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Investigation of Gamma-Ray’s Transmission Geometries for the Measurement of Attenuation Coefficients

  • Kulwinder Singh Mann EMAIL logo and Sukhmanjit Singh Mann
Published/Copyright: September 20, 2018

Abstract

For the measurement of attenuation parameters of any material for gamma (γ)-rays, the narrow-beam transmission geometry is one of the essential requirements. Linear attenuation coefficient (μ, cm−1), half value layer thickness and mean free path are some fundamental parameters used for the analysis of γ-ray attenuation behaviour of any material. The complete experimental setup used to measure these parameters is termed as γ-ray transmission geometry. The geometrical parameters such as the size of collimator aperture, thickness of sample (absorber), source to absorber (SA) distance, absorber to detector distance and source to detector distance (STD) are deciding factors for the nature of γ-ray transmission geometry. A novel geometrical parameter, scattered-to-transmission ratio (STR), has been proposed in this investigation. STR provides qualitative information of various geometrical parameters. It provides influence on the nature of transmission geometry for experimental measurements by various geometrical parameters and buildup factor. To investigate its influence, STR values have been analysed by varying sizes of collimator aperture between 3 and 12 mm and absorber thicknesses between 20 and 280 mm for fixed SA and STD. Six standard building materials (cement black, cement white, clay, red mud, lime stone and plaster of paris) have been used for the investigation. The point isotropic γ-ray sources Cs-137 (3700 M Bq) and Co-60 (370 M Bq) have been used in this study. It has been found that STR provides better information of scattered γ-rays by the material than its buildup factor (B). Additionally, CSTR (the critical value of STR) serves as an extensive parameter to distinguish between narrow-beam (good) and broad-beam (poor) γ-ray transmission geometries.

1 Introduction

The precise measurement of gamma (γ)-ray mass attenuation coefficients (μm) of absorber needs narrow-beam transmission geometry [1]. Both liner attenuation coefficient (μ) and mass attenuation coefficient (μm, cm2 g−1) are very useful parameters for non-destructive analysis of materials and in medical diagnostics such as the computed tomography scan [1]. The γ-ray shielding parameters (GSP) such as effective electron density (Nel,eff), Klein-Nishina cross section (σc) and scatter acceptance angle (θSC) are explicit functions of the attenuation coefficients. Thus, the accuracy in the μm measurement is desirable for analysis of the γ-ray shielding behaviour (GSB) of any material. A good-geometry (narrow-beam) condition is recommended for the analysis of GSB of absorbers [1], [2], [3], [4], [5]. In practice, the γ-ray transmission geometry deviates from the good-geometry conditions. Multiple factors cause such deviations, i.e. the size of collimator aperture, thickness of the sample, various distances [source to absorber (SA), absorber to detector (AD) and source to detector distance (STD)], buildup factors (B) and scatter acceptance angle (θSC) [6]. These factors are termed as geometrical parameters (GPs). In other words, it is impossible to design a collimator which allows an γ-ray beam with unit photon flux to pass, and at the same time it is very difficult to make the absorber’s thickness on an atomic scale. Practically during γ-ray measurements for the absorber, many photons pass through the finest collimator and thereby interact randomly with a large number of atoms during their traverse through the absorber. Thus, probability plays a role in the attenuation of γ-rays. The aim of the present work was to provide a parameter which provides quantitative information about the nature of geometry. The deviation of transmission geometry from a perfect narrow-beam condition results in the intermixing of scattered photons with the transmitted beam by the absorber. It causes fluctuations in the transmitted γ-ray intensity reaching the detector. This is the major cause of errors in μm measurements [5], [6]. In order to parameterise the magnitude of contribution of the scattered photons, White (1950) introduced buildup factor, which is the ratio of measured to computed intensities of γ-rays reaching the detector [7]. In the present study, the combined influence of GPs and B on the μm measurement has been investigated using scattered-to-transmitted ratio (STR).

2 Objective

The objective of this study was to develop a parameter which quantitatively describes the nature of the experimental setup (transmission geometry) used for the μm measurement of material.

3 Materials and Methods

3.1 Sample Materials

Six commonly used building materials [cement black (CB), cement white (CW), clay (CY), red mud (RM), lime stone (LS) and plaster of paris (PP)] have been used for this investigation. Their standard chemical compositions have been used for the investigation [5]. The information of samples has been provided in Tables 1 and 2.

Table 1:

Description of standard samples [5], [6].

Sr. no. and name of the sample (Standard)Sample’s material typeSymbol assignedDensity (g cm−3)Source
(1) Cement blackPortland CementsCB1.652Ultra Tech Cement, India
(2) Cement whiteCW1.826Ultra Tech Cement, India
(3) Clay (mix of kaolinite and montmorillonitic)SoilsCY1.743From a 1-m-deep pit at Village Gill-Patti, Bathinda, Punjab, India
(4) Red mud (montmorillonitic)RM1.855From a 1-m-deep pit at Village Gill-Patti, Bathinda, Punjab, India
(5) Lime stoneSupplementary MaterialsLS1.072Durga Lime Industries, Jodhpur, India
(6) Plaster of parisPP1.253Trimurti Rajasthan, India
Table 2:

Chemical composition of the samples.

OxidesBy weight fraction (×10−4)
CBCWCYRMLSPP
CaO4840.006620.001210.001150.009660.004300.00
SiO22950.002100.005280.005450.00107.00260.00
Al2O31200.00448.001690.001660.0023.0097.20
Fe2O3459.0036.10669.00646.0023.0047.10
SO3239.00433.0021.1016.1074.005190.00
MgO97.50233.00493.00471.00105.0065.10
TiO294.5023.0074.2073.200.006.01
K2O67.4075.10371.00350.002.0028.10
Na2O25.1019.00154.00159.000.007.01
P2O525.103.0014.0014.002.000.00
MnO8.041.009.0210.001.001.00
V2O54.023.000.000.000.000.00
Cr2O30.941.002.002.010.000.00
CuO0.900.451.001.000.440.38
NiO0.871.000.850.930.630.00
ZnO0.020.221.001.000.000.26

3.2 γ-Ray Sources and Detector

Two point isotropic sources, Cs137 (3700 MBq) and Co60 (370 MBq), procured from the BRIT (Board of Radiation and Isotope Technology, Bhabha Atomic Research Centre, Trombay, Mumbai, India) have been used in this study. The scintillation detector NaI(Tl) (Canberra, model: 802, 2007P, Meriden, CT, USA) coupled with a multichannel analyser (2k, ORTEC model: A64 B1, Atlanta, GA, USA) and computer has been used to record the spectra of γ-rays. A computer software, MAESTRO (Windows Model A65-B32, Version 6.01, ORTEC, Atlanta, GA, USA), has been used to capture and analyse the γ-ray spectra. Lead alloy blocks procured from Bhabha Atomic Research Centre, Trombay, Mumbai, India were used for shielding purposes of the source-detector assembly.

3.3 Preparation of Sample Bricks

Paste of the powdered samples (grain size ≤75 μm) was prepared with distilled water. A steel mould (95 × 93 × 50 mm) and a hydraulic press (5 MPa) have been used to make sample bricks. The bricks, thus, obtained were allowed to dry for 1 month after wrapping in polyethylene sheets. The polyethene helps to slow down the drying process and results in the reduction of crack formation due to the shrinkage process. The remaining moisture of the sample bricks has been removed by placing them in an oven (80 °C). Afterward, bricks of identical dimensions have been obtained by grinding and polishing. The combination of bricks that are 2 cm thick has been used to change the thickness of the absorber.

3.4 Computer Program

For theoretical computations, a computer program (GRIC3 toolkit) has been developed by modifying the GRIC2 toolkit [5] (see Supplementary Material, Fig. 1). The GRIC3 toolkit (see Supplementary Material, Fig. 2) has the ability to compute the θSC, buildup factor (B) and STR for a given experiential setup, i.e. for different values of the collimator aperture, SA and SD.

Figure 1: Schematic representation of transmission geometry used in the present investigations.
Figure 1:

Schematic representation of transmission geometry used in the present investigations.

Figure 2: Description of the variations in STR (%) and scatter acceptance angle with the absorber’s (CW) thickness (linear in cm and optical in mfp).
Figure 2:

Description of the variations in STR (%) and scatter acceptance angle with the absorber’s (CW) thickness (linear in cm and optical in mfp).

4 Methodology

According to the Midgley condition for narrow-beam geometry, θSC ≤ 3° [8], the nature of the transmission geometry has been decided. Mann [5], [6] used this condition for deciding the optimum thickness [0.5 mean free path (mfp)] of the sample for its precise μ measurements. The following section provides the step-by-step information and methodology used in the investigation of the STR.

4.1 Experimental Setup

The point isotropic source and three lead collimators (C1, C2 and C3) have been used in the experimental setup. The aperture size of C1 was fixed at 3 mm, but the apertures of C2 and C3 have been varied from 3 to 12 mm. Figure 1 describes all the details of the transmission geometry used for the investigation. The values of SD = 680 mm, SA = 312 mm and the thickness of collimator C1 = 90 mm, C2 = 33 mm and C3 = 40 mm were fixed. Figure 1 describes the transmission geometry used for the investigation. It also explains the concept of scatter acceptance angle, i.e. θsc = θin + θout [8].

The experiments were performed in the Nuclear Radiation Laboratory at Sant Longowal Institute of Engineering and Technology (SLIET), Sangrur (Punjab), India. Various physical parameters of the laboratory were controlled to avoid any peak shifting during the experiment. The magnitude of statistical errors was reduced below 0.5 % by selecting the real time such that observed counts remained above 40,000 [9]. The background counts and dead-time corrections have been applied on the measured spectra [9].

4.2 Measurements

The photo peak intensity without absorber (Io) and with absorber (I) placed in the γ-ray path from source to detector were measured and corrected for background. For poor geometry (broad-beam), the buildup factor (exposure) is measured by modified the Lambert-Beer equation [10]:

(1)I=BIoeμt=BIBexp=II

Buildup factor (B) is the measure of intensity of the scattered photons from the sample (absorber) reaching the detector [10]. Thus, for a thick absorber (broad-beam geometry), a factor [Io ∗ (S/T)] must be used to modify the Lambert-Beer equation for the intensity of γ-rays reaching the detector as: I′ = Io ⋅ (eμt + S/T), where S/T is the STR; it represents the fraction of scattered photons from the incident γ-ray beam of intensity (Io) and reaching the detector. The theoretical value of B for absorber of thickness (t) can be computed by (2), where μ is the theoretical value of the linear attenuation coefficient of the absorber for monoenergetic γ-ray beam.

(2)Btheo.=1+STexp(μt)
(3)STR(S/T)=(Bexp1)exp(μt)

The B values of the absorber were computed by putting the experimentally recorded data in (1). The measurements for each thickness of the absorber and energy were repeated four times. The arithmetic mean of the measured values of B has been considered as the experimental value (Bexp). For monoenergetic γ-rays, variations of B value with the absorber’s thickness have been studied. Various physical parameters such as mass, length and density of the absorber have been measured using electronic balance (±0.01 g) and digital vernier calipers (±0.02 mm).

The measured data for B were obtained from the experimental measurements of incident and transmitted intensities as explained in (1), and computational (theoretical) data were obtained from the American Nuclear Standards [10]. The measured and computed values of mass attenuation coefficients and buildup factors have been listed in Table 3.

Table 3:

Description of measured values of mass attenuation coefficients and computed values of exposure buildup factors (B) at various thicknesses for the selected samples.

ts (cm)Cs-137, 661.66 keVCo-60, 1173.24 keVCo-60, 1332.50 keV
μexp/ρ (cm2 g−1)BexpBTheo.μexp/ρ (cm2 g−1)BexpBTheo.μexp/ρ (cm2 g−1)BexpBTheo.
CB (μ/ρ = 0.0774 cm2 g−1)(μ/ρ = 0.0586 cm2 g−1)(μ/ρ = 0.0549 cm2 g−1)
20.07741.00001.00000.05861.00001.00000.05491.00001.0000
40.07731.00081.00010.05861.00001.00010.05491.00001.0001
60.07721.00231.00020.05861.00011.00010.05491.00011.0001
80.07711.00411.00030.05851.00081.00020.05491.00011.0002
100.07760.99751.00040.05851.00191.00030.05491.00011.0003
120.07431.06331.00050.05870.99881.00040.05490.99991.0004
140.07511.05521.00070.05841.00541.00050.05490.99991.0005
160.07281.13061.00090.05851.00311.00060.05491.00031.0006
180.07661.02331.00120.05811.01401.00080.05491.00031.0007
200.07661.02591.00160.05831.01171.00100.05491.00041.0009
220.07511.08811.00200.05831.01291.00120.05491.00041.0011
240.07661.03121.00260.05811.01881.00150.05491.00041.0014
260.07281.22081.00320.05831.01521.00180.05491.00051.0016
CW (μ/ρ = 0.0777 cm2 g−1)(μ/ρ = 0.0588 cm2 g−1)(μ/ρ = 0.0551 cm2 g−1)
20.07771.00001.00000.05881.00001.00000.05511.00001.0000
40.07761.00081.00010.05881.00001.00010.05511.00001.0001
60.07731.00431.00020.05881.00011.00010.05511.00011.0001
80.07721.00801.00030.05871.00091.00020.05511.00011.0002
100.07790.99721.00040.05871.00221.00030.05511.00011.0003
120.07611.03461.00050.05890.99871.00040.05510.99991.0004
140.07541.06141.00070.05871.00301.00050.05510.99991.0005
160.07231.17221.00090.05841.01041.00060.05511.00031.0006
180.07461.10761.00120.05871.00391.00080.05511.00041.0007
200.07231.21971.00160.05861.00861.00100.05511.00041.0009
220.07381.16891.00200.05841.01431.00120.05511.00041.0011
240.07691.03461.00260.05871.00521.00150.05511.00051.0014
260.07381.20261.00330.05871.00561.00180.05511.00051.0017
CY (μ/ρ = 0.0768 cm2 g−1)(μ/ρ = 0.0583 cm2 g−1)(μ/ρ = 0.0547 cm2 g−1)
20.07681.00001.00000.05831.00001.00000.05471.00001.0000
40.07671.00081.00010.05831.00001.00010.05471.00001.0001
60.07631.00481.00020.05831.00011.00010.05471.00011.0001
80.07661.00321.00020.05811.00241.00020.05471.00011.0002
100.07700.99731.00040.05821.00201.00030.05471.00011.0003
120.07451.04941.00050.05840.99881.00040.05470.99991.0003
140.07601.01891.00070.05781.01151.00050.05470.99991.0005
160.07301.11301.00090.05821.00331.00060.05471.00031.0006
180.07451.07501.00120.05801.01101.00080.05471.00031.0007
200.07601.02711.00160.05801.01231.00100.05471.00041.0009
220.07451.09241.00200.05801.01351.00120.05471.00041.0011
240.07371.13711.00250.05801.01471.00150.05471.00051.0013
260.07531.07211.00320.05811.01061.00180.05471.00051.0016
RM (μ/ρ = 0.0769 cm2 g−1)(μ/ρ = 0.0584 cm2 g−1)(μ/ρ = 0.0547 cm2 g−1)
20.07691.00001.00000.05841.00001.00000.05471.00001.0000
40.07681.00081.00010.05841.00001.00010.05471.00001.0001
60.07641.00601.00020.05841.00011.00010.05471.00011.0001
80.07651.00571.00020.05821.00261.00020.05471.00011.0002
100.07710.99721.00040.05831.00221.00030.05471.00011.0003
120.07151.12731.00050.05850.99871.00040.05471.00001.0004
140.07151.15001.00070.05791.01221.00050.05470.99991.0005
160.07611.02311.00090.05801.01051.00060.05471.00031.0006
180.07611.02601.00120.05791.01571.00080.05471.00041.0007
200.07541.05871.00160.05831.00431.00100.05471.00101.0009
220.07151.24571.00200.05791.01931.00120.05471.00051.0011
240.07461.10821.00250.05831.00521.00150.05471.00051.0013
260.07461.11771.00320.05821.01131.00180.05471.00051.0016
LS (μ/ρ = 0.0780 cm2 g−1)(μ/ρ = 0.0589 cm2 g−1)(μ/ρ = 0.0552 cm2 g−1)
20.07801.00001.00000.05891.00001.00000.05521.00001.0000
40.07781.00081.00010.05891.00001.00010.05521.00001.0001
60.07781.00151.00020.05891.00001.00010.05521.00001.0001
80.07751.00471.00020.05881.00101.00020.05521.00001.0002
100.07820.99831.00040.05881.00131.00030.05521.00011.0003
120.07721.01011.00050.05900.99921.00040.05521.00001.0003
140.07721.01181.00070.05841.00711.00050.05521.00001.0004
160.07331.08361.00090.05881.00201.00060.05521.00021.0006
180.07491.06211.00120.05881.00231.00080.05521.00021.0007
200.07491.06921.00150.05841.01021.00100.05521.00041.0009
220.07331.11671.00190.05881.00281.00120.05521.00041.0011
240.07331.12801.00250.05841.01221.00140.05521.00031.0013
260.07491.09091.00310.05881.00331.00180.05521.00031.0016
PP (μ/ρ = 0.0776 cm2 g−1)(μ/ρ = 0.0588 cm2 g−1)(μ/ρ = 0.0551 cm2 g−1)
20.07761.00001.00000.05881.00001.00000.05511.00001.0000
40.07741.00081.00010.05881.00001.00010.05511.00001.0001
60.07741.00121.00020.05881.00001.00010.05511.00001.0001
80.07751.00081.00020.05871.00121.00020.05511.00011.0002
100.07780.99811.00040.05871.00151.00030.05511.00011.0003
120.07681.01171.00050.05890.99911.00040.05511.00001.0003
140.07531.04171.00070.05871.00211.00050.05511.00001.0005
160.07291.09781.00090.05861.00471.00060.05511.00021.0006
180.07291.11071.00120.05831.01071.00080.05511.00031.0007
200.07531.06011.00150.05841.00891.00100.05511.00051.0009
220.07451.08931.00200.05861.00651.00120.05511.00051.0011
240.07221.17751.00250.05831.01431.00150.05511.00031.0013
260.07221.19361.00310.05871.00381.00180.05511.00041.0016

5 Results and Discussion

Figure 2 describes the variation of STR and θSC with absorber thickness (CW) by keeping constant values for the size of the collimator apertures, SA and SD. The value of STR for which the Midgley condition [8] was satisfied is termed as the critical value of STR (CSTR). It is indicated from Figure 2 that for the CW sample, CSTR is 0.0075 and the corresponding absorber thickness, i.e. optimum thickness = 24 mm (2.18 mfp). Thus, for accurate μ measurement for the energy range (661.66–1332.5 keV), the experimental setup should be such that its STR remains below the CSTR. Thus, the STR includes various parameters such as absorber’s thickness, collimator aperture sizes, buildup factor and γ-ray energy, which otherwise are required to quantify the nature of geometry for an experimental setup.

Figures 3 and 4 describe the simultaneous variations in STR and θSC for the absorber (CW) with different aperture values of C2 and C3, respectively, for γ-ray energy 661.66 keV. Other GPs have been kept constant during these variations. The inverse relationship has been found between the size of the aperture and the optimum thickness value of the absorber in light of the Midgley condition [8].

Figure 3: For monoenergetic γ-rays (661.66 keV), the description of variations in scatter acceptance angle with CW sample thickness and collimator C3’s aperture.
Figure 3:

For monoenergetic γ-rays (661.66 keV), the description of variations in scatter acceptance angle with CW sample thickness and collimator C3’s aperture.

Figure 4: For monoenergetic γ-rays (661.66 keV), the description of variations in scatter acceptance angle with CW sample thickness and collimator C2’s aperture.
Figure 4:

For monoenergetic γ-rays (661.66 keV), the description of variations in scatter acceptance angle with CW sample thickness and collimator C2’s aperture.

Figure 5 provides the simultaneous variations of STR and θSC with absorber thickness for three γ-ray energies. The similar trend of variation in STR with absorber thickness at three γ-ray energies for the same geometrical setup and GPs has been observed.

Figure 5: For fixed geometry, description of the combined variations in STR (%) and θSC with the absorber’s (CW) thickness at three γ-ray energies.
Figure 5:

For fixed geometry, description of the combined variations in STR (%) and θSC with the absorber’s (CW) thickness at three γ-ray energies.

6 Conclusions

It has been concluded that the STR provides a quantitative description of the nature of γ-ray transmission geometry used for the measurements of attenuation coefficients of materials. It summarises multiple parameters related to the geometry such as thickness of sample, size of collimator apertures, SA, STD, AD, θSC and B. STR provides better information of scattered γ-rays by shielding material than buildup factor (B). In addition, the CSTR can serve as the borderline between the narrow-beam and broad-beam transmission geometries. For a given energy range (661.66–1332.50 keV), it has been found that for the chosen low-Z samples, CSTR is 0.075.

This study can be extended to the wider energy range and for high-Z materials after the reestablishment of American Nuclear Standards [10].

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Supplementary Material

The online version of this article offers supplementary material (DOI: https://doi.org/10.1515/zna-2018-0282).


Received: 2018-06-05
Accepted: 2018-08-21
Published Online: 2018-09-20
Published in Print: 2018-11-27

©2018 Walter de Gruyter GmbH, Berlin/Boston

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