The concentrations of natural radioactivity were measured in igneous rock samples collected from Albaha region in the south west of Saudi Arabia. A high purity germanium (HPGe) detector was used for analysis. The average activity concentrations for
226Ra,
232Th and
40K were 35, 31.52 and 843.63 Bq kg
−1, respectively. The average absorbed dose rate was 70.86 nGy
⋅h
−1 with a corresponding average annual effective dose 0.09 mSv
⋅y
−1. The average radium equivalent activity value was 145.84 Bq
⋅kg
−1, lower than the international limit 370 Bq
⋅kg
−1. The external and internal indices average values were 0.39 and 0.49, respectively. The average results obtained in this study are lower than the average national and world recommended values, therefore, there is no health risk to the populace of the area. This study provides a baseline map of background radioactivity levels in the Saudi environment and will be used as reference information to assess any changes in the level background due to geological processes.
Natural Radioactivity Radium Thorium and Potassium Concentrations Hazard Index1. Introduction
The importance of this study is based on the igneous rocks. These rocks are divided into different types: the melting of solid rock and the crystallization of molten rock. Some igneous rocks such as granite and basalt have other purposes in industries and commercials due to their high clay mineral element. Therefore, the radioactive contents of various radionuclides in rocks may play an important role in health conditions and geoscientific research. These radionuclides create risk exposure both externally and internally due to their gamma-ray emissions, their radon and progenies. The main natural contributor to external exposure is from the original radionuclides, such as 40K, and the radionuclides from 238U and 232Th series and their decay materials [1] . Conducting an assessment, the activity of these radionuclides in the environmental samples is necessary to control the radiation levels [2] . The radioactive elements of various radionuclides in rocks may affect the health. Thus, numerous studies have been performed in many regions of the world, and the obtained data can be used to establish if the local controls are needed [3] - [10] . The major objective of this work is to estimate the radiological effects of the specific activities of 226Ra, 232Th and 40K in some rock samples collected from a part of the south west in Saudi Arabia (Albaha region). According to a literature survey, there are no previous data for the rock activities in the studied region. The present data are of great interest in the environmental radiation protection study and may be helpful as a baseline in making estimations of population’s exposure in Saudi Arabia. These results are useful, since these types of rocks are available in the building and ornamental materials.
Description of Study Area
This study was carried out in Albaha region in the south west of Saudi Arabia. This region lies on Longitude 41˚E, 42˚E and Latitude 19˚N, 20˚N. It is the smallest of the Kingdom’s provinces (11,000 square km) and has a population of 533,001. This specific region has been chosen for this study due to its rocky location where there is a variety of igneous rocks used as building materials. In addition, no previous significant work about radioactivity has been done. The studied area was illustrated in Figure 1.
2. Material and Methods2.1. Samples
Thirty igneous rock samples have been collected randomly from various locations in Albaha region, southwestern part of Saudi Arabia. In the laboratory the rocks were crushed and pulverized to a uniform mixture, dried in an oven at 110˚C and sieved to a particulate size of about 2 mm. About 500 mg of powder
Location map of the study area
samples were filled with Polyethylene containers, sealed for four weeks before measurement to reach secular equilibrium between 226Ra and 232Th and their decay products [11] .
2.2. Measurements
The gamma-rays emitted by the rock samples were measured by using High Purity Germanium (HPGe) detector gamma-ray spectrometry system of 1.85 keV resolution and 25% relative efficiency with coaxial-type vertical dipstick cryostat. It is surrounded by lead and copper, which provides an efficient suppression of background gamma radiation present at the laboratory. The system has a resolution (FWHM) of (3.0 - 3.5 keV) for 1332.5 keV gamma-ray peak of 60Co and a peak to a Compton ratio of 41:1. The spectra were analyzed by commercially available software GE-NIE-2000 obtained from Canberra, USA. Counting of samples and background was done for 36,000s duration. The activity concentration for 226Ra was determined by using the average obtained by gamma peaks at 351.87 keV, 295.09 (214 Pb) and 609.31 keV, 1120.27 keV, 1764.49 keV (214Bi), while 232Th from gamma peaks 238.63 keV (212 Pb) and 911.21 keV (228Ac), finally, 40K from 1460 keV gamma peak. The radioactivity concentrations of 226Ra, 232Th, and 40K in the environmental samples were calculated using the following relation [10] [11] [12] :
where A is the activity concentration in Bq∙kg−1, NC is the net gamma counting rate (counts per second), ε the detector efficiency of the definite Gamma-ray, γ is the absolute transition probability of Gamma-decay and m the mass of the sample (kg).
2.3. Calculations
The radium equivalent activity of the granite samples was calculated by using the formula [1] [11] [12] :
where ARa, ATh and Ak are the activity concentrations of 226Ra, 232Th and 40K, respectively. This formula is based on the assumption that 370 Bq∙kg−1 of 226 Ra, 259 Bq∙kg−1 of 232Th and 481 Bq∙kg−1 of 40K produce the same gamma-ray dose rate [13] . A value of 370 Bq∙kg−1 corresponds to 1 mSv∙y−1.
The external hazard index (Hex) is a radiation hazard index defined by [14] . This index value must be less than unity to keep the radiation hazard insignificant, i.e., the radiation exposure due to the radioactivity of construction materials to be limited to 1.5 mSv∙years−1 [15] , based on the formula [14] :
In order to address the radiation hazard to respiratory organs due to 222Rn and its radiation hazard to respiratory organs due to 222Rn and its progeny, the internal hazard index Hin which is given by [14] :
where ARa, ATh and Ak are the activity concentrations of 226Ra, 232Th and 40K, respectively. For safe, use of a material in the construction of dwellings, Hex and Hin should be less than unity [16] .
The total air absorbed dose rate (nGy∙h−1) due to the activity concentrations of 238U, 232Th, and 40K (Bq/kg) can be calculated using the activity concentration (in Bq∙kg−1) of 40K(AK),226Ra (ARa) and 232Th (ATh) substituted into the formula [1] :-
The annual effective dose equivalent (AEDE) was calculated from the absorbed dose by applying the dose conversion factor of 0.7 SvG∙y−1 with an outdoor occupancy factor of 0.2 [1] :
3. Results and Discussion
Table 1 shows the values of activity concentration of 226Ra, 232Th and 40K and the corresponding radiological hazards were obtained from thirty rock samples collected from Albaha region in the South west of Saudi Arabia. From this Table, it can be seen that the activity concentrations of 40K varied between 124.19 Bq∙kg−1 in sample (R9) to 2353.19 Bq∙kg−1 in sample (R27) with a mean value of 843.63 Bq∙kg−1. 226Ra concentrations varied from 7.39 Bq∙kg−1 in sample (R21) to 82.85 Bq∙kg−1 in sample (R27) with a mean of 35 Bq∙kg−1. The concentrations of 232Th varied from 12.09 Bq∙kg−1 in sample (R15) to 82.96 Bq∙kg−1 in sample (R7) with a mean value of 31.52 Bq∙kg−1. The mean activity concentration values for 226Ra and, 232Th were lower than the recommended radioactivity levels of 50, 50 as reported by UNSCEAR 2000, while 40K mean concentration was found to be greater than the global value 500 Bq∙kg−1. The variations of natural radioactivity levels in different samples are due to the variation of concentrations of these elements in the geological formations. The high activity concentration of 40K in some rock samples may be attributed to the presence of relatively increased amount of accessory minerals such as zircon, iron oxides, fluorite and other radioactive related minerals [17] [18] . In general, Potassium-40 is usually of limited interest because it is an isotope of an essential element, controlled in the human cells [19] . However, the 40K mean value of this study is still more below the rigid control 100,000 Bq∙kg−1 as given by IAEA [20] . So, the present results indicated that, the activity concentrations in the rock samples are quite uniform and do not show any considerable variation. Figure 2 shows the activity concentration of uranium, potassium and radium in the collected samples. Figure 3(a) and Figure 3(b) show that there is a good linear correlation (R2 = 0.80 and 0.83) between the activity concentration of Ra, Th and Ra, K, respectively. Table 1 summarized the results of the hazard parameters as the following:-
The values of Raeq for all samples range from 53.72 to 339.36 Bq∙kg−1 with a mean value145.84 Bq∙kg−1. These obtained values were below the recommended maximum value of 370 Bq∙kg−1, which is equivalent to an external dose of 1.5
Values of radioactivity concentrations and radiation hazard parameters for rock samples under investigation
Sample code
Activity concentrations (Bq/kg)
Radium-equivalent (Bq/kg)
External index (Hex)
Internal index (Hin)
Absorbed dose(D) (nGy/h)
Annual effective dose (AEDE) (mSv∙y-1)
226Ra
232Th
40K
R1
20.54
17.77
522.72
86.20
0.23
0.29
42.32
0.052
R2
41.84
23.57
541.15
117.21
0.32
0.43
55.82
0.068
R3
37.12
25.69
896.81
142.91
0.39
0.49
70.42
0.086
R4
36.02
21.76
403.56
98.21
0.27
0.36
46.29
0.057
R5
53.98
38.06
829.31
172.26
0.47
0.61
82.42
0.101
R6
35.23
24.86
699.51
124.64
0.34
0.43
60.61
0.074
R7
76.64
82.96
1871.31
339.36
0.92
1.12
164.88
0.202
R8
9.69
9.25
377.65
51.99
0.14
0.17
26.14
0.032
R9
29.71
50.58
124.19
111.60
0.30
0.38
49.54
0.061
R10
8.66
12.64
350.39
53.72
0.15
0.17
26.64
0.033
R11
11.59
15.17
428.75
66.30
0.18
0.21
32.84
0.040
R12
81.38
64.36
1879.83
318.16
0.86
1.08
155.68
0.191
R13
17 .86
13.06
487.54
74.08
0.20
0.25
36.73
0.045
R14
31.49
44.46
1181.55
186.05
0.50
0.59
91.95
0.113
R15
27.65
12.09
326.86
70.11
0.19
0.26
33.39
0.041
R16
47.39
36.79
924.24
171.17
0.46
0.59
82.89
0.102
R17
43.33
34.22
1320.73
193.96
0.52
0.64
96.61
0.119
R18
66.75
54.13
1479.67
258.09
0.70
0.88
125.85
0.154
R19
45.54
35.68
1126.56
183.31
0.50
0.62
90.12
0.111
R20
23.49
30.69
620.75
115.17
0.31
0.37
55.84
0.068
R21
5.57
24.16
472.35
76.49
0.21
0.22
37.74
0.046
R22
34.54
22.96
803.35
129.23
0.35
0.44
63.60
0.078
R23
7.39
15.01
452.88
63.73
0.17
0.19
31.98
0.039
R24
20.29
21.58
835.79
115.51
0.31
0.37
58.05
0.071
R25
43.15
23.27
504.81
115.30
0.31
0.43
54.63
0.067
R26
24.79
18.39
536.27
92.38
0.25
0.32
45.10
0.055
R27
82.85
69.45
2353.19
223.46
0.98
1.21
179.83
0.221
R28
37.43
45.11
1288.81
317.94
0.54
0.64
99.50
0.122
R29
22.72
42.65
1128.25
170.58
0.46
0.52
84.79
0.104
R30
25.21
15.34
540.21
136.05
0.24
0.31
43.55
0.053
5.57 - 82.85
12.09 - 82.96
124.19 - 2353.19
53.72 - 339.36
0.14 - 0.98
0.17 - 1.21
26.14 - 179.83
0.032 - 0.221
Mean
35
31.52
843.63
145.84
0.39
0.49
70.86
0.09
UNSCEAR2000
50
50
500
370
< 1
< 1
18 - 93
< 1
mSv∙y−1. Therefore, the rock samples are within an acceptable safe limit. The external hazard (Hex) in the rock samples ranged from 0.14 to 0.98 with a mean
Activity concentrations of radionuclides <sup>226</sup>Ra, <sup>232</sup>Th and <sup>40</sup>K in rock samples from South western, Saudi Arabia
(a, b), Correlations between <sup>226</sup>Ra and <sup>238</sup>U and between <sup>226</sup>Ra and <sup>40</sup>K in selected rock samples.
value of 0.39. Also, the internal hazard (Hin), its values ranged from 0.17 to 1.21 with a mean value of 0.49. Three samples (R7, R12, R27) had an internal hazard values above the recommended limit of 1.0 which implies that these samples are not suitable as interior building materials and may be a source of internal radon and its progeny, while the other samples have Hin values below the recommended limit. In general, for the safe use of a material in the construction of dwellings, Hex and Hin should be less than unity. The estimated absorbed dose rate varied from 26.14 to 179.83 nGy∙h−1. The mean absorbed dose rate was calculated to be 70.86 nGy∙h−1 within the typical range of worldwide average values (18 - 93) reported in UNSCEAR 2000. The calculated values of annual effective dose (AEDE) ranged from 0.032 to 0.221 mSv∙y−1 with a mean value 0.09 mSv∙y−1. The recommended upper limit of 1 mSv∙y−1 is not exceeded in all samples. This means that these rock samples are safety for human health.
Figure 4 shows a comparison between the average radium equivalent activity (Bq/kg) and the absorbed dose rate (nGy∙h−1) for rock samples under investigation. Table 2 compares the average values of natural radioactivity for rocks in the present study with the obtained data for other countries. As shown in this table, the radioactivity in rock samples varied from one country to another
Radium equivalent and absorbed dose in rock samples, south western, Saudi Arabia
Comparison of natural radioactivity concentration (Bq/kg) in the present study with the reported values of the world
Country
Average activity concentration (Bq/kg)
References
226R
232Th
40K
Saudi Arabia
35
31.57
843.63
Present work
Saudi(South of Al-Madina)
106.4
110.35
2683
[12]
Egypt
28.4
37.4
1167
[11]
Yemen (Aden)
57.086
80.26
846.21
[7]
Yemen(Sana’a,)
26.6
23.2
515.6
[9]
Italy
15 - 164
16 - 174
201 - 1350
[21]
India
41.08
86.26
869.29
[4]
Brazil
24
37
1173
[22]
Turkey
12.01 - 48.95
8.2 - 53.27
143.97 - 452.34 45444445452.34
[23]
depends on the locality geological conditions [9] [11] [16] . In general, the results of this study are comparable to the different published studies as listed in this Table.
4. Conclusion
Gamma ray spectrometry has been used to determine the radioactivity concentrations of 226Ra, 232Th and 40K in the rock samples, collected from Albaha region in the south west of Saudi Arabia. The results show that the activity concentrations of 226Ra and 232Th consent with the world-wide average recommended values. The radium equivalent activity values were below the permissible limits 370 Bq/kg. The values of external, internal hazard index and outdoor effective dose were found less than unity. Therefore, the study area is still in the zones of normal radiation level. This data may provide a guideline for future measurement and assessment of possible radiological risks to human health in this region.
Cite this paper
Al-Zahrani, J. (2017) Gamma Radiation Measurements of Naturally Occurring Radioactive in Igneous Rocks and Its Radiological Complications. World Journal of Nuclear Science and Te- chnology, 7, 136-144. https://doi.org/10.4236/wjnst.2017.73012
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