Mass Stopping Research Articles

Influence of Ag2O insertion on alpha, proton and γ-rays safety features of TeO2.ZnO.Na2O glasses: Potential use for nuclear medicine applications

Influence of Ag2O insertion on the nuclear radiation safety features of sodium zinc-tellurite glasses has been reported. To this end, six glasses of 80TeO2.10ZnO.[(10-x)Na2O.xAg2O)]: x = 0–10 mol% abbreviated as (TZNA0-TZNA10) have been chosen. The mass attenuation coefficients (μ/ρ) were simulated using MCNP-5 simulation codes and the results were matched with which calculated via XCOM software. In term of μ/ρ, half value layer, mean free path (HVL, MFP), effective atomic number, equivalent atomic number (Zeff, Zeq), exposure and energy absorption buildup factors (EBF, EABF), Mass Stopping Power (MSP) and the Projected range (PR) of the proton and alpha particles have been evaluated. Results reveal that the increase in Ag2O from 0–10 mol % enhances the attenuation properties of TZNA glasses and the μ/ρ takes the order that TZNA10>TZNA8>TZNA6>TZNA4>TZNA2>TZNA0. The insertion of Ag2O in the TZNA glasses reduced the HVL, MFP, and exposure buildup factors (EBF and EABF). In addition, the smallest values of MSP and PR for proton and alpha particles observed for TZNA10 glass. Moreover, the insertion of Ag2O leads to enhance the radiation safety capability of the TZNA glasses to apply in various medical applications.

Radiation shielding properties of Nd0.6Sr0.4Mn1−yNiyO3 substitute with different concentrations of nickle

In this work, we investigate the effect of Ni concentration on several shielding properties of Nd0.6Sr0.4Mn1−yNiyO3 (0.00 ≤ y ≤ 0.20) perovskite ceramic for possible use as radiation shielding materials. X-ray diffraction (XRD) analysis revealed that these ceramics have the orthorhombic structure with group space Pnma over a wide range of Ni-substitutions. Moreover, the analysis showed a nearly linear decrease in the lattice parameters and the unit cell volume (V) causing a gradual increase in the packing density with increasing Ni concentration. The shielding features for photons, neutrons, and protons of all ceramic samples were assessed. The mass attenuation coefficient (MAC) was computed at 0.1, 0.6, 1.25, 5 and 15 MeV by utilizing (MCNP) (version 5.0); the results were compared with the corresponding values obtained using Phy-X and XCOM program. The results obtained showed slight enhancement with increasing Ni contents. The substitution of Ni leads to progressive enhancement in effective removal cross-section of fast neutron (∑R) values. Whereas the values of Mass Stopping Power (MSP) and projected range for the protons showed a gradual reduction with increasing Ni concentration. These findings suggest that the current ceramic samples can be useful as radiation shielding materials.

Nuclear radiation shielding using barium borosilicate glass ceramics

This study assessed the ability of glass ceramics that included zirconolite and barite to protect against different kinds of radiation. Firstly, the mass attenuation coefficient (μ/ρ) values of five different glass ceramics with different amounts of SO3, barite, and zirconolite additive were simulated by MCNPX (version 2.6.0) codes at 0.015–20 MeV photon energies. The simulated results were tested by comparing with theoretical data. With the help of μ/ρ values, essential gamma protection parameters of glass ceramics such as half-value layer, linear attenuation coefficient, effective atomic number, equivalent atomic number, and exposure buildup factor were obtained. The results showed that the S0 sample may be a safe protective material against gamma-radiation. Removal cross-sections of glass ceramics were acquired to determine the capacity of the glass ceramics to stop fast neutrons. The addition of barite and zirconolite raised the density and increased the neutron preventive capacity of the glass ceramics. Finally, the competence of glass ceramics to stop charged alpha and proton particles was investigated using parameters of mass stopping power and projected range. It is concluded that the range of charged particles was the shortest in S0 glass ceramic. The corollaries of the present work will help in determining the impact of barite and zirconolite on the nuclear shielding capacity of glass ceramics.

Bi2O3 effect on physical, optical, structural and radiation safety characteristics of B2O3[sbnd]Na2O-ZnO[sbnd]CaO glass system

Novel transparent glasses with nominal composition of 50B2O3 +15Na2O+15ZnO+(20−x)CaO+xBi2O3; x = 0, 5, 10, 15, and 20 were synthesized using melt quenching method. The molar volume and density of the produced glasses with boosting the substitution ratio of Bi2O3 were measured. X-ray diffraction (XRD) patterns of the glasses were obtained for confirming their amorphous structure. UV–Vis spectra of the prepared samples were detected over the range of 190–1100 nm. By using UV–Vis results, Fermi level energy (Ef), refractive index (n), optical energy gap (Eg), Urbach's energy (Eu), and optical dispersion parameters were estimated. Results exposed that the optical energy gap (Eg) and single-oscillator energy (Eo) were decreased however other parameters increased with increasing Bi2O3 content. Mass attenuation coefficient (μ/ρ), as an essential variable for photon protecting research, was attained at 0.015–15 MeV photon energies for investigated glasses. Other relevant variables that can define the photon protecting features like Mean Free Path (MFP), Half Value Layer (HVL), equivalent atomic number (Zeq), gamma-ray exposure buildup factor (EBF), energy-absorption buildup factor (EABF) were obtained for the prepared glasses. The corollaries revealed that the BCNZB20.0 glass can be a strong shield material against gamma radiation. Finally, the proficiency of proposed glasses to stop fast neutrons charged alpha and proton particles was explored utilizing effective removal cross section (ΣR) and Mass Stopping Power (MSP) parameters. The glass with 20% Bi2O3 (BCNZB20.0) addition is very effective in preventing charged and uncharged particles. The addition of Bi2O3 to the studied glass system not only improved the optical and structural features but also the nuclear radiation shielding properties.

Feasibility study of using polyacrylamide gel dosimeter as brain equivalent material in therapeutic energy range of X-rays

In this paper the feasibility study of using polyacrylamide gels as a brain equivalent material has been performed. Thus, the parameters of mass energy absorption coefficient (μen/ρ), mass stopping power (S/ρ), effective atomic number (Zeff), mass attenuation coefficient (μeff/ρ) and absorbed dose delivered to polyacrylamide gel (D) were determined for this gel using analytical and Monte Carlo methods and were compared with brain reference material. The calculation results reveal that the relative difference between the calculated μen/ρ, S/ρ, Zeff, μeff/ρ and D for polyacrylamide gel and those for brain are 1.32%, less than 1%, less than 2%, less than 4% and less than 1%, respectively in therapeutic energy range. Consequently, like water, polyacrylamide gel can be also used for designing and construction of head and neck phantoms applied for validation of medical algorithms used in treatment planning systems. The advantage of using polyacrylamide gel as a brain equivalent material in comparison to water is that this gel is a reliable X and gamma rays dosimeter applicable for three dimensional dose distribution determination. Also, other advantages of this gel are its low price, availability and forming it in different sizes and shapes. These properties of the polyacrylamide gel make it beneficial as brain equivalent material in designing and construction of head and neck phantoms.

Stopping power ratio databases for proton therapy dose calculation

In modern radiation therapy, ion beams are increasingly used for cancer treatment. Protons are light ions that have Bragg peak characteristic in the depth dose distribution that is optimal for minimizing dose to surrounding normal tissues. In proton therapy treatment planning, the stopping power ratio (SPR) of a given medium to that of water is used for calculating the water-equivalent pathlength (WEPL) of tissues in the patient. Since SPR is related to the computed tomography (CT) number, the conversion from CT numbers to SPRs can be used to find WEPLs of tissue voxels, which are sequentially applied in selecting the initial proton energy. In this work, we investigated the effect of using different CT number to SPR conversion models on proton pencil beam dose calculation. In the SPR calculation, either elemental mean excitation energy (I-value) from the ICRU report or elemental mass stopping power from SRIM software were used. For each approach, four energy dependent scenarios were investigated. The ICRU model and the SRIM model showed a monotonic correlation of SPRs for most tissue types. The 2D dose distribution was calculated by a MATLAB-based proton therapy treatment planning system, PSPLAN. The results suggest that elemental I-values and elemental mass stopping power can be used interchangeably for SPR calculation. Moreover, CT number to SPR conversion models obtained for specific proton energy and average proton energy did not cause difference in pencil beam dose calculation unless the proton energy was relatively low.

Improvement of radiation shielding properties of some tellurovanadate based glasses

In this research, various valuable features having discriminating characteristics, namely the mass attenuation coefficient (μm), effective atomic number (Zeff), energy absorption buildup factor (EABF), neutron removal cross-section (ΣR), mass stopping power (MSP) and projected range values were studied in the energy range of 0.015–15 MeV for vanado-telluride glass network had heavy or transition metal oxides. μm for the different glass series were calculated using Monte Carlo code. Besides, the EABFs were also calculated using geometric progression fitting technique. The proton and alpha MSP as well as projected range values were computed using SRIM code. Moreover, the generated μm by MCNPX for the different glass series was compared to the outputs of XMuDat and XCOM. The analysis indicated that the glass sample VTBi6 had good magnitudes of μm and the lowest values of half value layer, i.e. the sample had the superior radiation shielding properties among the explored glasses.

Newly developed BGO glasses: Synthesis, optical and nuclear radiation shielding properties

In this research paper, we studied the optical and nuclear shielding efficiency of newly developed BGO glasses with the following compositions (in wt%): 32Bi2O3–68GeO2, 42Bi2O3–58GeO2, 47Bi2O3–53GeO2, 52Bi2O–48GeO2, 62Bi2O3–38GeO2. BGO glasses were prepared by traditional melt quenching method. To obtain the band gap values of fabricated BGO glasses, optical absorption spectra were used for evaluation of optical properties. The mass attenuation coefficients (μ/ρ) were achieved for prepared glasses at 0.015–15 MeV photon energies employing MCNPX Monte Carlo code and WinXcom program. Moreover, broad-range of nuclear shielding parameters for gamma ray, neutrons and charged particles such as mass attenuation coefficient, half value layer, effective atomic number, buildup factors, mass stopping powers, projected ranges, fast neutron removal cross sections and damage factors were calculated. The refractive index is calculated from Eopt, As Bi2O3 concentration is enhanced, Eopt is also increased as well as the optical electronegativity and consequently the refractive index. In addition, the results showed that BIGE5 glass sample with highest Bi2O3 contribution has excellent nuclear radiation shielding ability among the other fabricated glass samples.

Phy-X/ZeXTRa: a software for robust calculation of effective atomic numbers for photon, electron, proton, alpha particle, and carbon ion interactions.

The purpose of the present work is robust calculation of effective atomic numbers ([Formula: see text]s) for photon, electron, proton, alpha particle and carbon ion interactions through the newly developed software, Phy-X/ZeXTRa (Zeff of materials for X-Type Radiation attenuation). A pool of total mass attenuation and energy absorption coefficients (for photons) and total mass stopping powers (for charged particles) for elements was constructed first. Then, a matrix of interaction cross sections for elements Z = 1-92 was constructed. Finally, effective atomic numbers were calculated for any material by interpolating adjacent cross sections through a linear logarithmic interpolation formula. The results for [Formula: see text] for photon interaction were compared with those calculated through Mayneord's formula, which suggests a single-valued [Formula: see text] for any material for low-energy photons for which photoelectric absorption is the dominant interaction process. The single-valued [Formula: see text] was found to agree well with that obtained by other methods, in the low-energy region. In addition, [Formula: see text] values of various materials of biological interest were compared with those obtained experimentally at 59.54keV. In general, the agreement between values calculated with Phy-X/ZeXTRa and Auto-Zeff and those measured were satisfactory. A comparison of [Formula: see text] values for photon energy absorption calculated with Phy-X/ZeXTRa and literature values for a nucleotide base, adenine, was made, and the relative difference (RD) in [Formula: see text] between Phy-X/ZeXTRa and literature values was found to be 2% < RD < 11%, at low photon energies (1-100keV), while it was less than 1% at energies higher than 100keV. Highest [Formula: see text] values were observed at low photon energies, where photoelectric absorption dominates photon interaction. For electrons, corresponding RD(%) values in [Formula: see text] were found to be in the range 0.4 ≤ RD(%) ≤ 1.7, while for heavy charged particle interactions it was 2.4 ≤ RD(%) ≤ 4.2 for total proton interaction and 0 ≤ RD(%) ≤ 8 for total alpha particle interaction. In view of the importance of [Formula: see text] for identifying and differentiating tissues in diagnostic imaging as well as for estimating accurate dose in radiotherapy and particle-beam therapy, Phy-X/ZeXTRa could be used for fast and accurate calculation of [Formula: see text] in a wide energy range for both photon and charged particle (electrons, protons, alpha particles and C ions) interactions.

Comparative evaluation of nuclear radiation shielding properties of xTeO2 + (100–x)Li2O glass system

In the present investigation, nuclear radiation shielding parameters of xTeO2 + (100–x)Li2O (where x = 95, 90, 85, 80, 75, and 70 mol%) glass system have been examined. Gamma shielding parameters such as mass attenuation coefficients (MAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Neff) were calculated. Moreover, neutron effective cross sections (∑R) are determined. The calculations for present materials have been performed in different photon energy ranges (0.01–20 MeV) and using Monte Carlo N-Particle eXtended (MCNPX) simulation code and theoretical results were also obtained with WinXcom program. The results obtained from the MCNPX and WinXcom program were found to be in well harmony. Moreover, for the assessment of radiation shielding success of tellurite glasses, the mass stopping power (MSP) and projected range (PR) were computed for proton and alpha particles using stopping and range of ions in matter (SRIM) code. When the results obtained from the study are examined, it is seen that 95TeLi glass has the lowest HVL, TVL, MFP, TF and the highest (∑R) values. Therefore, the 95TeLi glass has the most perfect radiation shielding achievement than other investigated glasses.

Bioactive glasses with TiO2 additive: Behavior characterization against nuclear radiation and determination of buildup factors

This paper studies the radiation attenuation properties and build up (EBF and EABF) factors of different types of bioactive glasses in the 0.015–15 MeV photon energy range. EBF and EABF values of investigated bioactive glasses are determined by using the G-P fitting method. Moreover, effective removal cross-section values, alpha/proton mass stopping power (MSP), and alpha/proton projected range values (PR) are determined for fast neutrons and charged particles. The investigation indicates that TiO2 additive in the bioactive glasses causes considerable variations in the attenuation properties of bioactive glasses. The results show that the BT2.5 bioactive glass sample has highest attenuation performance among the samples.

WITHDRAWN: Assessment of ionizing radiation attenuation features of zirconolite silicate glasses using XCOM and FLUKA simulation code

Abstract This work aimed to investigate ionizing radiation shielding features of zirconia silicate SiO2-Na2O-CaO-xZrO2 (SCNZ) glass system. The mass attenuation coefficients (MAC, μ/ρ) were generated by FLUKA Monte Carlo simulation code and the obtained data verified via the calculated data of XCOM software over an extended photon energy range of 0.015 – 20 MeV. The obtained value of μ/ρ have been used to evaluate several effective attenuation features such as half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), and effective electron density (Neff). Results reveal that μ/ρ, MFP, HVL, Zeff and Neff parameters of the investigated glasses strongly depend on photon energy and chemical composition. Additionally, by using G-P fitting parameters, the exposure buildup factor (EBF) and energy absorption buildup factor (EABF) of the investigated glasses were calculated. Results show that the greatest values of buildup factors exhibit at higher energies for all glass samples. Finally, the values of fast neutron removal cross section (ΣR) and the kinetic energy loss rate (Mass Stopping Power, MSP) of alpha and protons passing through the studied glasses were evaluated. The results display that insertion of ZrO2 improved the nuclear security capability of SCNZ glasses. Especially, SCNZ7 glass owns superior shielding ability for charged particles as well as gamma radiation.

Low energy electron mass stopping power in H2

SynopsisWe present experimental mass stopping powers of electrons in gaseous H2 obtained with a newly developed electron time-of-flight spectrometer, for the incident electron energy range of 10 eV to 25 eV. In our procedure the average energy loss is derived from our conversion of measured electron time-of-flight spectra into equivalent electron energy loss spectra so as to obtain the values of mass stopping power for electron scattering from H2.

Calculations of positron scattering on the hydrogen molecular ion

Positron scattering from the vibrational ground state of the hydrogen molecular ion has been investigated using the single-centre convergent close-coupling (CCC) method. Cross sections for dissociative excitation, dissociative ionisation, total inelastic scattering, and proton production have been calculated at incident positron energies from 10 to 500 eV. For this energy range the mass stopping power and mean excitation energy have also been calculated for both the positron and electron cases. Since there are no experiments or other calculations for positron scattering on the hydrogen molecular ion, the obtained results have been compared with corresponding CCC results for positron collisions with He+ and electron collisions with . Comparative analysis allows to estimate the quality of the approximations used in the present calculations.

The effective role of La2O3 contribution on zinc borate glasses: radiation shielding and mechanical properties

In this theoretical study, the zinc borate glasses have been modified with lanthanum oxide (La2O3) in a different amount (0, 1, 2, 3 and 4%).The mechanical and shielding properties change after adding of lanthanum oxide in zinc borate glasses depending on the bond compression and Makishima-Mackenzie models. The mass attenuation coefficients have been calculated using the XCOM program and MCNPX simulation code. The results present that La2O3 increment in the glass density modifies the glass mechanical properties and improves the radiation attenuation performances. The variations in the mechanical properties are resulting from the formation of bridging oxygen. The density of the ZnO–B2O3–La2O3 glass system is proportional to La2O3 concentration, which is attributable to the highest molecular weight of La2O3 than those of ZnO and B2O3. Furthermore, the mass attenuation coefficients, effective atomic numbers and effective removal cross-section of the glasses increases as La2O3 contains increase. The half-value layer, tenth value layer, mean free path, buildup factors and mass stopping power of the glasses decrease as La2O3 contain increases. Present results explained the characteristic of ZnO–B2O3–La2O3 glass as a novel nominee for radiation attenuation barrier in the chosen energy zone.

Sm2O3 effects on mass stopping power/projected range and nuclear shielding characteristics of TeO2–ZnO glass systems

This work aims to research not only neutron and gamma shielding specialties of Sm2O3-doped TeO2–ZnO glasses but also mass stopping power (MSP) and projected range (PR) for alpha and proton particles. Mass attenuation coefficient (μ/ρ) of 60(TeO2)–(40−x)ZnO–x(Sm2O3): x = 0.0, 0.1, 0.2, 0.3, 0.4, and 0.5 mol%) glasses were obtained using GEANT4 Monte Carlo codes and WinXCOM software. A good agreement was observed between the two outcomes. The insertion of Sm2O3 into the glasses raised the μ/ρ values. It was found that TZSm0.4 glass owns lowest MFP, HVL and TVL values than the other glass samples due to its high specific gravity. Besides, the additive material increased effective atomic number (Zeff) values while the Exposure (EBF) and Energy Absorption (EABF) Buildup Factors decreased which are computed at 0.015–15 MeV photon energies up to 40 mfp. This shows that the addition of Sm2O3 improves the performance of glasses to reduce gamma radiation. Moreover, fast neutron macroscopic cross-sections (ΣR) of the glasses were specified. MSP and PR values were also computed for proton (H1) and alpha (He+2) particles. The outcomes display that the specific gravity of the TZSm glasses are extremely influential on neutron, alpha and proton shielding. With the largest ΣR and lowest PR values, the TZ0.4 glass showed the ability to stop both neutral and charged particles. It can be deduced that TZSM glasses with Sm2O3 addition may be preferred shield materials in the sense of gamma, neutron, alpha and proton attenuation.

Newly developed tellurium oxide glasses for nuclear shielding applications: An extended investigation

Newly developed glasses were produced using different compositions as follows (in wt.%): (85TeO2-15ZnO, 85.00TeO2-12.95ZnO-2.05Al2O3, 85.40TeO2–3.20PbO-6.97ZnO-4.43Na2O, 83.5TeO2-16.5BaO, 82.77TeO2–17.23Nb2O5, 54.6TeO2-22.6WO3-22.8Bi2O3). The acquired mass attenuation coefficients (μ/ρ) were used to determine another vital parameters for gamma-ray shielding performance namely mean free path (MFP), half value layer (HVL), tenth value layer (TVL), energy absorption buildup factor (EABF), exposure buildup factor (EBF), effective atomic number (Zeff), respectively. Simultaneously, effective removal cross section (∑R) values for fast neutrons, proton projected range (PPR), alpha projected range (APR), proton mass stopping power (PMSP), alpha mass stopping power (AMSP), neutron absorption parameters (absorption neutron scattering cross section (σabs)), SAFE factors and relative dose distribution (RDD) have been investigated for fabricated glass samples. The results showed that the 54.6TeO2-22.6WO3-22.8Bi2O3 composition has the best performance in terms of nuclear shielding purposes. It is worth recommending the continuous investigations on chemical combinations and changes of TeO2 concentration for future applications.

Assessment of nuclear shielding and alpha/proton mass stopping power properties of various metallic glasses

This work aimed to investigate alpha, proton, neutron and gamma shielding qualifications of different bulk metallic glasses (Zr65Al7.5Ni10Cu17.5, Ti40Zr26Be28Fe6, Cu49Hf42Al9, Pd40Ni40P20, Ni50Pd30P20, and Ca65Mg15Zn20) for nuclear security applications. Therefore, vital gamma radiation attenuation parameter namely mass attenuation coefficients ($$\mu_{\rho }$$) of investigated bulk metallic glasses (BMG) were determined using WinXCOM program. Next, half value layer (HVL), effective atomic number (Zeff), effective electron density (Nel) and exposure buildup factors (EBF) were perused in a wide energy interval (0.02–20 MeV). Among the investigated samples, MG3 was found to be superior attenuator sample for gamma radiation, while MG6 was the least forceful glasses to reduce the photon intensity. The elements Pd and Hf in MG4, MG5 and MG3 were enhanced radiation shielding competences of the BMGs. Further, fast neutron removal cross-sections ($$\sum R$$) were evaluated to investigate neutron protection ability of the BMGs. Projected range (PR) and mass stopping power (MSP) values were obtained for proton (H1) and alpha particles (He+2). The outcomes showed that elemental composition of the metallic glasses was highly powerful on alpha, proton and neutron attenuation. It can be concluded that MG3 sample exhibited high nuclear shielding efficiency as deduced from the largest $$\mu_{\rho }$$, Zeff, and $$\sum R$$, and the lowest HVL, EBF, MSP and PR values.

Bazı Nükleer Reaktör Kontrol Çubuğu Malzemelerinde Yüklü Parçacık Giricilik Mesafesi ve Kütle Durdurma Gücü Hesaplamaları

One possible solution to the increasing energy demand, which mankind has been facing through, might be pointed as the nuclear reactors that work with the fission mechanism. In order to pursue the operation of these facilities, many equipment have been designed in a way that all of them could operate together where the control rods could be given as one of the vital parts among them. Material properties of these components, such as physical-chemical characteristics and their behaviors under different interactions, have an undeniable importance. Due to that, gathering all the possible information about the materials used for the production of these components is extremely important. By considering this importance, in this study, the mass stopping power and charged particle penetration distance calculations have been done for some materials which have possible usage in nuclear reactor control rods using alphas, 3He, tritons, deuterons and protons within the energy range of 1-50 MeV via employing two of the most known computer aided calculation and simulation software which are GEANT4 and MCNP. Obtained results from both codes have been visualized by graphing and compared with each other.

Synthesis and nuclear radiation shielding characterization of newly developed germanium oxide and bismuth oxide glasses

We present the synthesis and nuclear radiation shielding characterization of glasses based on germanium and bismuth oxide prepared with the melt-quenching technique. The glasses were produced using six different compositions as follows (in wt%): 40.0GeO2-60.0PbO, 38.0GeO2-62.0Bi2O3, 31.344GeO2-41.900Bi2O3-26.756PbO, 33.334GeO2-33.333TeO2-33.333PbO, 20.6GeO2-41.9TeO2-17.4Nb2O5-20.1BaO, 41.98Bi2O3-48.26PbO-8.10Ga2O3-1.66BaO. Monte Carlo method (MCNPX code, v-2.6.0) has been utilized for the determination of mass attenuation coefficients (μ/ρ) of the synthesised six different glasses. The acquired mass attenuation coefficients (μ/ρ) have been used to determine the vital parameters for gamma-ray shielding namely half value layer (HVL), mean free path (MFP), tenth value layer (TVL), effective atomic number (Zeff), exposure buildup factor (EBF), energy absorption buildup factor (EABF), transmission factors (TF), respectively. Simultaneously, effective removal cross section (∑R) values for fast neutrons and Proton mass stopping power & proton projected range have been also calculated. The results showed that among all the investigated glasses, 41.98Bi2O3-48.26PbO-8.10Ga2O3-1.66BaO glass sample has the extra capability to reduce nuclear radiation as a shielding material.