2.1. Study Area
Figure 1 shows the regions where the samples were taken. The Eastern Pontides, one of Turkey's tectonic and geological associations, are divided into three separate regions, taking into account the structural and lithological features, defined as the Northern Zone, Southern Zones, and the Axial Zone (Arslan et al. 1997; Özsayar et al. 1981; Eyuboglu, Y. 2006). The study area is located in the Northern Zone. The oldest unit in the study area is late Cretaceous-aged Çağlayan Formation consisting of basalt, andesite, and pyroclastic rocks. The unit is observed southern and eastern parts of the study area and is overlain by late Cretaceous-Paleocene-aged Kaçkar Granitoid which presents vast outcrops surrounding the study area. Pliocene-Pleistocene aged trachyte-trachyandesite and obsidian outcrop in the middle and eastern sections of the area in relation with NE-SW and SE-NW trending faults.
2.2. Preparation of Samples for Measurement
Rock samples were taken within the scope of the field studies for the İkizdere district of Rize province, which is the study area. The samples taken from the surfaces of the obsidians with the help of a hammer were placed in clean, closable nylon bags and brought to the laboratory. The collected obsidian samples were broken and pounded with the help of crushers in the laboratory and passed through a 80 Mesh sieve for homogeneity. For chemical analysis, determination of mass absorption coefficients and radionuclide analysis, the samples must be ground and pulverized.
In order to form absorption discs, parts with a mass of approximately 1.5 g were taken from each sample and discs with a diameter of 12 mm were formed under 5 bar pressure with a hydraulic press machine. It was observed that the discs formed were strong and did not break down due to the structure of the samples.
For radionuclide analysis, crushed and pounded rock samples were placed in plastic boxes with a diameter of 6 cm and a height of 5 cm, prepared in accordance with the experiment geometry, and the boxes were kept tightly closed for 1 month. Thus, the radioactive balance between 238U and 232Th products was achieved and the samples were made ready for counting.
2.3. Experiment
2.3.1. Gamma Measurements
Radionuclide analysis of obsidian samples that were ready for measurement was conducted with an high purity coaxial Ge detector (HPGe). HPGe detector (AMATEK-ORTEC-GEM25P4-76, U.S.A) with a relative efficiency of 33%. The resolution of the system was 1.7 keV at the 1332.5 keV peak of 60Co. In the spectra, 238U decay product 214Pb (295.2 keV and 352 keV), 214Bi (609.4 keV), 232Th decay product 212Pb (238.6 keV), 208T1 (583.1), 228Ac (911.1 keV); 137Cs (661.6 keV) and 40K (1460 keV) peaks were determined and activity was calculated with the Equation-1 given below
where A (Bq.kg-1) is the activity concentration of a radionuclide, N is the total net count of a specific gamma emissions, m is the mass of the sample (kg), Ɛ is the detector efficiency of the specific gamma emission, P is the absolute transition probability of that gamma emission, t is the counting time. In water samples, unlike soil samples, the water sample volume was used instead of the sample mass. Spectral analysis was performed using the Genie 2000 software that was obtained from CANBERRA. After the activities of the water and soil samples were calculated, absorbed dose, annual effective dose and external hazard index were calculated. If a radionuclide activity is known then its exposure dose in air at 1 m above the ground can be calculated using the Equation-2 proposed by UNSCEAR 2000 (UNSCEAR, 2000).
D (nGy/h) =(0.462xAU) + (0.604xATh) + (0.0417x AK) (2)
AU, ATh and AK are the activity concentrations of 238U, 232Th and 40K, respectively, in the samples. The conversion factors of 238U, 232Th and 40K are 0.462, 0.604 and 0.0417 nGy h-1 per Bq kg-1, respectively.
The Annual Effective Dose Equivalent was calculated from the Equation-3.
In this equation; The Environmental Gamma Dose Conversion Factor does not change for both indoor and outdoor measurements and is taken as 0.7 Sv Gy-1. The occupation factor is the time people are exposed to these rays. In this study, occupation factor in Equation 4 was taken as 0.8 for indoor and 0.2 for indoor outside, considering that people spend 20% of their time outdoors and 80% indoors. Time is the number of hours in a year (8760 s/y) (UNSCEAR, 2000).
2.3.2. Mass Absorption Coefficient Measurement
It is necessary to measure with a gamma detector system to determine the gamma ray mass absorption coefficient of the samples created and the radionuclide concentrations in the samples. In this study, Amatek-Ortec-Gem25p4-76 model high purity coaxial Germanium detector (HPGe) was used. This device, which is used in the analysis of radioactive materials that emit gamma rays of different intensity and energy, consists of a radiation detector, liquid nitrogen-based cooling mechanism, electronic system and amplifiers that detect the generated signals. This detector has a resolution of 1.7 keV at 1.33 MeV and a relative efficiency of 33%.
Each count was carried out for a period of 10.000 seconds, a total of 14 samples and three measurements were made for the blank count and calculations were made by taking the average of these three measurements. Gamma ray mass absorption calculations are made at four energy values. These are 80.99 keV, 302.85 keV, 356.01 keV for 133Ba and 661.66 keV, which is the only peak of 137Cs. Gamma ray mass absorption coefficients for obsidians were calculated by the following formulas.
If a material of thickness x is placed in the path of a beam of gamma radiations, the intensity of the beam will be attenuated according to Beer-Lambert’s law:
where I0 and I are the unnattenuated and attenuated photon intensities, respectively, and μ (cm−1) is the linear attenuation coefficient of the material.
A coefficient more accurately characterizing a given material is density-independent mass attenuation coefficients μ ρ-1 (cm2 g-1):
Where “d” is the mass per unit area (g cm-1) and “µ ρ-1” is the mass attenuation coefficient (cm2 g-1) (Baltas 2020).
2. 3.3. Elemental Analysis
Chemical analysis is carried out in order to determine the chemical content of the test samples and the amount of elements contained in it. In this study, X-ray fluorescence spectrometer (XRF), one of the chemical analysis methods, was used. The chemical contents of the test samples obtained after the grinding process were determined with the help of the XRF tester.
The samples were prepared as pellets without using any additives after drying at 105 0C for 1 day. The sample was placed in a 30 mm sample holder in accordance with the sample amount and semi-quantitatively studied in the form of oxide in the Boron-Uranium range. The results are prepared as both oxide and metal.