity for sand samples collected at a depth of 0.3 m–0.5 m ranged between 840 ± 70 Bqkg−1 and 1800 ± 50 Bqkg−1 with a mean of 1300 ± 300 Bqkg−1 as indicated in Table 3 (column 3). The difference existing between the two sets of data is insignificant. The distribution of 40K at various sampling depths has been displayed in Figure 3(c).Table 3
Specific activity of the40K radionuclide in sand samples collected at depths 0 m–0.3 m and 0.3 m–0.4 m from Ekalakala River.
Sample
Specific activity (Bqkg−1)
0 m–0.3 m
0.3 m–0.5 m
1
1270 ± 70
1460 ± 60
2
1370 ± 50
1300 ± 40
3
1190 ± 40
1380 ± 70
4
1100 ± 40
990 ± 50
5
1410 ± 60
1500 ± 70
6
800 ± 60
840 ± 70
7
1880 ± 30
1800 ± 50
8
1340 ± 80
1440 ± 40
9
1320 ± 30
1450 ± 50
10
900 ± 60
970 ± 60
11
1060 ± 40
1170 ± 50
12
1680 ± 60
1790 ± 70
13
1360 ± 50
1310 ± 60
14
1360 ± 30
1310 ± 70
15
1200 ± 60
1280 ± 70
Minimum
800 ± 60
840 ± 70
Maximum
1880 ± 30
1800 ± 50
Mean
1300 ± 300
1300 ± 300The average specific activities in Bqkg−1 for the samples collected at the depths of 0 m–0.3 m and 0.3 m–0.5 m are shown in Table 4 and summarized in Figure 4. The overall mean activity for the data in this table was calculated to be 14.3 ± 3.8, 17.3 ± 4.2, and 1300 ± 300 for 238U, 232Th, and 40K, respectively. However, the specific activity of 40K obtained in this study is higher than the global mean value of 420Bqkg−1 [15].Table 4
Average specific activity of238U, 232Th, and 40K calculated from sand samples collected at depths of 0 m–0.3 m and 0.3 m–0.5 m from Ekalakala River.
Sample
Specific activity (Bqkg−1)
238U
232Th
40K
1
15.0 ± 1.0
18.5 ± 2.6
1370 ± 90
2
13.5 ± 1.5
16.1 ± 1.0
1340 ± 30
3
10.2 ± 0.7
11.9 ± 1.8
1290 ± 100
4
12.6 ± 0.9
18.0 ± 1.1
1040 ± 60
5
16.6 ± 3.4
26.2 ± 3.7
1470 ± 60
6
9.7 ± 1.1
11.5 ± 1.6
820 ± 20
7
11.3 ± 2.1
15.4 ± 1.3
1850 ± 40
8
20.4 ± 1.0
19.6 ± 2.4
1390 ± 50
9
17.7 ± 1.7
19.4 ± 0.9
1380 ± 70
10
10.5 ± 2.6
13.8 ± 1.0
930 ± 30
11
14.3 ± 3.1
13.0 ± 2.0
1120 ± 50
12
24.0 ± 1.3
25.9 ± 2.6
1740 ± 50
13
14.0 ± 1.8
18.6 ± 1.6
1340 ± 30
14
12.0 ± 1.7
16.0 ± 1.5
1330 ± 30
15
12.7 ± 2.3
15.7 ± 1.3
1240 ± 40
Range
9.7–24.0
11.5–26.2
820–1850
Mean
14.3 ± 3.8
17.3 ± 4.2
1300 ± 300
World mean
33
45
420Figure 4
Distribution of (a)238U, (b) 232Th, and (c) 40K in different sampling points.
(a)
(b)
(c)This high value is attributed to the use of phosphate fertilizers for agriculture done on the upper parts of the river. Fertilizers are known to increase the concentration of40K [25, 32]. It might as well be attributed to the fact that 40K is the most abundant radionuclide and is found in the earth’s crust on an average of 2.6% [33]. Comparison of values of specific activity due to primordial radionuclides obtained in this study with values obtained nationally and internationally (Figure 1) indicates highest values of 40K activity followed by 232Th and 238U, that is, 40K > 232Th > 238U, except for [5, 11] whose data indicate slightly higher values of 232Th than those of 238U even though the values of 40K are highest in both cases.The percentage contribution of each radionuclide is indicated in Figure5, which shows 97.7% of 40K, 1.26% of 232Th, and 1.07% of 238U which is in close agreement to values obtained in [34].Figure 5
Percentage contribution of individual radionuclides to the average specific activity.From Figure1, the specific activity of 40K reported in this study is lower than values reported in Narok, Kenya [10], but higher than the global average value [15] and values reported in other parts of the world [5, 11–14]. 238U recorded in this study is lower than the worldwide mean [15] and values obtained in [5, 10, 13, 14] but higher than values reported in [11, 12].Specific activity of232Th obtained in the present study is lower than the worldwide average [15] as well as values recorded in [5, 10, 13, 14] but higher than values reported in [11, 12].Correlation analysis performed between specific activities of238U, 232Th, and 40K revealed that they all had a positive correlation with each other as shown in Table 5. This shows a strong degree of closeness among different radionuclides. It further implies that knowing the specific activity of one radionuclide can help in predicting the specific activity of the other radionuclide of interest in the study area.Table 5
Correlation matrix table for the specific activities of238U, 232Th, and 40K.
238U
232Th
40K
238U
1
232Th
0.8133
1
40K
0.5302
0.5760
1Regression plots showing the correlation between the three radionuclides are displayed in Figure6. 232Th has a strong positive correlation with 238U (r = 0.81). However, a relatively strong positive correlation is evident between the specific activities of 40K and 238U (r = 0.53) and between the specific activities of 40K and 232Th (r = 0.58). This could possibly be due to the fact that radionuclides originate from the same rock formation.Figure 6
Regression plots showing the correlation between (a)238U and 232Th, (b) 232Th and 40K, and (c) 238U versus 40K in sand samples analysed.
(a)
(b)
(c)The total absorbed dose rate (nGyh−1) due to terrestrial gamma radiation was calculated from the mean specific activity of 238U, 232Th, and 40K in the sand samples using equation (2). The dose rate ranged between 46.8 nGyh−1 and 94.2 nGyh−1 with a mean value of 68.5 ± 13.3 nGyh−1, as indicated in Table 6 (column 2). The values obtained have been compared to values obtained in different parts of the world (Figure 7(a)).Table 6
Dose rate (nGyh−1), external hazard index, and 238U/232Th ratio for sand samples collected from Ekalakala River.
Sample
Dose (nGyh−1)
Hex
238U/232Th
1
76.9
0.39
0.81
2
73.5
0.37
0.84
3
67.4
0.34
0.86
4
61.6
0.32
0.7
5
86.9
0.45
0.63
6
46.8
0.24
0.84
7
94.2
0.47
0.73
8
80.9
0.41
1.04
9
79.3
0.40
0.91
10
53.4
0.27
0.76
11
62.4
0.32
1.1
12
75.0
0.52
0.93
13
57.8
0.38
0.75
14
57.6
0.37
0.75
15
53.5
0.35
0.81
Maximum
94.2
0.52
1.1
Minimum
46.8
0.24
0.63
Average
68.5 ± 13.3
0.37 ± 0.07
0.83 ± 0.12Figure 7
Comparison of the average (a) AEDR and (b)Hex obtained in this study with world average values and values obtained in other parts of the world [5, 9, 10, 15, 33, 35–37].
(a)
(b)The AEDR due to indoor and outdoor exposure was determined from equations (3) and (4). The mean indoor AEDR is 0.25 mSvy−1, while the average outdoor AEDR is 0.17 mSvy−1 as indicated in columns 2 and 3 in Table 7, respectively. The total AEDR varied from 0.29 mSvy−1 to 0.14 mSvy−1 with a mean of 0.23 ± 0.04 mSvy−1 as in column 4 in Table 7 and in Figure 8.Table 7
Indoor, outdoor, and average annual effective dose rate (mSvy−1) for sand samples collected at Ekalakala River.
Sample
Indoor AEDR (mSvy−1)
Outdoor AEDR (mSvy−1)
Total AEDR (mSvy−1)
1
0.28
0.19
0.24
2
0.27
0.18
0.23
3
0.25
0.17
0.21
4
0.23
0.15
0.19
5
0.32
0.21
0.27
6
0.17
0.11
0.14
7
0.35
0.23
0.29
8
0.30
0.20
0.25
9
0.29
0.19
0.24
10
0.2
0.13
0.16
11
0.23
0.15
0.19
12
0.28
0.18
0.23
13
0.21
0.14
0.18
14
0.21
0.14
0.18
15
0.20
0.13
0.16
Maximum
0.35
0.23
0.29
Minimum
0.17
0.11
0.14
Average
0.25 ± 0.05
0.17 ± 0.03
0.21 ± 0.04Figure 8
Comparison of the indoor and outdoor AEDR for all the sand samples.The average value obtained is lower than the recommended safety limit of 1 mSvy−1 for members of the general public. From a radiological point of view, this implies that the dose emitted from natural gamma does not pose any significant health implication to the sand harvesters as well as the inhabitants of the houses constructed using this sand. The 238U/232Th ratio is less than one as shown in Table 6 (column 4). This can be explained by the high solubility of uranium ions as compared to thorium ions which are slightly soluble.TheHex index, as calculated from equation (5), has a maximum value of 0.52, while the minimum value is 0.24 with a mean of 0.37, as indicated in column 3 in Table 6. These values have been compared to values obtained in Kenya and other parts of the world as displayed in Figure 7(b). Since the Hex index is less than the global permissible limit of unity, the radiation hazard posed is negligible. This implies that the construction sand from Ekalakala may be considered safe for use by members of the general public.


## 5. Conclusion

The levels of natural radioactivity in sand samples collected from Ekalakala River, Machakos County, Kenya, have been assessed using an HPGe detector. The mean values of specific activity in Bqkg−1 are indicated in Table 4. The maximum specific activity of 238U and 232Th is 24.0 ± 1.3 Bqkg−1 and 26.2 ± 3.7 Bqkg−1, respectively, which is below the set values of 33 Bqkg−1 and 45 Bqkg−1, respectively. The maximum value of the specific activity of 40K reported is 1850 ± 40 Bqkg−1 which is higher than the worldwide mean value of 420 Bqkg−1. The average dose rate of 68.5 ± 13.3 nGyh−1 is slightly higher than the worldwide average value. The average indoor and outdoor AEDR was reported, and the values obtained were 0.25 ± 0.05 mSvy−1 and 0.17 ± 0.03 mSvy−1, respectively. The total AEDR due to indoor and outdoor exposure to gamma radiation is 0.21 mSvy−1, which is lower than the recommended safety limit of 1 mSvy−1. The Hex index was also reported. This value was below the set limit of unity. The construction sand from Ekalakala River poses an insignificant health risk to members of the general public. These results can be of great use by the relevant governmental organizations in coming up with suitable policies on radiation protection and control. It can as well be used as reference data in future to monitor possible radioactivity pollution from the construction sand from Ekalakala River.



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*Source: 7269840-2020-05-05.xml*