Values Of Projected Range Research Articles

Efficacy of barium and calcium additives in lithium silicate glasses for nuclear shielding applications

This study presents a detailed investigation into the nuclear radiation shielding capabilities of lithium silicate (Li2O-SiO2) glass systems, specifically examining the impact of doping with barium oxide (BaO) and calcium oxide (CaO). Utilizing advanced simulation tools, including PAGEX and SRIM for charged particle interactions, and Phy-X/PSD for gamma-ray attenuation analysis, the radiation shielding effectiveness of BaO-based and CaO-based lithium silicate glasses were systematically compared. The gamma attenuation parameters (LAC, MAC, TVL, HVL, EBF, EABF, MFP, Zeff, Neff, FNRCS, and Zeq) of investigated glass samples were computed via the Phy-X/PSD program (15 keV-15 MeV energy). The HVL values vary between 0.007–14.203 cm, and the TVL values vary between 0.054–47.182 cm for all samples in the selected energy range. The highest and lowest values of FNRCS were observed for samples BaO20 and CaO5, with the values 0.093 and 0.1 cm−1, respectively. KERMAs were calculated using PAGEX software between the 1.5 keV and 20 MeV energy range, with the highest KERMA obtained for the BaO20 sample at 0.05 MeV and the lowest KERMA obtained for the CaO5 sample at the lowest density. The mass stopping power quantities were computed between 1 keV-10 GeV energy with PAGEX. The projected range values were calculated with SRIM codes. The lowest projected range values for both alpha particles and protons were obtained for the BaO20 sample with maximum density (3.391 g cm−3). The sample with BaO20 code showed better shielding potential for alpha and proton particles with lower values of projected range and mass stopping power. Findings reveal that the Li2O-BaO-SiO2 glass composition exhibits superior gamma-ray attenuation properties compared to its CaO-doped counterpart, with the BaO20 sample demonstrating particularly enhanced performance.

The structural, optical, electrical and radiation shielding properties of Co-doped ZnO thin films

Co:ZnO thin films are promising due to the similar ionic radii of cobalt and ZnO, and their potential for carrier spin injection, transfer, and detection. This study aims to investigate the structural, optical, electrical, and radiation shielding properties of Co-doped zinc oxide (Co:ZnO) thin films for potential applications in various fields such as semiconductors, solar cells, spintronics, and radiation shielding. The effect of commercially available Cobalt acetate tetrahydrate and Cobalt complex (Co with conjugated NN ligand) as cobalt additives on the synthesis of ZnO thin films is compared, aiming to discern their respective impacts. The dopants are incorporated in 2, 4, and 6 wt%, employing the sol-gel spin coating method.Applying cobalt complex additive as Co precursor resulted in ZnO:Co films with a superior enhancement of the electronic band gap of 2.84–3.00 eV compared to cobalt acetate precursor (2.62–2.84 eV). With the introduction of Cobalt, there is a notable change in the electrical conductivity, showcasing a decrease from 1.5x10−7 to 2.11x10−10 (S/cm). Also, radiation shielding parameters were experimentally measured in the energy range of 186.1–1764.5 keV within the scope of gamma ray spectral analysis. Exposure buildup factors (EBF) in the energy range of 15–15,000 keV were calculated up to 1–40 mean free path (mfp). Mass stopping power (MSP) and projected range values (PR) for nuclear safety applications were calculated for protons and alpha particles using the SRIM code. Thin film thicknesses were determined by using Lambert-Beer law. It was observed that the thin film thicknesses obtained from gamma spectrometry (2.090–2.628 μm) and SEM (2.157–2.725 μm) were compatible with each other.

Fabrication and characterization of different PbO borate glass systems as radiation-shielding containers

Three borate glasses of 50, 35, and 15 mol% PbO-doped Ce, Sb, or Mn ions were fabricated via the melting-annealing procedure. Their structural features were inspected before and after 250 kGy of gamma irradiation using FTIR and ESR techniques. The spectra of the ESR and FTIR vibrational bands remain constant, with a minor reduction in N4 and an enhancement in density values after irradiation, indicating the large structural stability and glass compactness. Many radiation shielding parameters were studied, such as gamma dose rate (µSv/h), dose transmission %, lifetime cancer risk %, macroscopic effective removal cross-section (∑R), mass stopping power, and projected range values ​​were considered for protons particles by SRIM Monte Carlo simulation code and ESTAR program. The whole data reveals the high radiation shielding efficiency of the glasses compared to other standard shields to be used as glass immobilizers for radioactive wastes or storage containers, e.g., for nuclear medicine units in hospitals.

Case study of Er- and Dy-doped boron-aluminosilicate glasses on radiation shielding performance in the energy range 0.015–10 MeV with MCNP6.2

The use of radiation-shielding materials has significantly increased with the advancement of new technologies. The present work aims to demonstrate that the nuclear shielding properties of boron-aluminosilicate glasses can be enhanced by doping with rare earth elements (REEs) such as erbium (Er) and dysprosium (Dy). Testing was performed by mixing different ratios of dopants into the glass system. This procedure was implemented on 13Al2O3–21B2O3-35.4SiO2-(30.6-X) Er2O3-X(Dy2O3) glass, where X = 0, 15.3, 22.1, and 30.6. MCNP6.2, SRIM, PSD, ROOT software, and XCOM databases were used as tools. MCNP6.2 software and XCOM databases were used to calculate, simulate, and validate the mass attenuation cross-sections for 15 selected gamma energies ranging from 0.01 MeV to 10 MeV. On the other hand, SRIM was used to obtain information about the mass stopping power (MSP) and stopping distance, the so-called projected range (PR), for charged particles of H+1 and He+2. Likewise, the PSD was only used to obtain a fast neutron removal cross-section (FNRCS) per density value for each element. This is referred to as the macroscopic neutron cross-section for fast neutron removal in the literature. Finally, the data analysis framework ROOT was used for calculations and graphical representations. To validate this study, the radiation-shielding properties of the material were compared with the globally accepted mass attenuation coefficient database of XCOM using MCNP6.2 simulation results. The proximity between these two is promising. The accuracy of the study was determined by examining the relative error values. The results indicate a strong correlation between the database and theoretical data. Radiation shielding properties such as mass and linear attenuation coefficients (MAC and LAC), half and tenth value layers (HVL and TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Neff), effective conductivity (Ceff), and fast neutron removal cross-sections (FNRCS) against gamma rays suggested that the lowest X ratio indicated the highest protection. However, the MSP and PR values for the charged particles at most energies indicate the lowest protection with the lowest X ratio in the glass mixture. Finally, the glass shield with the lowest X ratio provided the highest neutron protection, similar to gamma rays. In summary, dysprosium and erbium doping in boron-aluminosilicate glasses can be tailored to specify different requirements for gamma-ray and particle attenuation, as well as neutron absorption. This study aims to fill a gap in the literature by providing a basis for future research on shielding materials based on doped boron-aluminosilicate glasses using high-atomic-number particles, such as REEs, as a radiation protection medium.

Exploring the KERMA, mass stopping power and projected range values against heavy-charged particles: A focusing study on Sm, Yb, and Nd reinforced tellurite glass shields

In present study, the behavior of ytterbium (III) oxide, samarium (III) oxide and neodymium (III) oxide reinforced novel TeO2–B2O3–V2O5 (TBV groups, tellurite-vanadium–boro) glasses groups are investigated against heavy charged particles, on mass stopping power, projected range and KERMA parameters. SRIM and PAGEX codes are used for determination of the mass stopping power, projected range and KERMA parameters in a kinetic energy range of 0–10 MeV. The highest KERMA values of TBV(X) glasses were achieved at 0.6 MeV. Among TBV(X) glasses, the TBVY1.5 sample with the highest material density (i.e. 5.01038 g/cm3) had the highest KERMA value. The TBVY1.5 sample has the lowest projected range values for alpha and protons with the same kinetic energy. The lowest values of mass stopping power were reported for the TBVY and TBVS groups, which had the highest density values among the analyzed glass samples. The TBVY1.5 sample provides the greatest stopping and slowing characteristics for alpha and proton kinetic energies ranging from 0 to 10 MeV. In this case, it can be said that these two glass groups may slow down alpha particles with a certain kinetic energy the most effectively. It can be concluded that TBV(Y) and TBV(S) glass groups might be useful for stopping the alpha, proton and electron particles.

Gamma-ray, fast neutron and ion shielding characteristics of low-density and high-entropy Mg–Al–Ti–V–Cr–Fe–Zr–Nb alloy systems using Phy-X/PSD and SRIM programs

This study aimed to assess the radiation shielding properties of ten low-density high-entropy alloys (LWHEAs) using Phy-X/PSD software to analyze various shielding parameters, such as attenuation coefficients (μm and μ), mean free path (λ), effective atomic number (Zeff), and removal cross-section (ΣR), in the energy range of ▪ to ▪. A comprehensive evaluation was performed to compare the attenuation outcomes provided by HEAs with a range of shielding materials documented in the literature. The study also calculated the build-up factors (BUFs) of the alloys by using the GP-fitting interpolation method. The stopping power of the alloys against H1/He+2 ions was analyzed using the SRIM Monte Carlo code, considering total stopping power (TSP) and projected range (PR). The results indicated that HEA8 (Al3.88Cr14.95Mo27.58Nb26.71Ti13.76Zr13.11) had the best performance in terms of shielding against γ-rays, fast neutrons, and H1/He+2 ions, as it achieved the highest values of parameters such as μm, μ, Zeff, and ΣR, along with the lowest values of HVL, TVL, λ, BUFs (▪▪), TSP, and PR. On the other hand, HEA10 (Mg10.77Al11.96Mn24.35Fe24.75Cu28.17) had the lowest BUFs in both lower (▪▪) and higher (▪▪) energy regions. The order of μm for the alloys was found to be HEA5<HEA6<HEA9<HEA7<HEA10<HEA4<HEA2<HEA3<HEA1<HEA8. The study concluded that LWHEAs possess superior radiation shielding properties compared to conventional materials, making them a promising new class of materials for radiation shielding applications.

Tailoring a Behavioral Symmetry on KERMA, Mass Stopping Power and Projected Range Parameters against Heavy-Charged Particles in Zinc-Tellurite Glasses for Nuclear Applications

We present the behavioral changes and symmetrical enhancement on KERMA, mass stopping power and projected range parameters against heavy-charged particles through Indium (In) and Tantalum (Ta) incorporations for various zinc-tellurite glass groups such as TZI and ZTT for nuclear applications. SRIM and PAGEX codes are utilized for the determination of investigated attenuation parameters for alpha and proton particles. In KERMA calculations, the ZTT7 sample is reported to have the greatest release of charged particles because of an increase in kinetic energy. The mass stopping power values of all absorbent glass materials are steadily increased from 0 MeV to 0.1 MeV. TZI and ZTT attained their maximum mass stopping power at a kinetic energy value of 0.1 MeV. While comparable behavior patterns are seen for various energy values on the examined energy scale, the ZTT7 sample is observed with lower mass stopping power and projected range values against proton particles than the other samples. It can be concluded that zinc-telluride glasses through maximum Ta-reinforcement may be considered as promising materials for stopping the proton and alpha particles. Moreover, Ta-reinforcement may be considered as a monotonic tool in terms of providing a symmetry for attenuation enhancement against heavy-charged particles.

Radiation shielding properties of low-density Ti-based bulk metallic glass composites: a computational study

Bulk metallic glasses (BMGs), a new class of structural and functional materials with unique physical and chemical features like high corrosion resistance, high yield strength, low elastic modulus, and transparency to visible light, indicate they could be potential shield against unwanted radiations. This study presents an attempt to investigate radiation shielding efficiencies of a few titanium (Ti)-based BMGs with low densities of range 4.43–5.15 g/cm3. Different shielding properties viz., attenuation coefficients (μ m and μ), half and tenth value layers (HVL and TVL), mean free path (λ), effective atomic number (Zeff), buildup factors (EBF and EABF), and fast neutron removal cross-section (Σ R ) were evaluated in 0.015 − 15 MeV energy range using Phy-X/PSD software. The interaction of charged particles (i.e., H1 and He+2 ions) with BMG samples was investigated in terms of mass stopping power (MSP) and projected range (PR) by deploying Monte Carlo-based SRIM software. The five-parametric geometric-progression (G-P) fitting method was employed to calculate EBF and EABF, whereas Zeff values were calculated through atomic to electronic cross-section ratio. Further, obtained results were compared with two conventional shielding materials: lead (Pb) and heavy concrete (StMg). We found that among 8 BMGs, sample Ti41.9Zr36.3V12.1Cu6.3Be3.4(S1) with the lowest Ti and highest Zr-composition by mass (41.9% and 36.3%, respectively) exhibited the best gamma-rays, fast neutrons, and H1/He+2 ions shielding characteristics with the highest μ m (0.02–15 MeV), μ (0.015−0.2 MeV), Zeff (0.015–0.06 MeV) and Σ R . These values were higher than that of StMg, but lower than those of Pb. Moreover, S1 exhibited the lowest values of HVL, TVL, and λ in 0.015 − 0.2 MeV region for gamma-rays and also has the lowest MSP and PR values for H1/He+2 ions. However, the lowest EBF and EABF values belonged to BMG S1 in intermediate energy region (0.1−2 MeV) only. But, the sample Ti90Al6V4(S7) was the worst among all BMGs and StMg. Thus, low-density Ti-based BMGs have better performances towards gamma-rays, fast neutrons, and H1/He+2 ions shielding and hence the potential to replace conventional StMgs and toxic Pb-based materials.

A Monte Carlo simulation study on the evaluation of radiation protection properties of spectacle lens materials.

The eye lens has been known a radiosensitive tissue. Radiation exposure can cause opacities, cataracts and vision loss. The sensitivity of the eyes to ionizing radiation has attracted attention in the last decade. ICRP announced that equivalent dose limit of eye lens has dropped in recent years. Therefore, spectacle lens selection is becoming increasingly important. In this study, the radiation protection properties of spectacle lens (CR-39, Polycarbonate and Trivex) materials were investigated using the MCNP-6.2 Monte Carlo code and SRIM software. The suitability of the results obtained with MCNP-6.2 Monte Carlo code was provided by comparing the theoretical results obtained from the WinXCOM program. The results showed that the CR-39 spectacle lens had minimum half-value layer, tenth value layer and mean free path values. In addition to the photon protection properties of spectacle lens materials, proton (H1) and alpha (He+2) radiation protection properties were also investigated. Mass stopping power and projected range (PR) values for proton and alpha particles were calculated using SRIM code in the energy range of 0.01-10MeV. As a result of the research, it was seen that the CR-39 lens had minimum PR values.

Radiation shielding parameters and Micro-Raman spectral analysis of some pyroclastic rocks

In this study, the radiation shielding parameters of some pyroclastic rocks (Karabakir, Elazığ) were experimentally measured at 59.54–661.62 keV energy region. In addition, theoretical mass attenuation coefficients were calculated. Fast neutron removal cross section, exposure buildup factor, mass stopping power and projected range values for proton (H1) and alpha (He+2) particles were theoretically determined. The equivalent dose rates due to fast neutrons absorption by rock samples was measured experimentally using a241Am–Be fast neutron source with 10 mCi activity. Also, the elemental analysis of pyroclastic rocks was done by instrumental neutron activation analysis and inductively coupled plasma mass spectrometry. Minerals type and rock strength were evaluated by micro-Raman spectroscopy methods. The dose rate at detector is D0 when there is no sample between the neutron source and the detector, the dose rate at detector is Dd when there is a K-8 rock sample. The difference between the dose rates (Ds), was calculated and the equivalent dose rate absorbed by the K-8 rock sample was obtained as 0.2667 μSv⁄h. It is observed that K-8 rocks sample is a promising choice for gamma, neutron, proton and alpha shielding.

ZnO/CdO translocation in P2O5-TeO2-ZnO ternary glass systems: A reformative enhancement tool for physical, optical, and heavy-charged particles attenuation properties

We report the optical, physical, structural, and heavy charged particle absorption parameters of CdO doped P2O5-TeO2-ZnO ternary glass structures with a nominal composition of 20 P2O5.30TeO2.(50-x)ZnO.xCdO (x = 0, 2, 4, 6, 8, 10 mol. %). Physical as well as optical characteristics of the synthesized glasses are measured using experimental methods. ZnO/CdO translocation is caused an increase in the density of the synthesized samples. Synthesized glasses are reported along with seventeen different bands as a result of deconvolution processes. The structure is formed more tightly and regularly with ZnO/CdO translocation process. As a result of the evaluation of the absorption edge, transmittance of the glass without CdO additive is reported around 338 nm in the 20–30 % transmittance region, the absorption edge of all the glasses doped with CdO is shifted to around 336 nm. According to results, un-doped C0 glass is observed more unstable and far from homogeneous than doped glasses with the largest Urbach energy value (0.1506 eV), while C10 glass is observed as much more stable and uniform when compared to all glasses in this study with a value of 0.1311 eV. Moreover, projected range values of alpha and protons grew as the energy level increased. The shortest lengths that alpha and protons may travel at the same energy levels are reported for the C10 sample, which has the highest CdO contribution as well as the highest glass density. C10 glass sample is reported to have the maximum degree of clarity, making it one of the most important qualifying requirements for shields in medical radiation facilities, where the observation of both the patient and the physical radiation source is crucial. It can be concluded that the investigated ZnO/CdO translocation process may be seen as a beneficial tool for P2O5-TeO2-ZnO ternary glass structures in terms of enhancing optical, physical, and heavy charged particle attenuation properties.

Optical, structural, physical, and nuclear shielding properties, and albedo parameters of TeO2–BaO–B2O3–PbO–V2O5 glasses

In this study, glass systems were constructed according to the formula 34TeO2∙xBaO∙35B2O3∙(30-x)PbO∙1V2O5 (x=0, 5, 10, 15, 20, 30 mol%). The gamma, neutron, proton, and alpha shielding characteristics of the glasses were evaluated for nuclear security applications. The mass attenuation coefficient (MAC), half-value layer, mean free path, effective atomic number, and radiation protection efficiency (RPE) were experimentally measured in the energy range of 59.54–661.62 keV. In addition, the theoretical MAC values were determined. The exposure buildup factor, fast neutron removal cross section, mass stopping power, and projected range values for proton (H1) and alpha (He+2) particles were theoretically determined. Albedo parameters were measured for the prepared glasses at photon energy of 59.54 keV. The optical and structural properties were studied using X-ray diffraction, FT-IR Fourier transform infrared, ultraviolet–visible, and electron paramagnetic resonance spectroscopy. The glass samples comprised structural units such as TeO4, TeO3, BO3, and BO4. The spin Hamiltonian parameters, g∥, g⊥, A∥, A⊥, dipolar hyperfine coupling parameter, P, and Fermi contact parameter, κ, were calculated. The molecular orbital parameters, α2, β2, and γ2, were determined by optical absorption spectroscopy. The number of bonds per unit volume in the glasses ranged between 8.763 and 9.212×1028 m−3. The most reflective compound among the glasses investigated was BaO. Good agreement was found between the theoretical and experimental MAC values. TeBaBPbV1 glass was identified as a potential candidate for use in neutron, gamma, proton, and alpha shielding.

A comprehensive ionizing radiation shielding study of FexSe0.5Te0.5 alloys with various iron concentrations

This study aims to explore the photon, neutron, and proton shielding features of FexSe0.5Te0.5 alloys with different iron concentrations; 0.95 ≤ x ≤ 1.05. The X-ray diffraction revealed that the prepared samples have the PbO-tetragonal structure. SRIM code and Phy-X program were used to determine various ionizing radiation shielding features. The alloys density, mass attenuation coefficient, and the removal cross-section for fast neutrons showed a progressive reduction with increasing iron contents. While the mass stopping power and projected range values increased with the addition of iron contents. The Fe0·95Se0·5Te0.5 sample has the maximum density and appeared to have superior photons, neutrons, and protons shielding features. The obtained results nominate the present alloys to be used in ionizing radiation shielding applications.

Investigation of photon, neutron and proton shielding features of H3BO3–ZnO–Na2O–BaO glass system

The current study aims to explore the shielding properties of multi-component borate-based glass series. Seven glass-samples with composition of (80-y)H3BO3–10ZnO–10Na2O–yBaO where (y = 0, 5, 10, 15, 20, 25 and 30 mol.%) were synthesized by melt-quench method. Various shielding features for photons, neutrons, and protons were determined for all prepared samples. XCOM, Phy-X program, and SRIM code were performed to determine and explain several shielding properties such as equivalent atomic number, exposure build-up factor, specific gamma-ray constants, effective removal cross-section (ΣR), neutron scattering and absorption, Mass Stopping Power (MSP) and projected range. The energy ranges for photons and protons were 0.015–15 MeV and 0.01–10 MeV, respectively. The mass attenuation coefficient (μ/ρ) was also determined experimentally by utilizing two radioactive sources (166Ho and 137Cs). Consistent results were obtained between experimental and XCOM values in determining μ/ρ of the new glasses. The addition of BaO to the glass matrix led to enhance the μ/ρ and specific gamma-ray constants of glasses. Whereas the remarkable reductions in ΣR, MSP, and projected range values were reported with increasing BaO concentrations. The acquired results nominate the use of these glasses in different radiation shielding purposes.

Charged particles and gamma-ray shielding features of oxyfluoride semiconducting glasses: TeO2-Ta2O5-ZnO/ZnF2

In this study, the uncharged/charged and photon shielding features of TeO2.Ta2O5.ZnO/ZnF2 tellurite-rich glass system with different ZnO/ZnF2 ratio (encoded as TTZ, TTZF4, TTZF8, TTZF12 and TTZF16) were comprehensively discussed. The mass attenuation coefficients (MAC) were achieved employing MCNPX simulation codes and the outcomes were verified with theoretical data computed by WinXCOM software. The MACs varied between 47.667 to 0.034 for TTZ glass (for ZnO=16 mol%) and the largest MAC values were gained for TTZ glass among the others. Several MAC-based photon attenuation parameters, Half Value Layer (HVL), equivalent atomic number (Zeq) and Exposure Buildup Factor (EBF), of TTZF glasses were also determined for the energy range of 0.015–15 MeV. The results indicated that the enhancement in ZnO grows the gamma-ray attenuation competences of TTZF glasses. Furthermore, removal cross section of fast neutrons (∑R) for TTZF glasses was found and it has been noted that higher glass density has enhanced the ∑R values. The ΣR values of TTZF glasses change between 0.1103-0.1174 cm-1. At last, projected range (PR) and mass stopping power (MSP) for charged particles has been investigated within the kinetic energy range between 0.01–10 MeV. It is found that all TTZF glasses possess nearly close MSP and PR values for proton and alpha particles. We trust that the results of this study will guide the radiation protection capabilities of tellurite-rich glass systems.

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.

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.

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.

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.

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.