The exposure of human to naturally occurring radiation comes primarily from two different origins. The first source, the main contributor is the terrestrial radioactive materials which shape from the formation of the earth crust. The second source comes directly from the cosmic radiation. The term of naturally occurring radionuclides is known as NORM. Only long-lived radionuclides, with half-lives comparable to the age of the earth, and their daughters, contribute to this natural radiation background in significant levels [1] .

The majority of NORMs belong to the U-238, Th-232 decay series and K-40 as illustrated in Figure 1. NORMs emit alpha, beta particles and gamma ray as these radiations represent the primary sources of external exposure to the society [2] .

These radionuclides (U-238, Th-232 decay series, and K-40) which emit either beta or alpha particles may be ingested or inhaled and surely can increase the internal exposures. Moreover, some radiation emitters may emit gamma radiation following their nuclear decay [3] .

Terrestrial radionuclides occurred in all types of building materials, can give rise to external exposures owing to gamma rays. The specific activities of the radionuclides of various rocks and soils used as raw material in building materials are presented in Table 1. In Table 1, ignition rocks show higher levels of natural radionulcides than sedimentary rocks.

There have been so many studies concerning NORMs in soils, rocks, and construction materials which can furnish invaluable details on the nature and levels of radiation in any region and provide information in the change in radionuclide concentrations. All the studies of regional radionuclides in Table 1 showed that most of building materials contain wide ranges of NORM levels.

There have been so many studies concerning NORMs in soils, rocks, and construction materials which can furnish invaluable details on the nature and levels of radiation in any region and provide information in the change in radionuclide concentrations. All the studies of regional radionuclides in Table 1 showed that most of building materials contain wide ranges of NORM levels.

Determination of radioactivity in building materials used in them, shows that natural radionuclides of uranium (U-238) and thorium (Th-232) series, together

with the radioactive isotope of potassium (K-40), are presented. Limits of Ra-226 concentrations are established by different countries in order to control Rn-222 levels (200 Bq/m³ in European Union and up to 1000 Bq/m³ in Saudi Arabia). Potassium-40 and others gamma emitters of Ra-226 and Th-232 descendants, can cause an external dose. In European Union, a maximum value of 1 mSv∙y⁻¹ is recommended as well as in Saudi Arabia [4] .

Merle Lust studied the NORM in building materials used in Estonia. During the Merle Lust investigation, 53 samples of commonly used raw materials and building products were collected and measured. The activity levels were determined by gamma ray spectrometry [5] . Their mean values were in the ranges 7 to 747 Bq/kg for K-40, 4.4 to 69 Bq/kg for Ra-226, and 0.8 to 86 Bq/kg for Th-232. The activity index I in the 53 different building materials varied from 0.02 to 0.74 and the radium equivalent, from 6 to 239. The average annual dose for the people, caused by the building materials of dwellings, was assessed for most commonly used materials. It was estimated to be in the range from 0.16 mSv to 0.44 mSv.

Adriana Etokov and Lenka Palakov [6] studied activities of Ra-226, Th-232 and K-40 and radiological parameters (radium equivalent activity, gamma and alpha indexes, the absorbed gamma dose rate and external and internal hazard indices) of cements and cement composites commonly used in the Slovak Republic. The cement samples of 8 types of cements from Slovak cement plants and five types of composites made from cement type CEM I were analyzed. The radionuclide activities in the cements ranged from 8.58 to 19.1 Bq/kg, 9.78 to 26.3 Bq/kg and 156.5 to 489.4 Bq/kg for Ra-226, Th-232 and K-40, respectively. The radiological parameters in cement samples were calculated as follows: mean radium equivalent activity R a e q = 67.87   Bq / kg , gamma index I γ = 0.256 , alpha index I α = 0.067 , the absorbed gamma dose rate D = 60.76 nGy/h, external hazard index H e x = 0.182 and internal hazard index H_in was 0.218. The radionuclide activity in composites ranged from 6.84 to 10.8 Bq/kg for Ra-226, 13.1 to 20.5 Bq/kg for Th-232 and 250.4 to 494.4 Bq/kg for K-40.

Singh [7] carried out radiation measurement of Indian building materials. The activity concentrations of Ra-226, Th-232 and K-40 have been determined by gamma-ray spectrometry. The measured activity in the selected building materials ranges from 3.2 to 151.7 Bq/kg, 14 to 63.7 Bq/kg and 24.3 to 121.5 Bq/kg for Ra-226, Th-232 and K-40 respectively. The activity concentration of U-238 were determined using fission track technique and the value ranges from 0.11 to 3.85 ppm.

W.R. Alharbi, J.H. AlZahrani [8] studied the radioactivity in some building materials in Saudi Arabia, the natural radionuclides (Ra-226, Th-232 and K-40) present in various building materials available in Saudi Arabia (Jeddah city) analyzed using Gamma-ray spectrometry. The results showed that the activity concentration of Ra-226, Th-232 and K-40 was between 12.6 Bq/kg (Brick-clay) to 31.5 Bq/kg, (Granite), 9.2 Bq/kg (Brick-clay) to 27.2 Bq/kg (Granite) and 114.4 Bq/kg (Brick-clay) to 534.7 Bq/kg (Granite), respectively. The radiological hazard parameters radium equivalent activity, gamma index, absorbed dose rate and the annual exposure rate, were calculated to assess the radiation hazards associated with Saudian buildings. All studied samples were lower than world average limits. The results were compared with the published data of other countries and with the world average limits. The measurements helped in the development of standards and guidelines for the use and management of building materials.

Therefore, this work dealt with assessing of natural radioactivity in adhesive materials used and sold in Riyadh city, Saudi Arabia.

The risk assessment of radiation doses can be given in form of radiation indexes. In literature, there has been tonnes of publications on how to evaluate the radiation hazards linked to presence of ²²⁶Ra, ²³⁸U, ²³²Th, and ⁴⁰K [9] [10] .

In order to carry on such assessment, one needs to provide some terminologies associated with radiation hazard. Therefore, this section will explain them.

The samples were crushed using crusher and then homogenized. The homogenized samples were filled into 1000 ml Marinelli beakers which were later hermetically sealed with the help of PVC (polyvinyl chloride) commercial to prevent the escape of air-borne of Rn-222 and Rn-220 from the samples. All the samples were accurately weighted and stored for period of at least one month prior to determination in order to attain radioactive secular equilibrium between Ra-226 and Rn-222 [9] .

In this investigation, the sample activities in building materials were measured by using high-resolution gamma-ray spectrometry system consists of coaxial hyper-pure germanium (HPGe) detector with highly passive shielding and low background. The detector was cooled with liquid nitrogen cryostat to re-duce the leakage current. To reduce the background radiation from natural sources the detector was enclosed of 10 cm thick cylindrical lead shield. The lead shielding was graded with an inner layer of thick copper to reduce any influence fluorescences [22] .

The detector was connected to a pre-amplifier, shaping amplifier and high voltage power supply which were used for conversion of the observed energy into a pulse height spectrum. The pulse amplitude was converted to a discrete number through more 8000 channel multi-channel analyser (MCA). The data acquisition, display, and analysis of γspectra were carried out using Genie 2000 software [23] .

The relationship between the channel numbers corresponding to absolute γenergies was determined. The specification of the used instrument is listed in Table 2 [22] .

In this work, gamma reference sources containing mixed of radionuclide were used for energy set of calibration. These references emit a wide range of gamma- ray energies covering the entire energy range of interest. The main gamma-ray energy lines of the used references are shown in Table 3.

The gamma energies used for Ra-226 was at 186.2 keV and Pb-214 was also used at different energies at 295.2 and 351.9 keV.

For gamma-ray spectrometry of unknown, the detector efficiency measurement plays important role in gamma-counting. The full-energy peak efficiency

can be computed through:

ε f = N p N γ (5)

where ε f is defined as the full-energy peak efficiency,

N p is the net gamma-ray counting rate in the full-energy peak

N γ is defined as the gamma-ray emission rate where it can be calculated via:

N γ = A P γ (6)

where A is the activity in Bq of the reference and P γ is the branching ratio of the radionuclide.

In order to removed interference between multi peaks, the calibration of energy efficiency was carried out carefully. For every source, the energy efficiency was calculated using formula (5) as shown in Figure 2 and the energy channels was calculated as shown in Figure 3 [21] [22] .

The minimum detection activity (MDA) which is the performance of gamma- ray spectrometry is defined as the lowest quantity of radionuclide that can be measured for a certain measurement. MDA can be calculated via the following

equation in unit of Bq/kg:

M D A = L D ε f P γ T M (7)

where L D is the detection limit,

ε f is the absolute efficiency of the detector,

P γ is the gamma branching ratio or gamma probability,

T is the counting time,

M is the sample mass in kg.

L D can be expressed through the equation:

L D = 2.71 + 4.65 ( background ) 0.5 (8)

L D was measured for over 170,000 sec with no radiation and it was carried out with 1000 Marinelli beaker filled with tri-di-ionized water placed inside the detector using the same geometry.

The specific activity is defined as the activity per mass unit. The specific activity of individual radionuclide in the studied building material can be calculated using the following equation:

A = N ε f P γ T M K (9)

where ε f is the efficiency of energy at the photopeak of interested radionuclide

T is counting time in second (86,400 sec)

M is the mass in kg of the analysed sample,

P γ is the gamma branching ratio or gamma probability,

K is a correction factor,

N is the corrected net peak area

N = N S − N B (10)

where N S is the net peak area and N B is the net peak area of the background [23] .

The relevant radiological assessed values for adhesive materials are listed in Table 4. The highest reported value of U-238 in adhesive was 17.4 Bq/kg whereas the lowest value was 5.2 Bq/kg and the mean value was 8.7 Bq/kg. For Th-232, the lowest reported value in this study was 5.3 Bq/kg and the highest value was 12.4 Bq/kg. The average of Th-232, by this study, was 7.2 Bq/kg. For K-40, The highest reported value, by our study, was 183 Bq/kg and the lowest values was 0 Bq/kg which is normal as adhesive does not contain potassium.

To discuss the statistical evaluation, one can start with confidence limits test of Shawhart. The confidence limit test of Th-232 in Figure 4 indicated that Th-232 levels in adhesive materials were normal distributed and all the data were located within the max and min border of confidence limits.

The confidence limit test for U-238 is illustrated in Figure 5. The U-238 levels clearly proved that data can be treated as parametric due to normal distribution of the obtained data.

The shawhart confidence limit interval test showed K-40 results passed the test as illustrated in Figure 6.

R a e q mean value was 24 Bq/kg that is lower than set limit of 370 Bq/kg [24] . For H e x , the lowest reported value was 0.05 and the highest value was 0.07 with mean value of 0.06 mSv/yr. The fixed limit of H e x is set to be 1 mSv/yr. H i n lowest value for adhesive was 0.08 mSv/yr and highest value was 0.13 mSv/yr with mean of 0.09 mSv/yr. Lucky, the study adhesive materials were less than max permissible value of 1 mSv/yr. The annual effective does reported in this work was 0.08 mSv/kg in average where this values is less than max permissible value of 1 mSv/yr. Therefore, The reported radiological values were far below the permissible limits. Therefore, it is obvious that the adhesive did not posses any radiation hazard to residents.

Turhan, eref et al. (2008) reported natural radioactivity in adhesive materials. In their study, U-238 activities were 7.3 to 69.4 Bq/kg whereas this study showed the ranges were 0 to 17 Bq/kg. Thus, the study adhesives were located within the worldwide ranges. In Tuhan study, Th-232 activity was 2 to 57 Bq/kg in adhesives

while, this study, showed the range of Th-232 was 4.9 to 12.4 Bq/kg. So, it can be stated that the study adhesives were within the worldwide range. K-40, in Turhan study, was ranging 21 to 816 Bq/kg whereas in this study was 0 to 183 Bq/kg. Therefore, the natural radioactivity in adhesives, by this study, were less than the worldwide values.

This section deals with previous unpublished data of heavy metals in adhesive materials and their correlation with radioactivity. It is a step to explore the relationship between them in form of matrix correlations and Mood’s test (Monte Carlo).

Using Mood’s Median Test, the obtained results showed there was different in the medians of the data as calculated in Table 5 and can be shown in Figure 7. Thus, the obtained results of heavy metals levels and natural radioactivity may be treated as non-parametric data.

Table 6 and Table 7 show the calculations of correlations of the studied adhesive materials between selected heavy metals and natural radioactivity.

K-40 was positively correlated with Ga, As, Mo, and Cd. Th-232 was also correlated with Ga, As, and Cd.

Using Mood’s Median Test, the obtained results showed there was different in the medians of the data as calculated in Table 5 and can be shown in Figure 5. Thus, the obtained results of heavy metals levels and natural radioactivity may be treated as non-parametric data.

In Figure 8 and Table 8, the obtained results of Radium equivalent radiation hazard index showed that data were located below the max permissible limit of 370 Bq/kg. Therefore, the radiation hazard index of Ra_eq indicated the analysed adhesive material were not contaminated with NORM.

Figure 9 shows the obtained results of external hazard values where all the reported data are located below 0.09. The average external radiation hazard was much more below the permissible limit of one mSv/yr. Thus, it can be stated that adhesive materials were free of natural radioactivity in term of external radiation hazard.

Similarly, the internal radiation hazard was computed as demonstrated in Figure 10. All the reported data of internal radiation hazard were in range of less than 0.1 whereas the max allowable limit is fixed by one.

The last radiation hazard index used in this study was annual effective dose. This index is the most important radiation index in any radiation risk assessment. Figure 11 shows the average valued of annual effective dose was less than 0.07 while the fixed value of this index is one mSv/yr.

Turhan, eref et al. [25] reported natural radioactivity in adhesive materials. In their study, U-238 activities were 7.3 to 69.4 Bq/kg whereas this study showed the ranges were 0 to 17 Bq/kg. Thus, the study adhesives were located within the worldwide ranges. In Turhan study, Th-232 activity was 2 to 57 Bq/kg in adhesives while, this study, showed the range of Th-232 was 4.9 to 12.4 Bq/kg. So, it can be stated that the study adhesives were within the worldwide range. K-40, in Turhan study, was ranging 21 to 816 Bq/kg whereas in this study was 0 to 183 Bq/kg. Therefore, the natural radioactivity in adhesives, by this study, were less than the worldwide demonstrated in Table 9. It can be stated that the study

adhesive building materials were safe to be used in construction building materials in term of natural radioactivity.

Alshammari, H., Algammidi, A. and Algammidi, A. (2017) The Experimental Gamma Radiation Dose Rate for Radiation Hazard into Adhesive Building Materials in Saudi Arabia. Open Journal of Radiology, 7, 272-291. https://doi.org/10.4236/ojrad.2017.74030