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Effect of TeO2 addition on the gamma radiation shielding competence and
mechanical properties of boro-tellurite glass: an experimental approach
Article in Journal of Materials Research and Technology · March 2022
DOI: 10.1016/j.jmrt.2022.02.130
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Available online at www.sciencedirect.com
journal homepage: www.elsevier.com/locate/jmrt
Original Article
Effect of TeO2 addition on the gamma radiation
shielding competence and mechanical properties
of boro-tellurite glass: an experimental approach
M.I. Sayyed a,b,*, Nidal Dwaikat c,d, M.H.A. Mhareb e,f,
Ashwitha Nancy D'Souza g, Nouf Almousa h, Y.S.M. Alajerami i,
Fahad Almasoud j,k, K.A. Naseer l,**, Sudha D. Kamath g,
Mayeen Uddin Khandaker m, Hamid Osman n, Sultan Alamri n
a
Department of Physics, Faculty of Science, Isra University, Amman, Jordan
Department of Nuclear Medicine Research, Institute for Research and Medical Consultations (IRMC), Imam
Abdulrahman Bin Faisal University (IAU), Dammam, Saudi Arabia
c
Department of Physics, College of Engineering and Physics, King Fahd University of Petroleum & Minerals,
Dhahran, 31261, Saudi Arabia
d
Interdisciplinary Research Center for Advanced Materials, King Fahd University of Peroleum & Minerals, Dhahran,
Saudi Arabia
e
Department of Physics, College of Science, Imam Abdulrahman Bin Faisal University, P.O. Box 1982, 31441,
Dammam, Saudi Arabia
f
Basic and Applied Scientific Research Center, Imam Abdulrahman Bin Faisal University, PO Box 1982, 31441,
Dammam, Saudi Arabia
g
Department of Physics, Manipal Institute of Technology, Manipal Academy of Higher Education, Manipal, India
h
Department of Physics, College of Science, Princess Nourah Bint Abdulrahman University, P.O. Box 84428, Riyadh,
11671, Saudi Arabia
i
Medical Imaging Department, Applied Medical Sciences Faculty, Al Azhar University-Gaza, Palestine
j
Nuclear Science Research Institute (NSRI), King Abdulaziz City for Science and Technology (KACST), Riyadh, 11442,
Saudi Arabia
k
Department of Soil Sciences, College of Food and Agricultural Sciences, King Saud University, Riyadh, 12372, Saudi
Arabia
l
Department of Physics, Farook College (Autonomous), Kozhikode, 673632, India
m
Centre for Applied Physics and Radiation Technologies, School of Engineering and Technology, Sunway University,
47500, Bandar Sunway, Selangor, Malaysia
n
Department of Radiological Sciences, College of Applied Medical Sciences, Taif University, Taif 21944, Saudi Arabia
b
article info
abstract
Article history:
We experimentally investigated the effect of TeO2 on the radiation-shielding competence
Received 3 January 2022
of a BaOeMoO3eB2O3 glass system. Two gamma-ray sources (137Cs and
Accepted 27 February 2022
scintillator detector (sodium iodide (NaI(Tl)) were utilized to measure the attenuation
Available online 4 March 2022
factors of the prepared glass at 0.184, 0.280, 0.662, 0.710, and 0.810 MeV. The measured
166
Ho) and a
* Corresponding author.
** Corresponding author.
E-mail addresses: dr.mabualssayed@gmail.com (M.I. Sayyed), naseerka.phy6@gmail.com (K.A. Naseer).
https://doi.org/10.1016/j.jmrt.2022.02.130
2238-7854/© 2022 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license (http://
creativecommons.org/licenses/by-nc-nd/4.0/).
1018
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
Keywords:
mass attenuation coefficient agreed well with the theoretically calculated values for all the
Boro-tellurite glass
prepared samples. The linear attenuation coefficient (LAC) results demonstrated that as
Radiation shielding
the photon energy increased, the penetrating ability of the photons through the glass
Scintillator detector
increased. The LAC values of boro-tellurite glass at 662 keV were compared with those of
Tenth-value layer
other tellurite glass. We found that MTB1 glass produced better attenuation results than
10Li2Oe20K2Oe50B2O3e20TeO2 glass, whereas MTB5 glass with 70 mol% TeO2 had an LAC
value greater than that of 90.4TeO2-9.6ZnOe4NiO glass. The half-value layer (HVL)
increased continuously with photon energy. For MTB1 glass, the HVL increased from
0.3609 cm at 184 keV to 1.6078 cm at 662 keV and 1.8381 cm at 810 keV. The lowest set of
HVL values was observed for MTB5 glass, which confirmed its superior attenuation properties compared to other compositions. The transmission factor (TF) was also calculated;
MTB5 glass had the lowest TF values, which revealed that MTB5 provided the best shield.
For glass with a thickness of 1 cm, the TF was 75.8% for MTB1, 72.8% for MTB2, 70.6% for
MTB3, 68.8% for MTB4, and 63.4% for MTB5.
© 2022 The Authors. Published by Elsevier B.V. This is an open access article under the CC
BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
1.
Introduction
Human radiation exposure can occur in nuclear research facilities, nuclear reactors, during radiological diagnoses, and in
various other applications. High-energy ionizing radiation can
be extremely harmful to human tissue and living cells because
it ionizes the atoms it comes in contact with by ripping away
their electrons. To safely harness the benefits of radiation,
radiation shields are placed between the radiation source and
the person or object that needs to be protected [1e5]. The
creation of shields that absorb gamma radiation has attracted
the interest of researchers in the field because of the high
penetration ability of this form of radiation. The field of radiation shielding strives to prevent nuclear accidents and radiation leaks in the future and ensure safe transportation and
storage of nuclear waste. An effective radiation shield should
be defined by its ability to protect against these forms of
harmful radiation [6e10].
A variety radiation shields are used, depending on the requirements of the desired implementation. Concrete is a
common shielding substance owing to its low cost and
versatility. Although concrete offers multiple advantages as a
radiation shield, it tends to develop cracks over long periods of
exposure to radiation because of the tensile stress produced,
loses water content due to heating, and is unable to allow
visible light transmission. Owing to these general disadvantages, researchers have attempted to discover alternative
materials that can more effectively shield against incoming
photons [11,12].
Recently, glass has gained immense attention because of
its transparency to visible light, which is a property that other
shielding materials lack. Additionally, the composition of the
glass system can be varied significantly by doping different
heavy metal oxides (HMOs) into the glass matrix [13e16]. By
introducing these HMOs into glass, their radiation shielding
properties are greatly enhanced, and the glass can absorb
gamma rays and neutrons more effectively. There are three
types of HMOs that act differently on the glass matrix: glass
network formers, glass network modifiers, and glass
intermediates. When glass formers are introduced into a glass
system, they form the backbone of the network, whereas glass
modifiers alter the glass network by creating non-bridging
oxygen but are not part of the network's backbone. Glass intermediates have properties similar to those of formers and
modifiers, and these properties vary depending on the
composition of the glass matrix [17e20].
Tellurite is a glass intermediate with great promise in the
radiation-shielding field owing to its high thermal stability,
high density, high electrical conductivity, low melting temperature, and significant moisture and corrosion resistance
[21,22]. By itself, TeO2 cannot form a glass system and requires
additional glass modifiers to form stable glass. Other HMOs
such as PbO, MoO3, WO3, BaO, and Bi2O3 can be added to tellurite glass to improve their optical, thermal, and mechanical
properties [23e27]. For instance, MoO3, can be a helpful additive
because it can act as either a glass modifier or glass former.
HMOs are beneficial in radiation shielding because they tend to
increase the density of the glass system, have a broad attenuation cross-section, and maintain good optical and mechanical
properties [28,29]. TeO2 is a heavy glass former, and it has been
used in radiation shielding because of its high ability to absorb
gamma rays compared with other glass formers. Tijani et al.
[30] studied the shielding features of transparent tellurite glass
within diagnostic energy ranges of 20, 30, 40, and 60 keV. The
radiation-shielding features were evaluated using the XCOM
program, and the results obtained for the glass samples were
compared with those of the concrete samples. The fabricated
glass exhibited better shielding results than those of the concrete samples. Al-Buriahi et al. [31] reported the radiation
shielding and mechanical features of (100-x)TeO2-xZnO-4NiO
glass. The radiation shielding properties were investigated
theoretically using the Phy-X program and Geant4 simulation,
and the studied parameters included the mass attenuation
coefficient (m/r) and transmission factor (TF). The addition of
zinc oxide (ZnO) to the glass system directly affected the mechanical and radiation shielding properties. Rammah et al. [32]
evaluated the radiation-shielding capacity of a new group of
tellurite glass systems. The glass system contained both vanadium and antimonates. The impact of antimony oxide
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
Table 1 e The composition ratio and density values of
20BaOeMoO3-(70-x)B2O3:xTeO2.
Sample
codes
MTB1
MTB2
MTB3
MTB4
MTB5
Composition ratio (mole%)
BaO
MoO3
B2O3
TeO2
20
20
20
20
20
10
10
10
10
10
70
52.5
35
17.5
0
0
17.5
35
52.5
70
Density
(g cm3)
3.4446
3.9320
4.3091
4.6314
5.5057
1019
explored for fabricated glass. The addition of Sb2O3 to the tellurite glass system led to an increase in the linear attenuation
coefficient (LAC), whereas the fast neutron removal crosssection (SR) reduced with increasing Sb2O3 content. Sayyed
et al. [27] reported the radiation shielding of a novel tellurite
glass
system
((60-x)TeO2-10GeO2-20ZnOe10BaO-xBi2O3).
MCNP-5 was used to study radiation-shielding features within
energies ranging from 0.015 to 15 MeV. The replacement of
TeO2 with bismuth oxide (Bi2O3) enhanced the gammashielding features and reduced SR. Numerous studies have
been conducted on tellurite glass in the radiation-shielding
field [9,21,22,24,26,27,33]. In this study, we experimentally
investigated the influence of TeO2 on the radiation-shielding
competence of a BaOeMoO3eB2O3eTeO2 glass system.
2.
Materials and methods
2.1.
Glass fabrication
A series of boro-tellurite glasses were prepared using the
traditional melt-quenching process, and different raw oxides
such as tellurium oxide (TeO2), boron oxide (B2O3), barium oxide
(BaO), and molybdenum oxide (MoO3) were utilized for this
purpose. These oxides were determined at specific ratios, as
listed in Table 1. The raw oxides were weighed carefully, mixed
to obtain a homogenous mixture, and placed in an alumina
crucible. Subsequently, the homogenous mixture was introduced into an electrical furnace at 1100 C for 40 min and stirred
periodically to discharge bubbles during the melting process.
The molten mixture was then annealed inside another electrical furnace at 450 C for 3 h, and a steel plate was used to pour
the molten mixture. The same procedure has been applied to
other types of glass systems [33,34].
2.2.
Fig. 1 e Photograph of the experimental setup.
(Sb2O3) on the radiation shielding features was studied using
WinXcom and a Monte Carlo simulation code (MCNP- 5) within
an energy range of 15 keV to 15 MeV. The projected range and
stopping power for protons and alpha particles were also
Glass density
The Archimedes concept was employed to determine the
current glass, and purified water was used as the submersion
liquid. A Radwag balance with a particular density kit system
was utilized for this purpose. The samples were weighed in air
(A) and fluid (B) to calculate the density (r) experimentally, and
the following relation was employed:
r¼
A
:
AB
ð1Þ
Fig. 2 e Schematic diagram of the detection system.
1020
(
(
(
(
(
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
Fig. 3 e The experimental and XCOM mass attenuation coefficients of the studied glass.
2.3.
Experimental radiation shielding
A well-designed irradiation setup at the King Fahd University
of Petroleum & Minerals (KFUPM) was used to investigate the
gamma-radiation shielding properties of the materials. It
consists of a narrow gamma-ray beam collimator (three
collimation steps) and gamma-ray spectrometer, as shown in
Fig. 1. The spectrometer is composed of a (300 300 ) NaI (Tl)
detector, preamplifier, high-voltage power supply, amplifier
(Ortec 572 A), 8 k multichannel analyzer (Amptek MCA8000D),
and computer (see Fig. 2). The detector is housed with layers of
10-cm thick lead bricks to minimize the background. The
resolution (FWHM) of the detector at 662 keV of 137Cs is 7%.
The collimator was fabricated by drilling three apertures of
different sizes in the center of the three lead bricks (see Fig. 1).
The centers of the apertures were aligned with the center of
the detector using a laser pointer. As described in a previous
publication [35], the chi-squared test was used to check the
performance of the detection system. In this study, two
familiar radioactive sources, Cs-137 (E_g ¼ 662 keV) with an
activity of 16.6 kBq and Ho-166 m (E_g ¼ 184, 280, 710, and
810 keV) with an activity of 29.6 kBq were used to calibrate the
system and investigate the gamma shielding property of glass
samples.
The gamma spectra of the Cs-137 and Ho-166 m sources
were recorded with and without the samples for 1 h using the
previously mentioned MCA, and DPPMCA computer-based
software was used to analyze the spectra. The background
was measured during the same period. After the subtraction
of the background, the area under the photopeak (gross count)
of the gamma line transitions at 662 (Cs-137), 184, 280, 710,
0.55
0.50
2.4
MTB1
MTB2
MTB3
MTB4
MTB5
1.2
0.8
0.35
0.30
0.25
0.4
0.0
100
0.40
-1
1.6
0.45
LAC (cm )
LAC (cm-1)
2.0
0.20
200
300
400
500
600
700
800
900
Photon energy (keV)
Fig. 4 e The linear attenuation coefficient of the studied
glass.
-10
0
10
20
30
40
50
60
70
80
TeO2 (mol%)
Fig. 5 e Comparison of the linear attenuation coefficient of
the studied glass and other tellurite glass in literature.
1021
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
and 810 keV (Ho-166 m), with a 95% confidence level, was
measured and used to calculate the linear attenuation coefficient (m) using
2.4
LAC
;
MAC ¼
r
ln 2
;
LAC
ð4Þ
MFP ¼
1
;
LAC
ð5Þ
TVL ¼
ln10
;
LAC
ð6Þ
RBE ¼ 1 eLAC x t x 100ð%Þ;
ð7Þ
ð8Þ
where t is the thickness of the glass. The mass stopping power
(MSP) and projected range (PR) were evaluated using the SIRM
program [36], and the removal cross-section of fast neutrons
(SR) was determined using the Phy-X program [37].
3.
Results and discussion
3.1.
Radiation shielding features
Table 1 shows the chemical composition, corresponding
sample codes, and density values of the synthesized borotellurite glass. The density values were found to increase
with the successive addition of TeO2, which is a consequence
of replacing B2O3 molecules of lower molecular weight
(M ¼ 69.63 g/mol) with TeO2 molecules (M ¼ 159.6 g/mol).
Figure 3 shows a comparative representation of m/r determined experimentally and theoretically from the XCOM
database. It is clear that the values measured from both
methods agreed well for all glass samples at all energies, with
minimal difference between the values.
With the help of theoretical m/r values, another essential
parameter, the LAC, was calculated by multiplying with the
density values. The computed LAC values (Fig. 4) also showed
a trend similar to that of m/r. As the photon energy increased,
the LAC values decreased for glass of all compositions. This is
MTB1
MTB2
MTB3
MTB4
MTB5
2.0
1.6
1.2
0.8
0.4
0.0
200
400
600
800
Photon energy (keV)
ð3Þ
HVL ¼
I
x100 ¼ eLAC x t x 100ð%Þ;
Io
HVL (cm)
ð2Þ
where x is the thickness of the sample (cm), which ranges
from 0.199 to 0.496 cm for MTB1 to MTB5, m is the linear
attenuation (cm1), I0 is the photopeak area at specified energy
lines after the subtraction of the background with no sample
between the source and the detector, and I is the photopeak
area after subtraction of the background with the sample between the source and the detector. Based on the LAC results,
the tenth value layer (TVL), mean free path (MFP), half-value
layer (HVL), radiation protection efficiency (RBE), mass attenuation coefficient (MAC), and TF were obtained.
TF ¼
2.8
Fig. 6 e The half value layer of the studied glass.
caused by the penetration of high-energy photons into the
material with greater ease and without interacting with
matter, which in turn decreases the probability of photon
interaction. However, the trend followed by the decreasing
LAC values can be split into two parts, one at low and the other
at high energies. The sudden decrease observed at lower energies is due to the photoelectric absorption of photons by the
glass material. Furthermore, at higher energies, the LAC
decreased at a slower rate because of the dominance of the
Compton scattering process [38e40]. Figure 4 also shows that
at each energy, the LAC increased with an increase in TeO2
concentration, and MTB5 glass showed the highest attenuation property. This was purely due to the contribution of TeO2
in enhancing the molecular weight and density of the glass
samples. Figure 4 clearly shows the increasing LAC values at
different photon energies with increasing number of TeO2
molecules.
In Fig. 5, the LAC values of boro-tellurite glass at 662 keV
are compared with those of other tellurite glass found in
literature [25,31,38,41e44]. All the prepared glass have higher
LACs and thus better shielding ability than 10Li2Oe20K2Oe50B2O3e20TeO2 [41] and 39.5B2O3e25TeO2e15BaOe10Na2
10
9
8
TVL (cm)
I ¼ Io exm ;
3.2
MTB1
MTB2
MTB3
MTB4
MTB5
7
6
5
4
3
2
1
0
200
400
600
800
Photon energy (keV)
Fig. 7 e The tenth value layer of the studied glass.
1022
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
4.8
184
280
662
720
810
4.2
MFP (cm)
3.6
3.0
2.4
1.8
1.2
0.6
0.0
3.0
3.5
4.0
4.5
5.0
5.5
3
Density (g/cm )
Fig. 8 e The mean free path of the studied glass as a
function of density.
Oe10K2O-0.5Dy2O3 [42] glass. MTB5 (glass with 70 mol% TeO2)
has an LAC close to that of 10WO3e10MoO3e80TeO2 [38] glass
and a slightly higher LAC than the 90.4TeO2-9.6ZnOe4NiO [31]
sample. Additionally, MTB5 glass has a higher LAC value than
10SrOe25B2O3e30TeO2e20BaOe15MoO3 [25] and 60TeO2e10SrOe30B2O3 [44] glass, but a lower LAC than the 29.5B2O3e30TeO2e20PbF2e20PbO-0.5Dy2O3 [43] sample. This
comparison demonstrates the importance of developing glass
with relatively high amounts of TeO2 to obtain glass with
better radiation attenuation properties than the available
boro-tellurite glass.
The HVL and TVL are considered essential shielding parameters for evaluating fabricated glass. The influence of
photon energy on the HVL and TVL values was analyzed with
the help of the graphs shown in Figs. 6 and 7. It is known that
glass with lower HVL and TVL values can block radiation
photons with minimal thickness. In Figs. 6 and 7, both parameters increase continuously with photon energy. For MTB1
glass, the HVL increased from 0.3609 cm at 184 keV to
1.6078 cm at 662 keV and 1.8381 cm at 810 keV. This indicates
Fig. 9 e The transmission factor of the prepared glass.
Fig. 10 e The radiation protection efficiency of the prepared
glass.
that a greater thickness is required for the attenuation of highenergy photons. In addition, in terms of TeO2 content, the HVL
decreased from 2.772 cm to 2.5018 cme1.8381 cm for MTB1,
MTB3, and MTB5, respectively. Hence, the lowest set of HVL
values observed for MTB5 glass confirmed its superior attenuation properties compared to other compositions. Figure 8
shows a graph of the MFP values as a function of density at
different photon energies. As the density increased, the MFP
values decreased in each case, indicating the significance of
adding TeO2 molecules to the glass. The minimum MFP values
exhibited at an energy of 0.184 MeV suggest that the capacity
of the studied glass to attenuate low-energy photons is greater
than that of high-energy photons. Because the density value
of 5.5057 g cm3 produced the lowest MFP values at all
Fig. 11 e The projected range of the prepared glass.
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
Fig. 12 e The mass stopping power of the prepared glass.
energies, the corresponding MTB5 glass can act as a better
shielding agent than the others.
The number of photons that can penetrate MTB glass can
be estimated using the TF. The TF shows the ratio of the real
number of photons transmitted from the first side of the glass
to the number of photons emitted from the other side of the
radioisotope source. Accordingly, to develop novel shields, we
attempted to identify a sample with a low TF. For the current
MTB glass, we present the results of the TF for five thicknesses
(1e5 cm) in Fig. 9, which clearly shows the role of the sample
composition and its thickness on the TF. First, MTB5 was the
best attenuator, according to Fig. 9, because it has the lowest
TF values. In contrast, MTB1 was the worst shield owing to its
high TF. These results are consistent with those concluded
1023
from previous figures. Owing to the high quantity of TeO2
(70 mol%), the chances of collision between photons and the
atoms of MTB5 are high. Therefore, most photons are absorbed or scattered by MTB5, and the number of photons transmitted from the first side to the other side is small; hence, the
TF value is low. Regarding the effect of thickness on the TF for
a certain composition, it is evident that increasing the thickness has an inverse influence on the TF values. For a glass
with a thickness of 1 cm, the TF was 75.8% for MTB1, 72.8% for
MTB2, 70.6% for MTB3, 68.8% for MTB4, and 63.4% for MTB5,
and these values decreased to 57.5%, 53.0%, 49.8%, 47.3%, and
40.2%, respectively, for the aforementioned glass with a
thickness of 2 cm. The TF results indicate that, to develop
glass with the oxides used in this study and with the same
concentrations given in Table 1, we must select a thickness
greater than 3 cm. In this case, the TF was less than 30%
(except for MTB1, where the TF for a thickness of 4 cm was
33%). Therefore, glass with a high quantity of TeO2 (more than
50 mol%) and containing 20 mol% of BaO and 10 mol% of MoO3
can attenuate most of the incoming radiation if the thickness
exceeds 3 cm.
Figure 10 shows the radiation protection efficiency (RPE) of
the MTB glass at different thicknesses; this can be used to
confirm the relationship between the thickness of the glass
and their attenuation ability. The RPE increased rapidly as the
thickness of the glass increased from 1 cm to 5 cm; this is a
result of the increase in photon interaction with the atoms as
the thickness increases, which boosts the attenuation performance of the sample. For MTB1, the RPE was approximately
24% at 1 cm, which increased to approximately 75% at a
thickness of 5 cm. In addition to thickness, the composition of
the glass also affected the RPE. MTB5 glass was the best
attenuator owing to its high RPE. At 4 and 5 cm, the RPE was
greater than 75%, suggesting that most photons cannot pass
through high-thickness MTB5.
Figures 11 and 12 display the MSP and PR of protons,
respectively. From Fig. 11, the distance range of the proton
particles inside the glass samples can be determined before
their energy is deposited. The PR of protons was higher for the
Fig. 13 e The neutron fast removal section (SR) of (a) the fabricated glass and (b) the MTB4 and MTB5 samples in comparison
with different materials such as PLPG3, ordinary concrete (OC), and PLPG0.
1024
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
Table 2 e Elastic properties of the studied glass.
Elastic properties
Young's modulus
(E in GPa)
Bulk modulus
(K in GPa)
Shear modulus
(G in GPa)
Longitudinal modulus
(L in GPa)
Hardness
(H in GPa)
Fractal bond
connectivity (d)
Total packing
density (Vt)
Poisson's ratio (s)
MTB1
MTB2
MTB3
MTB4
MTB5
56.20
76.84
101.36
129.68
157.88
24.07
47.03
87.24
157.81
280.13
25.30
31.29
38.80
47.57
56.14
57.80
88.76
138.97
221.23
354.99
6.559
5.673
5.019
4.345
3.519
4.205
2.661
1.779
1.206
0.802
0.357
0.510
0.717
1.014
1.479
0.111
0.228
0.306
0.363
0.406
MTB1 samples than for the other samples, and the PR
decreased with decreasing TeO2 content. For example, the PR
values at 0.01 MeV were 2.0828, 1.9285, 1.7692, 1.6535, and
1.5032 mm for MTB1, MTB2, MTB3, MTB4, and MTB5, respectively. Additionally, the effect of kinetic energy on the PR
values is clear; the PR values at 10 and 1 MeV for MTB5 were
1015 and 58.5443 mm, respectively. The increase in kinetic
energy for the proton particles led to a higher penetration of
protons inside the glass samples. Figure 12 illustrates the
relationship between the kinetic energy and MSP for the
proton particles of the fabricated glass. At 0.8 MeV, the MSP
values were higher, and the MSP for the MTB1 sample was
superior to that of the other samples owing to the inverse
dependence of MSP on density. The MTB1 sample had the
lowest density compared to the other samples, and the
compatibility between the density and MSP led to these
results. The MSP values for the samples under study at 10 MeV
were 1.5499, 1.4351, 1.3166, 1.2191, and 0.8127 MeV cm2/g,
whereas the MSP for lead (Pb) and water at the same energy
was 17.5 and 47 MeV cm2/g. In general, heavy atoms and
compounds have a lower ability to slow down charged particles (protons) because they tie their electrons strongly with
the inner shell, reducing the ability to absorb charged particles. Thus, it can be concluded that MTB5 has the highest efficiency for stopping protons.
The neutron fast removal section (SR) results for the
fabricated glass are shown in Fig. 13-a. Fig. 13-b shows that the
MTB4 and MTB5 samples were compared with various substances such as PLPG3, ordinary concrete (OC), and PLPG0.
Fig. 13-a shows that the values of SR decrease with increasing
TeO2 to glass system up to MTB4; after this, an enhancement
of the SR values can be observed for MTB5. The glass systems
for MTB1 and MTB5 are different because MTB1 is based on
borate, which is suitable for absorbing neutrons, whereas the
MTB5 sample is based on tellurate, which is less capable of
absorbing neutrons than borate. The mixing between borate
and tellurate in this glass system led to a reduction in SR, as
evident in samples MTB2, MTB3, and MTB4. This reduction
was expected owing to the replacement of the high-ability
neutron absorber (B) with a lower-ability neutron absorber
(Te). In contrast, Fig. 13-b displays SR for MTB4, MTB5, and
different materials. The results show the superiority of MTB4
and MTB5 over other materials, indicating the excellent ability
of current glass to absorb neutrons.
3.2.
Elastic properties
The investigation of the elastic properties of glass emerges
from the dependence of these properties on the organization
and underlying conservation of the glass network. These also
350
150
250
100
200
150
100
50
50
Longitudinal modulus (L in GPa) &
Bulk modulus (K in GPa)
Young's modulus (E in GPa) &
Shear modulus (G in GPa)
300
0
0.0
17.5
35.0
52.5
70.0
TeO2 content (mol %)
Fig. 14 e The variation in the Young's modulus (E), shear modulus (G), bulk modulus (K) and longitudinal modulus (L) of the
studied glass.
1025
6.5
0.40
6.0
0.35
5.5
0.30
5.0
0.25
4.5
0.20
4.0
0.15
3.5
Poisson's ratio ( )
Hardness (H in GPa)
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
0.10
0.0
17.5
35.0
52.5
70.0
TeO2 content (mol %)
Fig. 15 e The hardness and Poisson's ratio with respect to TeO2 content.
determine the mechanical conduct of the glass and provide
data regarding the compound's glass construction and solidstate movement related to the interatomic bonds inside the
setup [45,46]. In particular, they react to geometrical and
arrangement changes due to the doping of modifiers [47,48].
The versatile properties, which are broadly consistent, show
significant changes over the glass transition temperature
because, above this transition temperature, the network disintegrates, and the non-elastic nature decreases. Examining
the elastic moduli of the glass structure plays a significant role
in dissecting the glass transition [49]. Utilizing theoretical
models gathered from literature [50e52], elastic constants (E,
K, G, L), the total packing density (Vt), hardness (H), molar
atomic volume (Va), fractal bond connectivity, and Poisson's
ratio (s) were estimated for the fabricated glass to obtain a
detailed picture of their design, as shown in Table 2. These
parameters were assessed as elements of the glass arrangement, packing density, and dissociation energy per unit volume (Gi) of the glass. Typical values of dissociation energy
were obtained from literature [47]. The calculated s values
noted in the range 0.111e0.406 exhibited an increase from the
low-to high-order glass as a result of the expanded compaction concentration. The 20NBDB glass had a lower s value,
which indicates a measurable effect on s. Therefore, from s,
the hardness (H) of the glass was assessed, which decreased
with an increase in the amount of TeO2, as shown in Fig. 14.
The elastic constants, represented by the intermediate-range
structural units (fragility) of the glass, were estimated. The
extra oxygen added through the modifiers delivers superstructural units of borate, which leads to the development of
NBOs in the glass design. As the amount of TeO2 increased, the
moduli E, K, G, and L increased, indicating the production of
BOs in the glass framework. The overall increase in the elastic
constants of the concentrated glass is shown in Fig. 15. Fractal
bond connectivity (d) is a significant device for examining the
adjustment of the dimensionality of glass.
4.
Conclusion
We reported the influence of TeO2 on MAC, Zeff, and other
shielding factors of a BaOeMoO3eB2O3 glass system using a
scintillator detector and two gamma-ray sources (137Cs and
166
Ho). In addition, we report the influence of glass thickness on
the TF. The LAC values decreased as the energy increased from
0.184 to 0.81 MeV for all glass compositions; hence, the radiation blocking competence of glass was weakened by increasing
the energy. At 0.662 MeV, the LAC value of the MTB5 glass was
more significant than that of the 90.4TeO2-9.6ZnOe4NiO glass
and slightly lower than that of the 10WO3e10MoO3e80TeO2
glass. The minimum MFP values were found for an energy of
0.184 MeV, which suggests that these glass are capable of
absorbing low-energy photons better than high-energy photons. The TF values indicate that MTB5 was the best attenuator,
whereas MTB1 was the worst shield. The main conclusion of
this study is that glass with a high quantity of TeO2 (more than
50 mol%) and containing 20 mol% of BaO and 10 mol% of MoO3
can attenuate most of the incoming radiation if the thickness
exceeds 3 cm. Extremely dense MTB glass were found to
possess elevated E, K, L, and G values, indicating their better
cross-linked structure.
Declaration of Competing Interest
The authors declare that they have no known competing
financial interests or personal relationships that could have
appeared to influence the work reported in this paper.
1026
j o u r n a l o f m a t e r i a l s r e s e a r c h a n d t e c h n o l o g y 2 0 2 2 ; 1 8 : 1 0 1 7 e1 0 2 7
Acknowledgement
[14]
We deeply acknowledge Taif University for supporting the
researchers through Taif University Researchers Supporting
Project number (TURSP-2020/287), Taif University, Taif, Saudi
Arabia. The authors express their gratitude to Princess Nourah
bint Abdulrahman University Researchers Supporting Project
number (PNURSP2022R111), Princess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia.
[15]
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