Using Mathematical Procedure to Compute the Attenuation Coefficient in Spectrometry Field

In gamma-ray spectrometry, the analysis of the environmental radioactivity samples (soil, sediment and ash of a living organism) needs to know the linear attenuation coeffi cient of the sample matrix. This coeffi cient is required to calculate the self-absorption correction factor through the sample bulk. In addition, these parameters are very important because the unidentifi ed samples can be different in the composition and density from the reference liquid sources which are usually used for effi ciency calibration in the radioactive monitoring process. The present work is essentially concerned to introduce a mathematical method to calculate the linear attenuation coeffi cient without using any collimator. This method was based mainly on the calculations of the effective solid angle subtended by the source-to-the detector confi gurations, the effi ciency transfer technique and the average path lengths through the samples itself. The method can be used as a tool for the calculation of the linear attenuation coeffi cient of unidentifi ed materials with good facility to use it in the calibration process of γ-ray detectors, particularly in the study of soil samples. The results are compared with the data from NIST-XCOM to show how much the results are in close agreement and to give the validity of the approach. Case Report Using Mathematical Procedure to Compute the Attenuation Coeffi cient in Spectrometry Field Mohamed Elsafi 1, Mona M Gouda1, Mohamed S Badawi1,2*, Abouzeid A Thabet3, Ahmed M El-Khatib1, Mahmuod I Abbas1 and Kholud S Almugren4 1Physics Department, Faculty of Science, Alexandria University, 21511 Alexandria, Egypt 2Department of Physics, Faculty of Science, Beirut Arab University, Beirut, Lebanon 3Department of Medical Equipment Technology, Faculty of Allied Medical Sciences, Pharos University in Alexandria, Alexandria, Egypt 4Physics Department, Faculty of Science, Princess Nourah Bint Abdulrahaman University, 11544-55532 Riyadh, Saudi Arabia *Address for Correspondence: Mohamed S Badawi, Physics Department, Faculty of Science, Alexandria University, 21511 Alexandria, Egypt, Tel: +201005154976; Email: ms241178@hotmail.com Submitted: 19 December 2016 Approved: 03 February 2017 Published: 06 February 2017 Copyright: 2017 Elsafi M, et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


INTRODUCTION
Relative measurement for the radioactivity analysis of environmental samples can be used as a typical technique of gamma-ray spectrometry. It is adopted to measure the radioactivity by applying the ef iciency of the detector obtained through volumetric sources that are made of liquid standard gamma sources. Typically, volumetric sources are made by considering the geometry of the samples. However, it is dif icult to consider the difference in chemical composition and density between standard volumetric sources and samples under investigation because there are various kinds of samples such as soil, sediment and ash of a living organism. The difference in the self-attenuation of the gamma-ray photon inside the source and sample materials should be considered in the analysis. It is caused by absorption and scattering of the gamma-ray in the samples and sources [1], and leads to incorrect measurement of radioactivity by more than 20%, especially for samples emitting low energy gamma lines [2][3][4]. Correcting this effect makes a more accurate analysis possible; therefore, the correction of difference in self-attenuation between the volumetric sources and the environmental samples is necessary in gamma-ray spectrometry.
The Source self-attenuation factor depends on the linear attenuation coef icient, which de ined as the probability per unit path length that the gamma-ray photon is removed from the beam [1]. When chemical composition of the samples is known, this coef icient can be calculated by using the photon cross sections data base [5]. There is one method for determining the linear attenuation coef icient under the assumption that the density of the sample in which a collimated narrow beam is used [6][7][8][9][10] is uniform. However, this method is dif icult to be carried out in a typical laboratory because of high radioactivity of sources prices and the requirement of a large space for the devices. In this study, a cone beam was utilized, not equipped with the collimator, and a complete geometric con iguration was modeled mathematically.
In the present work, a new mathematical method used to calculate the linear attenuation coef icient by using the source-to-detector con iguration and integration solutions. In this method gamma-ray point sources (special kind of Plexiglas vials with diameters smaller than the diameter of the detector crystal) were used. This vial was illed with reference sample materials of [NaCl, Na 2 CO 3 and (NH 4 ) 2 SO 4 ], which are similar to the densities of the environmental samples [soil, sediment and ash of a living organism].

MATHEMATICAL TREATMENT
Based on the direct mathematical method [10][11][12][13][14][15][16][17], a new theoretical approach was introduced to determine the detector ef iciency by the use of isotropic radiating axialpoint sources located at different heights from the cylindrical detector upper surface. This method depends on the accurate analytical calculation of the average path length covered by the photon inside the detector active volume and the effective solid angle Ω eff . This work is considered to be the best case of the mathematical expressions of the previous work presented at [17], where the volume of the other samples vials and the source positions were effected on the linear attenuation coef icient calculations, showing unlike behavior based on the change of the effective solid angle and the detector ef iciency.
The attenuation factor f att , is due to the detector dead layer, detector end-cap, the absorber between the source-to-detector space and the side and bottom of the sample container material, which are described for the absorber layers with attenuation coef icients μ 1, μ 2 …μ n , and relevant thicknesses t 1 , t 2 …t n , between the source-detector system given by: . att lay cap where,  lay and  cap are the attenuation coef icients of dead layer and end cap respectively, while  lay and  cap are the path length traveled by a photon through the dead layer and the end cap respectively. In addition, μ d is the attenuation coef icient of the detector crystal, μ s is the attenuation coef icient of the sample and μ v is the attenuation coef icient of the vial material, while y 1 , y 2 and y 3 are the path lengths through the sample container material top, side and the bottom respectively and can given by: The angles θ 1 up to θ 4 are the expressions of the polar angles based on the source and detector arrangement as shown in igure (1) and it can give by: According to igure (1) the incident photon path lengths throught the detector crystal may have two possible expressions as the following: The general de inition for the average path length x  traveled by the photons through the sample material can be given by: Where θ and φ, are the polar and the azimuthal angles respectively and de ine the direction of the incidence photons, while Ω, is the geometrical solid angle subtended between the source and the detector and can be given by: The possible average path length traveled by the photon within the sample material with radius R s and height L s , for using an isotropic radiating axial point source located at a distance h, from the surface of the vial as as shown in igure (1) and can be given as: The effective solid angle based on equation (1) can be calculated according to three different cases: 1-In case, there is no vial in between the source-to-detector arrangement and de ined as Ω Free (Reference position).
2-In case, there is an empty vial in between the source-to-detector arrangement and de ine as Ω Empty (The self attaenuation equal zero).
3-In case, there is a vial busy with sample in between the source-to-detector arrangement and de ine as Ω Busy (Included self-attenuation).
In addition ε 1 , and ε 2 , are the calculated detection ef iciencies at the same conditions using the principle of the ef iciency transfer method in the case of the vial was empty and busy with the sample. This calculated full-energy peak ef iciency can be calculated by using the following equation: & .

Empty Busy
Free Free Where ε * is called the reference experimental full-energy peak ef iciency while, Ω Free is called the effective solid angle subtended by the source and the detector crystal at the reference position. Also Ω Empty , and Ω Busy , are the effective solid angles in the presence of empty and illed vial with sample material at the same geometrical conditions. Hence, the effective solid angle ratio can be expressed as: Also, ε and ε o are the measured ef iciencies of the detector at the same conditions as ε 1 , and ε 2 .
The last equation can show a simple method to calculate the linear attenuation coef icient, which can be easily determined experimentally or theoretically based on the average path length of the photon through the sample material and can be given by:

EXPERIMENTAL PROCEDURE
Sources that have been used in this process are point sources like 241 Am, 133 Ba, 152 Eu, 137 Cs, 60 Co. The radioactive substance is a very thin, compact grained layer applied to a circular area about 5 mm in diameter, in the middle of the source between two polyethylene foils and each having a mass per unit area of (21.3±1.8) mg⋅cm -2 . By heating under pressure, the two foils are welded together over the whole area so that they are leak-proofed. The coaxial HPGe spectrometry from Canberra model GC1520 of volume 100 cm 3 approximately with wide energy range from 40 keV to >10 MeV to detect the gamma-rays. The detector cold inger was placed in cryostat model 7500SL. The main technical features were provided by the company are: the crystal diameter and length were 48 mm and 54.5 mm respectively. In addition, as shown in igure (1), the end cap to the crystal distance, VG, was 5 mm, the entrance window, EC th , was 1.5 mm of Al and the dead layer, DL was 0.5 mm of Ge. The detector relative ef iciency was 15% and the resolution (FWHM) at 1.33 MeV of 60 Co was 1.85 keV.
Environmental samples that has been used to study the linear attenuation coef icient are Sodium Chloride (NaCl), Sodium Carbonate (Na 2 CO 3 ) and Ammonium Sulphate ((NH 4 ) 2 SO 4 ) and their densities are 1.394, 1.297 and 1.157 g/cm3 respectively, which are similar to the densities of the environmental samples. These samples were kept in a vial of known geometry. The vials made from Plexiglas of density 1.19 g/cm 3 , sample vial is shown in igure 2 with cross sectional drawing and dimensions. The data acquisition and spectrum control were done by PC through USB port depend on spectrum acquisition and analysis software (ISO 9001 Genie 2000). The acquisition time was as long as required to get high and enough counts under each peak of interest with a statistical uncertainty less than 1%. The peak itting is performed using a Gaussian shape without a low energy tail for germanium spectra. In order to prevent the dead time, the pile up effects and the coincidence summing effects, the large sourceto-detector axial distance was considered from the detector end cap. The sources were kept ixed at 26.40 cm in the measurement geometry from the detector end cap.
The measured full-energy peak ef iciency of a photon with energy E, can be determined by using the following equation: where N(E), is de ined as the number of counts in the full-energy peak at time, T in seconds, P(E) is the emission probability at energy E, A S is the activity of the calibration source and C i , is called the correction factor due to half-life time of the used element, also C d , is the decay correction for the calibration source from the reference time to time of measurement (ΔT) and it is given as equation (14) by knowing the decay constant λ: The uncertainty values in the experimental full energy peak ef iciency, σ ɛ , can be calculated as the following: Where σ A , σ P and σ N, are the uncertainties associated with the quantities A S , P (E) and N (E), respectively. Figure 3 contains a comparison between the online database of the reference (XCOM), the calculated and the measured linear attenuation coef icient, where the measured values of the linear attenuation coef icient were determined depending on the ratio of the measured ef iciency in the equation (11) and the average path distance in equation (9) traveled by the photon inside the sample materials [Sodium Chloride (NaCl), Sodium Carbonate (Na 2 CO 3 ) and Ammonium Sulphate ((NH 4 ) 2 SO 4 ) and their densities are 1.394, 1.297 and 1.157 g/cm3 respectively].

RESULTS AND DISCUSSIONS
The same igures included the deviation percentage between the XCOM and the measured linear attenuation coef icient values is Δ 1 %. Also Δ 2 % is the deviation percentage between the XCOM and the calculated linear attenuation coef icient values, based on the following equations, respectively: The variation of the calculated linear attenuation coef icient of the three samples as a function of the photon energy is presented as shown in igure 4. The results show the feasibility of the mathematical model within a small difference with the experimental values, where the linear attenuation coef icient for the various photon interaction process at the start is high and then decreases sharply with increases the photon energy up to 100 keV for all the selected composite materials, this is due to a dominance the three main processes of incident photon energies. The values of the calculated and the measured linear attenuation coef icients are in close agreement with an online database of the reference linear attenuation coef icient from (XCOM) related to the calculated deviation percentage values. Therefore, it can be applied to determine the linear attenuation coef icient of any type of samples.
The linear attenuation coef icients were plotted as a function of effective solid angle at a certain gamma-ray energy of 59.5 keV as an example and can be described as shown in igure 5. From attenuation values, it is found that it is strongly depends on the density of the sample matrix.

CONCLUSIONS
In this study, the detectors were used simply without a collimator and applied in a typical laboratory work to determine the linear attenuation coef icient in environmental samples. The experimental method was modeled mathematically by the direct mathematical method and excluding the coherent scattering coef icient of the samples and the detector stuff. This method was veri ied under the assumption that the density is uniform in the cylindrical sample. The deviation percentages show the possibility of the method was within ̴ 5%. The method could be practical and assist the unskilled technicians in the usual measurements of gamma-ray spectrometry for unfamiliar samples as a cheap and useful method.