Radiation Shielding Capability Research Articles

Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contents

This work assessed highly effective bismuth borosilicate glasses' nuclear radiation shielding capabilities in terms of different concentrations of Bi2O3. Melt-quenching was the method used to create the glasses. The Phy-X/PSD program was used to compute the μm values. The bismuth borosilicate glasses' nuclear radiation shielding properties were determined in the 0.015–15 MeV energy range. Increasing Bi₂O₃ concentration resulted in an increase in mass attenuation coefficient, linear attenuation coefficient, and effective atomic number. Conversely, the half value layer and mean free path values decreased. The B48Bi17 sample, with its largest Zeff, is a great gamma attenuator. The results of a new study may help to clarify the nature of the Bi2O3 additive used in borosilicate glasses, which are a potential form of shield for use in industrial and medical radiation facilities.

Decoding the role of bismuth oxide in advancing structural, thermal, and nuclear properties of [B2O3–Li2O–SiO2]-Nb2O5 glass systems

This paper investigates the pivotal role of bismuth oxide (Bi₂O₃) in the enhancement of nuclear safety, structural, and thermal properties of glasses, specifically in the BNLS system. BNLS system has the formula [B2O3–Li2O–SiO2]-Nb2O5(20-x)–(Bi2O3)x (where x = 0.0,5.0,10.0,15.0 and 20.0 mol%). Through a comparative study, the potential advantages, and limitations of integrating Bi₂O₃ in place of traditional elements are highlighted, emphasizing its importance in the field of advanced glass materials. FTIR analysis showed the presence of Bi–O vibrations of the tetrahedral [BO4] groups and the Bi–O–Bi linkages. DSC testified the glass formation with increasing thermal stability of the formed glass with the inclusion of Bi2O3 into the glass system. Through the quantification of the Gamma Linear Attenuation Coefficient (GLAC) and Gamma Mass Attenuation Coefficient (GMAC), the work identifies the attenuation behavior against varying photon energies. Notably, a concentration-dependent rise in attenuation characteristics is observed, with BNLS20 exhibiting the most potent radiation shielding. Glass Half-Value Layer (GHVL) parameters and Mass Gamma Photon Penetration (GMFP) were measured, reinforcing that glasses with higher Bi2O3 concentrations and lower GHVL are better attenuators. The transmission factor (ln(I/Io)) was also studied, confirming that BNLS20 possesses the most effective radiation shielding capabilities. This research establishes that adding Bi₂O₃ to the [B2O3–Li2O–SiO2]-Nb2O5 glass system markedly improves its thermal stability and radiation shielding capabilities. BNLS20, in particular, emerges as a standout for radiation protection, surpassing both other BNLS variants and conventional shielding materials, thereby positioning it as an exceptional choice for advanced nuclear safety applications.

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.

Tailoring glass radiation shielding properties through the Integration of ZnO and CaO

In this study, borate glasses with a general formula of (80-x-y)B2O3–10BaO–10Na2O-xZnO-yCaO, where x = 10, 15, 20 and 25 mol %, and y = 5, 10, 15 and 20 mol % were prepared. The radiation shielding capabilities of the prepared glass system were investigated at a wide energy range of 0.015 MeV–15 MeV. The data reveal that, the values of the mass attenuation coefficient (MAC) vaired between 20.043 and 32.435 cm2/g at 0.015 MeV. The MAC demonstrated that the increase of the ZnO and CaO content within the glasses leads to increase the MAC values, and improve the absorption ability of the glasses. The relation between the density of the glasses and their linear attenuation coefficients (LAC) were studied. A positive linear relationship between LAC and density has been fond. At 0.150 MeV, the LAC values are 0.804, 0.874, 0.945, and 1.020 cm−1 for the glass with 5, 10, 15 and 20 mol % of CaO in the order, respectively. We also evaluated the ratio of half value layer (HVL) for all prepared glass samples with lowest and highest density. The results revealed that the calculated ratio of HVL is always >1. This means that the Zn25Ca20 sample requires a smaller thickness to attenuate the same number of photons as betweenZn10Ca5. This is desirable in situations where space is a constraints well as costs as a smaller material can be used. This study uniquely highlights the combined impact of ZnO and CaO on enhancing the radiation shielding performance of borate glasses, offering a novel approach to developing more efficient materials.

Iron borophosphate glasses: Merging optical transparency, structural integrity, and radiation shielding efficacy for sustainable uses

The research work explored the influence of iron doping on the optical behavior, structural characteristics, and radiation shielding capabilities of soda lime borophosphate glass system of composition xFe2O3-(42.5-x)B2O3-26CaO-28.7Na2O-2.8P2O5 (x up to 8 mol%). The glass samples doped with varying iron concentrations were synthesized via the conventional melt-quenching method. A comprehensive characterization approach was employed, integrating X-ray diffraction (XRD) analysis to probe the structural aspects, Fourier transform infrared (FTIR) spectroscopy to examine the molecular vibrations and bonding, and UV–visible spectroscopic techniques to investigate the optical properties. Furthermore, the study evaluated the potential of these iron-doped glasses as effective radiation shielding materials by assessing their attenuation performance against various radiation types. The influence of iron oxide (Fe2O3) addition on the borophosphate network, coordination environment, and optical absorption was examined. The radiation shielding characteristics, such as mass attenuation coefficient, half-value layer, mean free path, and other parameters, were assessed using Phy-x freeware program calculations. The results revealed the formation of an amorphous glass structure and the incorporation of iron ions into the borophosphate network. The addition of Fe2O3 influenced the borate superstructural units, the conversion of BO3 to BO4 units, and the optical absorption bands. The glasses exhibited promising radiation shielding properties combined with increasing Fe2O3 content.

Influence of WO3 replacement for CaO on physical, optical, and γ-ray protection properties of borotellurite glasses: A comparative study

Glasses with WO3 in place of CaO with the chemical formula 45B2O3+15TeO2+(18-X)CaO+22Na2O + XWO3: X = 0 (W-0), 1.5 (W-1.5), 3 (W-3), 4.5 (W-4.5), and 6 (W-6) mol% were prepared using the melt quenching method. A comprehensive study of the structural, physical, optical, and γ-ray protection properties of the prepared glasses was investigated. Density (ρ), molar volume (Vm), UV–Vis measurements, the MCNP5 simulation code, and PhX software were employed to achieve the aims of this study. The density (ρ) of the W-X samples increased slightly from 2.45 g/cm3 to 2.62 g/cm3 as WO3 content increased from 0 to 6 mol%. The molar volume (Vm) evinced the same trend as ρ. In the UV range, significant absorption was observed, rising as the molar concentration of WO3 increased. The direct optical gap (Eopt.(dir.)) declined from 3.59 eV to 3.24 eV, while the indirect gap (Eopt.(indir.)) declined from 3.27 eV to 2.36 eV. The Urbach energies (ΔE) ranged from 0.35 to 0.71 eV. The refractive index (n) increased from 2.33 to 2.59 as WO3 content increased. The molar polarizability (αm) and molar refractivity (Rm) increased. The linear-attenuation absorption (μ) order is: W-0 < W-1.5 < W-3 < W-4.5 < W-6. The W-6 glass sample possessed the lowest half- (HVL), and tenth- (TVL) value layer, as well as the lowest mean free path (MFP). Therefore, the W-6 glass sample offers the best gamma radiation shielding capability among the prepared W-X glasses. Within the investigated energy range, the effective atomic number (Zef) varied from 30.773 to 13.234, 35.398–13.969, 39.089–14.670, 42.103–15.338, and 44.611–15.977 for the W-0, W-1.5, W-3, W-4.5, and W-6 glasses, respectively. At 0.080 MeV, the mass-attenuation absorption (μm) of the investigated W-X glasses was higher than for TBLMC-X (TeO2–B2O3–Li2O–MoO3–CuO) and TS-X (9SiO2–Al2O3–Na2O–B2O3–TeO2) glasses.

3D Printing of Composite Radiation Shielding for Broad Spectrum Protection of Electronic Systems.

The miniaturization of satellite systems has compounded the need to protect microelectronic components from damaging radiation. Current approaches to mitigate this damage, such as indiscriminate mass shielding, built-in redundancies, and radiation-hardened electronics, introduce high size, weight, power, and cost penalties that impact the overall performance of the satellite or launch opportunities. Additive manufacturing provides an appealing strategy to deposit radiation shielding only on susceptible components within an electronic assembly. Here, a versatile material platform and process to conformally print customized composite inks at room temperature directly and selectively onto commercial-off-the-shelf electronics is described. The suite of inks uses a flexible styrene-isoprene-styrene block copolymer binder that can be filled with particles of different atomic densities for diverging radiation shielding capabilities. Additionally, the system enables the combination of multiple distinct particle species within the same printed structure. The method can produce graded shielding that offers improved radiation attenuation by tailoring both shield geometry and composition to provide comprehensive protection from a broad range of radiation species. The authors anticipate this alternative to traditional shielding methods will enable the rapid proliferation of the next generation of compact satellite designs.

Effect of temperature on gamma radiation shielding capabilities of bauxite-based refractory concrete

This work presents experimental and theoretical studies on gamma-ray shielding capabilities of bauxite-containing refractory concretes containing new types of inorganic cements belonging to the CaO-Al2O3 (as a reference), CaO-BaO-Al2O3-ZrO2 and CaO-Al2O3-Fe2O3-ZrO2 systems. Firstly, the structure, microstructure, hydration behavior of cements, and thermal stability analysis of hydration products were investigated using X-ray diffraction, scanning electron microscopy/energy-dispersive X-ray spectrometry (SEM-EDS) and Thermogravimetry-Differential Scanning Calorimetry (TG-DSC) coupled with Evolved gas analysis-mass spectrometry (EGA-MS). When both Fe2O3 and BaO occur in the form of hydraulic phases as Ca2AlFeO5 and BaAl2O4, respectively, or are structurally incorporated into Ca7ZrAl6O18, the iron and barium modify the nature of hydration products of the CaO-Al2O3-H2O-type. Secondly, three types of concretes containing refractory bauxite aggregates were developed and tested in terms of microstructure, phase content, volumetric density, and weight loss. The maximum weight loss at 110 °C was associated mainly with the evaporation of the capillary water and the physically adsorbed water (gel water), whereas the chemically bound water (crystal water) occurring in hydrates was released at higher temperatures. Slight variations of the volumetric density of the concretes due to temperature were found. The CCS of the concretes fell within the standard values of ca. 50–100 MPa for shielding refractory concretes. Finally, the effect of temperature on the gamma radiation shielding capabilities of concretes was evaluated using the transmission method for gamma rays with energy in the range of about 81–1400 keV. The obtained values of the linear and mass attenuation coefficients showed improvement in the shielding properties as compared with ordinary concrete. Moreover, the obtained results show no significant effect of elevated temperature on the gamma radiation attenuation properties of the studied bauxite-based refractory concretes which suggests that they may be very useful as shielding materials in severe thermal working conditions.

Thermal, and radiation shielding properties of SrO–B2O3–TeO2–ZnO–Bi2O3 glasses doped with Dy2O3

The newly proposed materials demonstrated outstanding and effective radiation shielding capabilities and promising mechanical properties. A series of (20-x) SrO-(73)B2O3-(5)TeO2-(1)ZnO-(1)Bi2O3 doped with x-Dy2O3 have been produced employing the traditional melt-quench process, with the concentration of Dy2O3 varying from 0.05 to 1.5 mol%. This research examined glass samples' structural stability, mechanical and thermal characteristics, and radiation shielding capabilities. All of the glasses were amorphous, as confirmed by the X-ray examination, and the glass with the label SBTZBD6 had the maximum density because of the higher Dy2O3 content. The insert of Dy2O3 into the glass composition increased density values from 2.94 to 3.04 g/cm3 for SBTZBD1 and SBTZBD6 and improved mechanical properties such as Poisson ratio and elastic moduli. The hardness Vickers showed the maximum value at 1095.7 HV corresponding to Dy2O3 1 mol%, indicating the influence of Dy2O3 addition on the mechanical properties. The ability of the generated samples to shield against several forms of radiation, such as alpha, proton, neutron, and gamma radiation, was examined using SRIM and Phy-X software. The lowest HVL is 0.009 cm for SBTZBD6 at 0.02 MeV, the highest HVL was observed at 15 MeV with a value equal to 7.066 cm for the same sample. Dy2O3 was used instead of SrO, significantly increasing the μ/ρ values and improving radiation shielding. However, it was discovered that fast neutron shielding experienced a reduction in energy loss per unit mass (mass stopping power) when SrO was replaced with Dy2O3. However, the substitution also reduced energy loss per unit mass for alpha and protons and fast neutron shielding. To sum up, this study's glass samples are highly recommended for ionizing radiation shielding.

Impact of neodymium oxide (Nd2O3) substitution in barium–boron-phosphate glasses: A pathway to superior mechanical, optical, and radiation shielding performance

This study delves into the impact of substituting Nd2O3 for Na2O in Barium–Boron-Phosphate glasses, aiming to enhance their mechanical strength, optical characteristics, and radiation shielding efficacy. Glasses with a composition of 50B2O3 + 20P2O5 + 20BaO + (10-x)Na2O + xNd2O3 (x = 0, 1, 2, 3, 4 mol%) were synthesized and characterized. The findings indicate that as the Nd/Na ratio increases, the density of the glass also rises within the range of 3.77–4.23 g/cm3. Moreover, the addition of Nd leads to notable alterations in the optical characteristics of the resulting glasses. Specifically, there is a shift observed in the UV absorption edges, coupled with a noticeable increase in absorption at visible wavelengths. Moreover, Nd2O3 addition reduced the Urbach energy (from 0.6018 to 0.2239 eV for Nd0-Nd4) and the optical band gap indicating improved electronic structure and decreased disorder. The mechanical properties studied using the Makishima-Mackenzie model show As the replacement ratio of Nd2O3 increases, there is a noticeable improvement in the glass's mechanical robustness. Importantly, Glasses with high Nd/Na ratio in their composition exhibit enhanced radiation shielding capabilities, evidenced by increased mass attenuation coefficients and effective removal cross-sections for photons and fast neutrons, respectively. These findings suggest that Nd2O3-doped glasses offer a promising pathway for developing superior radiation shielding materials with tailored properties for diverse applications in nuclear facilities, medical devices, and space exploration equipment.

Assessment of radiation shielding capability of a high-density TeO2–Tl2O–Ag2O glass system: A simulation and theoretical studies

We investigated the shielding properties of four selected glass samples among the 66 samples. These glass samples had the following compositions and densities: S1 (55TeO2+45Ag2O, density 6.28 g/cm3), S2 (55TeO2+5Tl2O+40Ag2O, density 6.37 g/cm3), S3 (50TeO2+15Tl2O+35Ag2O, density 6.49 g/cm3), and S4 (40TeO2+55Tl2O+35Ag2O, density 7.20 g/cm3). These glasses exhibit high density. We compute the mass attenuation and linear attenuation coefficients for these samples using MCNPX simulations and Phy-X software between 0.001 MeV and 15 MeV energy range. The derived mass attenuation coefficient (MAC) enables the calculation of key radiation shielding metrics. The tenth value layer, the half value layer (HVL), the mean free path (MFP), and the effective atomic number (Zeff) were also determined. Values of LAC values for S1, S2, S3 and S4 glasses span 244.91 to 0.24932 cm⁻1, 319.52 to 0.2625 cm⁻1, 447.24 to 0.28491 cm⁻1 and 379.480 to 0.273 cm−1, respectively. Correspondingly, HVL values range from 0.0028 to 2.78005 cm, 0.0021–2.6403 cm, and 0.00154–2.4327 cm and 0.002135–2.917403 cm for S1, S2, S3 and S4 glasses, respectively. Our findings reveal that results from both MCNPX and Phy-X exhibit consistency, supported by computed relative differences. Notably, the glass sample with a relatively higher TlO2 concentration demonstrates superior shielding properties across the entire energy spectrum. Importantly, these glass samples can significantly lower the strength of the x-rays and γ-rays.

Y2O3 reinforced B2O3–SiO2–BaO–Na2O glass system: A characterization study through physical, optical and gamma / neutron shields characteristics

Glasses with the composition 48B2O3– 13SiO2– 7BaO- (32-x) Na2O-xY2O3, (x = 0, 1, 2, 4, and 8 mol %) were synthesized by the melt quenching procedure. There is good transparency in every glass sample. The increase in density (2.825–3.894 gm/cm3) of the present glasses is what triggered the decline in molar volume (25.41–21.80 cm3/mol) and the decrease in the Boron–Boron distance (0.475–0.452 nm). The estimated values show that Eopt.indi. &Eopt.di are 2.317, 2.672, 2.8, 2.98 and 3.1 eV, 2.69, 2.92, 3.05, 3.25, and 3.44 eV respectively, whereas (Eu) values declined. As the Y2O3 increased the refractive index (nD) increased. (nD) of the synthesized glasses using Eopt.indi.&Eopt.di were estimated. To find the radiation properties of the suggested glasses, the Phy-X/PSD code was employed. We concluded that the current glasses have better radiation shielding capabilities when employed in such fields. As the Y2O3 replacing ratio increased ∑R increased.

Comparative analysis of TiO2, Fe2O3, CaO and CuO in borate based glasses for gamma ray shielding

This research intends to utilize melt-quenching technique in order to examine the radiation shielding capability of 10 % Mo, 10 % Na2O, 20 % PbO, and 60 % B2O3 glass system, with varying CaO, TiO2, CuO, Fe2O3 or Mo. XCOM and MCNP simulations were utilized to analyze the radiation shielding properties of the fabricated glasses. The results revealed CuO having the superior MAC of 49.91 cm2/g, then Fe2O3 with 49.24 cm2/g, followed by CaO with 49.10 cm2/g, and TiO2 with 48.49 cm2/g as the least. CuO and Fe2O3 were confirmed to have least HVL compared to CaO and TiO2. The value of the lead equivalent thickness showed fluctuation against the gamma energy, where it raisess within the photoelectric region and falls after the photoelectric region. The data reveal that, the lead equivalent thickness at 0.1 MeV were 7.88 cm, 7.86 cm, 7.81 cm and 7.80 cm for TiO2, Fe2O3, CaO, and CuO in the same order, respectively. The transmission factor (TF) raises as the gamma energy raises, having TiO2 as the highest with 76.068 %, while the radiation protection efficiency dropped as the energy raises.

Impact of Bi2O3 on the glass system B2O3 -TeO2–MgO–PbO on the purpose of radiation shielding efficacy

In this study, eight glass samples were prepared with the composition of [x Bi2O3-(75-x) B2O3–15TeO2 –5MgO–5PbO; where x = 0, 10, 20, 25, 30, 40, 50, and 60 mol%]. In the composition of those glass samples, various amountsof B2O3 were replaced by Bi2O3 to improve the glass material's radiation shielding capability. The mechanical properties of these glasses have been evaluated using densimeter and microhardness. The Vickers microhardness (Hv) slightly decreases as the amount of Bi2O3 increases due to the formation of Non-Bridging Oxygen (NBO). To evaluate the radiation shielding effectiveness of the prepared glass samples, we performed Monte Carlo simulations of several shielding parameters. The mass attenuation coefficients of the experimentally produced BTMPBi glass series were calculated using NIST and MCNP6, and reasonable agreement was found between the simulation and experimental results. The relative difference between NIST and MCNP6-based results was calculated, and the maximum deviation was 2.21% for the 1173 keV gamma ray incident in the BTMPBi60 glass sample. The value of the mean free path of those prepared glass samples maintained the following trend - BTMPBi0> BTMPBi10> BTMPBi20> BTMPBi25> BTMPBi30> BTMPBi40> BTMPBi50>BTMPBi60. The prepared glass sample BTMPBi0 showed a 2.6 times higher value of the mean free path at energy 1332 KeV compared with the prepared BTMPBi60. Analyzing the composition of the prepared glass samples, it is clear that the greater the amount of Bi2O3 the greater the value of linear attenuation coefficient (LAC) and effective atomic number. Based on the results, it can be concluded that the glass sample containing 60 mol % of Bi2O3 (BTMPBi60) exhibited the highest radiation shielding capability among all of the prepared samples.

Evaluation of incorporation of granite waste and SnO2-NPs into coating mortar for gamma-ray shielding

This study explores the use of waste granite and tin oxide nanoparticles (SnO2 NPs) as replacements for sand in mortar composites containing Ordinary Portland Cement (OPC), Hydrated Lime (HL), and Quarry Sand (QS). Scanning electron microscopy (SEM) imaging revealed an increase in particle distribution between voids in the control mortar, enhancing photon absorption. The density of the prepared mortar samples exhibited a notable increment, with a 2.12–2.30 g/cm3 increase through the inclusion of SnO2-NPs. Additionally, the Phy-X software was employed to experimentally measure and theoretically calculate the linear attenuation coefficient (LAC), demonstrating a high degree of agreement between the two values. The LAC values were found to increase with the replacement ratio of granite waste and SnO2 nanoparticles, demonstrating the effectiveness of these materials as radiation shielding agents. This study investigates the effect of substituting waste granite and SnO2 nanoparticles for sand in mortars, resulting in an increase in LAC levels, indicating potential for improved radiation shielding capabilities, although the degree of change in LAC may be energy-dependent. The half value results (HVL) results demonstrated a significant decrease in required material thickness for radiation shielding applications with numerical values of 1.153, 0.734, 0.456, 0.351, and 0.261 cm for the control, Mor-1, Mor-2, Mor-3, and Mor-4 samples, respectively, at an energy of 0.06 MeV.

Advancing mechanical durability and radiation shielding properties in Silicon dioxide (SiO2) glasses through various incorporations: A comparative analysis

Silicon dioxide (SiO2) glasses, known for their high thermal stability, excellent optical transparency, and substantial mechanical strength, are crucial in numerous technological applications, including radiation shielding. This research explores the impact of compositional variations in SiO2-based glasses on their mechanical and radiation shielding properties, particularly focusing on the inclusion of heavy metal oxides (HMO) and rare earth elements (REE) like neodymium (Nd). Through the systematic investigation of fifteen distinct glass samples with varying concentrations of specific oxides and elements, we investigate the compositional changes and their influence on physical properties and their effectiveness in attenuating radiation. Our findings demonstrate that the incorporation of Nd significantly enhances the glass's radiation shielding capabilities. Glasses doped with Nd exhibited higher effective atomic numbers and electron densities, which translate to superior attenuation characteristics at lower photon energies. This is highlighted by the exceptional performance of the 20Nd sample, showing the lowest exposure build-up factors (EBF) at 10 mean free paths (mfp), indicating its potential as a premier candidate for shielding applications against various energy levels of radiation. Moreover, the variation in the Elastic Modulus of the glass samples underscores the significant impact of the glass matrix composition on its mechanical properties, suggesting a delicate balance between network formers and modifiers in determining the glass properties. It can be concluded that the neodymium-doped SiO2-based glasses may be considered as targeted compositions in fine-tuning material properties to meet specific application requirements. As the demand for efficient radiation shielding materials grows across medical, industrial, and space exploration sectors, our findings provide a solid foundation for the development of new glass formulations tailored for enhanced mechanical properties and superior radiation protection levels.

Microstructure and radiation shielding properties of lead-fiber reinforced high-performance concrete

The increasing application of nuclear technology in medical fields has amplified the demand for radiation shielding materials. Traditional large-volume concrete cannot simultaneously exhibit excellent neutron and gamma-ray shielding capabilities while ensuring superior mechanical properties. This study tailored a novel lead fiber-reinforced high-performance concrete (LFRHPC) with lead fibers and magnetite aggregates, focusing on radiation attenuation. The effect of lead fibers on the mechanical performance, microstructure and radiation attenuation characteristics for LFRHPC was comprehensively evaluated. The results indicate a significant improvement in the mechanical performance of LFRHPC compared to traditional radiation shielding concrete (RSC), due to the scientific skeleton design. Additionally, the pore structure in LFRHPC is refined by incorporating lead fibers. Moreover, the interfacial transition zone (ITZ) between the cementitious matrix and magnetite is improved because of the very low water-to-binder ratio. To assess the radiation attenuation ability of LFRHPC, both direct measurements and simulation models were utilized. The data reveals that the porosity of LFRHPC plays a crucial role in its shielding effectiveness against neutron and gamma radiation. Furthermore, the addition of lead fibers considerably boosts its neutron and gamma-ray shielding attenuation capabilities. In summation, LFRHPC combines excellent mechanical properties and radiation shielding capabilities, making it suitable for construction applications in medical settings.

Study of optical, structural and radiation shielding properties of (55 − x)TeO2–20ZnO–25B2O3–xEr2O3 glass matrix

Abstract Erbium doped zinc boro-tellurite (EZBT) glass samples with molar composition of (55 − x)TeO2–20ZnO–25B2O3–xEr2O3 (x = 0.0, 0.5, 1.0, 1.5 and 2.0 mol.%) were prepared by a conventional melt quenching technique. The prepared samples were characterised using X-ray diffraction, Fourier transform infrared spectroscopy and ultraviolet–visible spectroscopy techniques to investigate the structural, optical and dielectric properties. To study the radiation shielding capabilities, the parameters such as mass attenuation coefficient (μ m), half-value layer (HVL), effective atomic number (Z eff) etc., were evaluated using WinXCom software. Judd–Ofelt analysis was carried out to determine the intensity of electronic transitions and other radiative transition parameters within the 4f shell of erbium ions. The μ m values in a range of (108.5–0.03) cm2 g−1 for energy range (0.01–10) MeV were obtained for 2.0 mol.% erbium-doped tellurite glass matrix. The μ m and HVL values were also compared with conventionally used ordinary concrete and specific lead borate glass at certain energies. The detailed investigation of this current EZBT glass matrix is very useful in the specific optical and radiation shielding applications of this EZBT glass.

Characterization of Radiation Shielding Capabilities of High Concentration PLA-W Composite for 3D Printing of Radiation Therapy Collimators.

This work evaluates the radiation shielding capabilities of the PLA-W composite for MV energy photons emitted by a linear accelerator and the feasibility of manufacturing a clinically-used collimator grid in spatially fractionated radiotherapy (SFRT) using the material extrusion (MEX) 3D printing technique. The PLA-W filament used has a W concentration of 93% w/w and a green density of 7.51 g/cm3, characteristics that make it suitable for this purpose. Relevant parameters such as the density and homogeneity distribution of W in the manufactured samples determine the mass attenuation coefficient, directly affecting the radiation shielding capacities, so different printing parameters were evaluated, such as layer height, deposition speed, nozzle temperature, and infill, to improve the protection performance of the samples. Additionally, physical and mechanical tests were conducted to ensure structural stability and spatial variability over time, which are critical to ensure precise spatial modulation of radiation. Finally, a complete collimator grid measuring 9.3 × 9.3 × 7.1 cm3 (consisting of 39 conical collimators with a diameter of 0.92 cm and center-to-center spacing of 1.42 cm) was manufactured and experimentally evaluated on a clinical linear accelerator to measure the radiation shielding and dosimetric parameters such as mass attenuation coefficient, half-value layer (HVL), dosimetric collimator field size, and inter-collimator transmission using radiochromic films and 2D diode array detectors, obtaining values of 0.04692 cm2/g, 2.138 cm, 1.40 cm, and 15.6%, respectively, for the parameters in the study. This shows the viability of constructing a clinically-used collimator grid through 3D printing.

Nuclear power plant pipeline detection robot based on a new radiation-proof material

Soft robots are gradually gaining recognition in recent years for their ability to work in extreme environments. However, radiation shielding is a major issue when designing soft robots for use in nuclear environments. In this paper we present an effective soft robot design and develop new radiation shielding materials that enable the robot to perform a variety of tasks in the complex pipelines of a nuclear power plant while being sufficiently radiation shielded. To achieve this, we used a mixture of silicone and lead powder with excellent radiation shielding capabilities and designed and built a soft robot prototype consisting of multiple pneumatic actuators and a resin frame. It is capable of moving through complex pipelines and performing inspection tasks, while also providing radiation shielding for the internal components of the robot. Finite element simulations and prototype experiments were then carried out to evaluate the robot's performance in various scenarios. Simulation results show that the soft robot is able to perform inspection of nuclear power plant pipelines efficiently and effectively. Furthermore, the radiation shielding provided by the radiation-proof material is effective in protecting the internal components of the robot from radiation exposure. In conclusion, we have successfully developed a soft robot prototype that is capable of performing pipeline inspections in extreme environments such as nuclear power plants, while providing adequate radiation shielding. The proposed approach can be extended to other soft robotics applications in the nuclear environment and has the potential to improve the safety and efficiency of nuclear power plant operations.