Neutron Radiation Shielding Research Articles

Production and evaluation of the polyester composites containing pyrite and niobium diboride for radiation protection

The presented study focused on investigating the radiation shielding properties of polyester/pyrite/niobium diboride (FeSNbB) composites. Various gamma-ray shielding parameters were evaluated with help of a HPGe detector system. Theoretical and simulation results are further evaluated by WinXCOM, GEANT4 and FLUKA codes, and the obtained results are compared with experimental values in the energy region 59.5 keV–1332.5 keV. The prepared samples are additionally evaluated using kerma relative to air values and Exposure build-up factors. Then, for the evaluation of neutron radiation shielding, effective removal cross sections for fast neutrons were determined for FeSNbB composites. Electron attenuation efficiency (AE%) for the produced composites was assessed across the energy spectrum of 4 MeV–18 MeV, utilizing experimental data from a Linac machine and theoretical predictions from Eclipse TPS. The results were found to be compatible with each other. FeSNbB50 has the best shielding properties among the studied composites.

Microstructure and radiation shielding characteristics of PVA fiber-reinforced ultra-high performance concrete

The application of nuclear technologies simulates the development of radiation shielding materials. Traditional heavy-weight concrete used for radiation shielding is limited in practical construction due to the poor mechanical properties and durability. This study developed a PVA fiber-reinforced ultra-high performance concrete (UHPFRC) with magnetite as heavy aggregates used for radiation shielding. Due to the scientific skeleton design, UHPFRC exhibits superior mechanical properties, with compressive strength and flexural strength reaching up to 121.9 MPa and 23.2 MPa, respectively. The microstructure of UHPFRC was investigated in detail and the results revealed that the incorporation of PVA fibers refined the pore structure of UHPFRC. The interfacial transition zone between magnetite aggregates and cementitious matrix in UHPFRC was much denser than that in traditional concrete due to the low water to binder ratio. The gamma and neutron radiations shielding capacity of UHPFRC were evaluated by the combination of actual measurement and simulation. By introducing light nuclei and refining the pore structure, the incorporation of PVA fibers improved the neutron radiation shielding capabilities of UHPFRC by 5.1%.

High-performance PEEK composite materials research on 3D printing for neutron and photon radiation shielding

With the rapid advancement of nuclear energy technology, addressing technical challenges in the field of radiation shielding, particularly achieving lightweight and efficient shielding against neutron and multiple radiation types, remains a formidable task. To address the aforementioned issues, this study investigates the 3D printing performance of polyether ether ketone (PEEK) composite materials for shielding against both neutron and photon multibeam radiation. High-content 3D printing filament is developed, with simultaneous shielding capabilities against neutron and photon radiation. This research successfully accomplishes the high-density 3D printing of PEEK shielding composites with increased concentrations of boron carbide(B4C), tungsten(W), and both materials. The experimental results indicate that 3D printed specimens of B4C/W/PEEK, a neutron and photon shielding composite material, exhibit excellent mechanical properties. Importantly, the radiation shielding composite 3D function parts achieves effective shielding against muitibeam radiation and weight reduction compared to traditional radiation shielding materials.

Structural, morphological, optical, and radiation shielding properties for BaO–TeO2 glass ceramic modified with different oxides: Bi2O3, MoO3, MnO2, and TiO2

This study investigates the impact of different modifiers on the optical, structural, morphological, and radiation-shielding properties of BaO–TeO2 glass ceramics. Various physicochemical instruments were used to assess structure, morphological, and optical properties, such as X-ray diffraction (XRD), Fourier transform infrared (FTIR), scanning electron microscope (SEM), and UV–Vis. The photon protection features were computed theoretically based on the Phy-X program. The XRD results showed different main phases in glass ceramics samples; other secondary phases appeared in each sample. The morphological results affirm the formation of some crystallized and glassy states with heterogeneous agglomerations. The linear attenuation coefficient (LAC) values at 0.2835 MeV for BiBTGC, TiBTGC, MnBTGC, and MoBTGC samples are 1.427, 0.852, 0.870, and 0.952 cm−1, respectively. Based on this result, the BiBTGC and MoBTGC samples showed the best gamma and neutron radiation shielding performances, respectively. While TiBTGC and BiBTGC samples showed the highest and lowest charged particle shielding properties, respectively.

Smart Foams: Boron Nitride‐Graphene Nanoplatelet Foams for Tunable Radiation Shielding and Strain Sensing

AbstractAs space exploration advances, the demand for lightweight, multifunctional materials has substantially grown. Hybrid two‐dimensional (2D) material foams of different boron nitride nanoplatelets (BNNP)‐to‐graphene nanoplatelets (GNP) ratios are developed, which exhibit dual functionality: neutron radiation shields and strain sensors. The relationship between the composition, processing, microstructure, and their resultant neutron shielding and strain‐sensing properties are investigated. The hybrid foam properties can be finely tuned by adjusting BNNP:GNP compositions (1:0, 3:1, 1:1, 1:3, and 0:1). In terms of neutron radiation shielding, the mass absorption coefficient of hybrid foams increased with added BNNP, peaking at 14.9 cm2 g−1 for a pure BNNP foam. This mass absorption coefficient is 1.6 times that of pure GNP foams and almost 75 times that of aluminum. The radiation shielding properties are simulated using Geant4, a Monte Carlo‐based platform, and the simulations displayed a similar trend to the experimental results. The strain‐sensing properties of hybrid foams, measured by their gauge factor, exhibited exponential growth with rising GNP concentrations. Starting from the electrically insulating BNNP foam, the gauge factor increased to 53.4 with 25% GNP concentration and reached 201.8 for pure GNP foams. These findings highlight the versatility of the hybrid 2D material foams for space exploration.

Enhancing gamma radiation shielding properties of iron metal and natural rubber composites

AbstractA comparative study was conducted to investigate the gamma and neutron radiation shielding properties of composites made from iron metal (micro and nano) dispersed within natural rubber (NR). The aim was to attenuate neutron and γ‐rays. The study utilized the gamma spectroscopy technique and the Monte Carlo FLUKA code. To assess the gamma ray shielding, a 3×3 Nal (Tl) detector and radioactive point sources were employed. Two comparative studies were carried out, one using Fe loaded NR (Fe/NR) composites in microsize and the other using Fe/NR composites in nanosize. The objective was to determine the impact of iron nanoparticles on the shielding ability of the composites. The findings revealed that the Fe/NR composites in nanosize exhibited superior gamma radiation shielding ability compared with the Fe/NR composites in microsize. These results were supported by the FLUKA Monte Carlo code, which demonstrated good agreement with both the experimental and theoretical XCOM data.

Structure, mechanical, and neutron radiation shielding characteristics of mechanically milled nanostructured (100-x)Al-xGd2O3 metal composites

Metallic substances are favored for storing and transporting spent nuclear fuels (SNFs) due to their thermal stability, mechanical strength, and corrosion resistance. Adding gadolinium (Gd) significantly enhances neutron shielding, improving efficiency with reduced thickness and dimensions. In this study, Al–Gd2O3 metal nanocomposites were synthesized using powder-processed mechanical milling. The crystal structure features of (100-x)Al-x%Gd2O3 samples with varying percentages of Gd2O3 (5 %, 10 %, and 15 % by weight) were analyzed by X-ray diffraction. Microstructural properties were studied using scanning and transmission electron microscopy (SEM and TEM). The synthesized composites' neutron and γ-radiation shielding characteristics were investigated theoretically using the MCNP6.2 transport code. Analysis of the XRD data revealed prominent peak shifts with increased milling time, indicating reduced particle sizes. Differential scanning calorimetry (DSC) indicated Gd2O3-induced changes in temperature behavior, and the Vickers microhardness tests demonstrated enhanced mechanical strength with increasing gadolinium concentration. Improved neutron radiation shielding was observed with higher Gd2O3 content. Our study highlights the potential of Gd2O3-enriched metal matrix composites for advanced industrial applications.

Sm2O3 micron plates/B4C/HDPE composites containing high specific surface area fillers for neutron and gamma-ray complex radiation shielding

In this study, a series of Sm2O3 micron plates/B4C/HDPE composites composed of synthesized Sm2O3 fillers (Sm2O3 micron plates) are prepared for shielding neutron and gamma radiation. The influence of micromorphology of Sm2O3 fillers on neutron and gamma radiation shielding properties of composites is investigated in detail. The XRD pattern reveals that the phase of synthetic Sm2O3 is cubic crystal systems, body-centered cubic lattices, and its space group is Ia 3‾ (206). SEM images and BET analyses reveal that the micromorphology of synthesized Sm2O3 is micron plates. The BET-specific surface area of the Sm2O3 fillers is increased with addition of urea content. The differential scanning calorimetry (DSC) curves reveal that Sm2O3 fillers increase the melting temperature of the composites, which is up to 138.6 °C. The thermogravimetric analysis (TGA) results reveal that the initial thermal degradation temperatures of the composites are all above 440 °C. The neutron and gamma radiation shielding tests show that Sm2O3 fillers with high BET-specific surface area (8.20 m2/g) and uniform size improve the neutron and gamma shielding rate of composites. A superior composite containing 10 wt% Sm2O3 (R = 1:25, R value represents the molar ratio of rare earth elements to urea)/20 wt% B4C/70 wt% HDPE has a neutron radiation shielding rate of 98.7% with a thickness of 15 cm under the 252Cf neutron source and a gamma radiation shielding rate of 72.1% with a thickness of 15 cm under 137Cs gamma source. And these lead-free and environment-friendly composites can be widely used in the neutron and gamma complex radiation fields.

Radiation shielding effectiveness, structural, and mechanical properties of HDPE/B4C composites reinforced with Fe2O3-Al2O3-Al-Fe fillers

The fast neutron and gamma-ray attenuation properties of pure high-density polyethylene and its composites were investigated, including 90 HDPE/10 B4C (wt%) and 60 HDPE/10 B4C/30X (wt%) (Where X represents iron oxide, aluminum oxide, iron, and aluminum). The examined samples were analyzed using a scanning electron microscope, and their mechanical properties were assessed. The composite of 60 HDPE/10 B4C/30 α-Fe2O3 (wt%) shows better mechanical properties than those of other composites under investigation. 239Pu–Be was used as a source of fast neutrons with a neutron yield of 1.7 × 106 n s−1 and was detected by the Stilbene scintillator. Neutron removal cross-section with dependent parameters, the mean free path and half-value layer of the prepared composites, were calculated. Furthermore, the gamma-ray transmission through the produced composites has been examined. The composite containing 30% iron oxide exhibited superior shielding characteristics for neutrons and gamma rays compared to the other analyzed samples. The computed values of the shielding characteristics indicate that the produced composites are highly effective for shielding fast neutrons and gamma rays in radiation facilities.

Foam with direction: unraveling the anisotropic radiation shielding properties of 2D boron nitride nanoplatelet foams

Neutron radiation exposure is one of the main challenges faced during space missions. There is a critical need for advanced lightweight radiation shielding materials. Two-dimensional (2D) boron nitride nanoplatelets (BNNP) are excellent candidates for polymer matrix nanofillers due to their superior neutron shielding and thermal and mechanical properties. Furthermore, the 2D material anisotropic behavior unlocks the potential for composite property tailoring. This study fabricated ultra-lightweight lamellar BNNP foams (density 0.05 g cm–3 and 97.5% porous) via freeze-drying processing. The neutron shielding effectiveness or mass absorption coefficient of the BNNP foams with walls perpendicular to the direction of the radiation source was 14.47 cm2 g–1, while that of the foam with parallel configuration was only 8.51 cm2 g–1. The orientation-dependent neutron radiation shielding properties were modeled using the Beer-Lambert law for porous composite materials. The BNNP foam in this study has the potential to benefit advanced tailorable radiation shielding technologies for future aerospace missions.

Evaluation of gamma and neutron radiation shielding parameters of some glass materials by Monte Carlo and theoretical method

The present study investigates the gamma-ray and neutron shielding properties of PbCu3Ti4O12, lithium borate (Li2B4O7), lithium borate glasses doped with dolomite (CaMg(CO3)) and neodymium oxide (Nd2O3) to assess their effectiveness as shielding materials against ionizing radiation. The gamma-ray shielding properties, including the attenuation and absorption characteristics of the materials were examined and compared using Geant4-based GATE simulation, XCOM, and EpiXS in the photon energy range of 80-2000 keV. When the shielding properties of the available materials were compared, it was determined that Li2B4O7-Nd2O3, PbCu3Ti4O12, Li2B4O7-CaMg(CO3), and Li2B4O7 exhibited the best shielding properties, in order from most effective to least effective. The neutron shielding properties of these materials, including scattering, absorption, and moderation capabilities, were also determined using MRCsC, Phy-X/PSD and estimation ΣR/ρ of elements. The results were then compared with the current literature. Li2B4O7, CaMg(CO3), and Nd2O3-doped lithium borate glass samples showed higher effective fast neutron removal cross-section values than water and concrete in all calculation methods. It shows that the investigated glass materials are better gamma and neutron beam absorbers and have the potential for use in gamma and neutron beam shielding applications.

Development and application analysis of high-energy neutron radiation shielding materials from tungsten boron polyethylene

The purpose of this study is to develop a high-energy neutron shielding material applied in proton therapy environment. Composite shielding material consisting of 10.00 wt% boron carbide particles (B4C), 13.64 wt% surface-modified cross-linked polyethylene (PE), and 76.36 wt% tungsten particles were fabricated by hot-pressure sintering method, where the optimal ratio of the composite is determined by the shielding effect under the neutron field generated in typical proton therapy environment. The results of Differential Scanning Calorimetry measurements (DSC) and tensile experiment show that the composite has good thermal and mechanical properties. In addition, the high energy-neutron shielding performance of the developed material was evaluated using cyclotron proton accelerator with 100 MeV proton. The simulation shows a 99.99% decrease in fast neutron injection after 44 cm shielding, and the experiment result show a 99.70% decrease. Finally, the shielding effect of replacing part of the shielding material of the proton therapy hall with the developed material was simulated, and the results showed that the total neutron injection decreased to 0.99‰ and the neutron dose reduced to 1.10‰ before the enhanced shielding. In summary, the developed material is expected to serve as a shielding enhancement material in the proton therapy environment.

Gamma, neutron, and charged particle shielding performance of ABKT glass system

In this study, the gamma, charged, thermal neutron, and fast neutron radiation shielding parameters of (5+x)K2O-(25-x)TeO2-(10-x)As2O3-(60-x)B2O3 (where x ranged from 0 (ABKT1) to 20 (ABKT5) mol% in 5 mol% steps) were calculated and simulated. In addition, important optical parameters such as the reflection loss (Rloss), molar refractivity (Rm), molar polarizability (αm), optical transmission (TOpt), metallization criterion (M(n)), static dielectric constant (Ɛsta), optical dielectric constant (Ɛopt) of the glasses, were computed and juxtaposed with the chemical composition of the glasses. The values of Rm and αm decreased from 17.213 cm3/mol to 15.247 cm3/mol and 6.830 x10−24 cm3 to 6.05 x10−24 cm3, respectively, as K2O replaced TeO2 in the ABTK glass system. Similarly, Rloss reduced from 0.173 to 0.164, while TOpt increased from 0.705 to 0.719. The values of M(n), εsta, and εOpt were in the range 0.381–0.397, 5.565–5.87, and 4.565–4.871, respectively. The mass attenuation coefficients of ABKT1–ABKT5 were within the range of 0.0276–30.8789, 0.0269–29.6485, 0.0262–28.3373, 0.0255–29.9370, and 0.0249–25.4384 cm2/g, respectively. ABKT1 is the best gamma photon absorber among the ABKT glasses for narrow and broad beam transmission modes. For electrons, protons, alpha particles, and heavy carbon ions, the mass stopping powers of the glasses follow the order ABKT1>ABKT2>ABKT3>ABKT4>ABKT5. ABKT1 had the best photon and ion absorbing capabilities, while ABKT5 has the highest thermal and fast neutron interaction cross-sections. The ABKT1 glass demonstrated the potential to perform better than some commercial glass shields, standard shielding glasses, light and heavy concretes, and a host of other materials as a transparent gamma radiation shielding material.

A simulation study on neutron radiation shielding in space conditions

The work studies the possibility of using a polymer composite based on polytetrafluoroethylene and modified radiation shielding fillers for protection against neutron radiation in space conditions. The physico-mechanical properties of the composite are presented, as well as the simulation of the neutron radiation passage through the polymer composite is performed by the Monte Carlo method using the GEANT4 software toolkit. The polymer composite proposed has high structural properties necessary for use in the space sphere. The Vickers hardness for a load of 200 g is 12.11, the erosion wear is 0.049∙10−3 mm3/g, the density is 4232 kg/m3. The most effective thickness of the protective layer to attenuate the intensity of neutron radiation is 8 cm, to reduce the equivalent dose of 30 g/cm2. The thickness of the protective layer made of the proposed polymer composite against cosmic radiation is 35% less than that of aluminum and 77% less than that of polyethylene, which is a very important factor for using the material in spacecrafts because of extremely limited free space on board. This indicates the prospects of its use for neutron radiation shielding at high energies to achieve complete and effective protection of astronauts and spacecraft equipment.

A KGd(WO4)2 powder/Er2Ce2O7–SiO2 aerogel with low thermal conductivity and excellent radiation shielding performance for thermal insulation of nuclear power plants

To meet the application requirements of thermal insulation materials for nuclear power plants, Rare earth composite aerogel (KGd(WO4)2 powder/Er2Ce2O7–SiO2) were prepared by compounding rare earth precursor sol and rare earth powder with silica aerogel based on directional freeze drying method. The effect of thermal diffusivity of rare earth salt crystals on the thermal conductivity of rare earth composite aerogel was found, and the mechanism of the effect of the type and morphology of rare earth powder on the γ-ray shielding performance was explored. The irradiation and temperature resistance measurement shows that the KGd(WO4)2 powder/Er2Ce2O7–SiO2 aerogel can withstand 1 × 107 Gy γ-ray and high temperature baking above 1100 °C. KGd(WO4)2 powder/Er2Ce2O7–SiO2 aerogel is an ideal new generation multi-functional shielding and thermal insulation material for nuclear power plants because of its low thermal conductivity, excellent γ-ray and neutron radiation shielding, high temperature resistance and radiation aging resistance.

Effect of chromium substitution on the gamma and neutron radiation shielding properties of calcium hexaferrite nanoparticles

Effect of chromium substitution on the gamma and neutron radiation shielding properties of calcium hexaferrite nanoparticles

Preparation and characterization of novel boron containing nanocomposites with neutron radiation shielding properties

AbstractPVA/PEO/PVP‐B4C and PVA/PEO/PVP‐BN polymer nanocomposites were prepared using boron nitrite (BN), boron carbide (B4C), polyvinyl alcohol (PVA), polyvinylpyrrolidone (PVP), and polyethylene oxide (PEO). B4C and BN nanopowders were added to the mixture at three different percentages: 5%, 10%, and 20%. Thermal characterization was performed by differential scanning calorimetry, differential thermal analysis and thermogravimetry. Scanning electron microscopy, X‐ray photoelectron spectroscopy, and X‐ray diffraction were used for surface analysis and crystal structure characterization. The atomic distribution was determined by elemental analysis. Neutron shielding properties were performed at three different gamma peak areas, 1293.56 keV, 1097.33 keV, 416.86 keV, and calculated total macroscopic cross‐section ∑T and half‐value layer. The ∑T values were found to be in the range of 7.99–14.37 for all synthesized composites. B4C‐doped composites show higher protection efficiency against slow thermal neutrons than BN‐doped samples.Highlights Poly(vinyl alcohol)/poly(ethylene oxide)/polyvinylpyrrolidone composites containing boron nanoparticles are flexible and workable. Nanocomposites were prepared with a simple, cheap, and fast method. Prepared boron nanocomposites exhibit slow thermal neutron stopping even at 3 mm thickness. PVA90/PEO5/PVP5‐BN and PVA90/PEO5/PVP5‐B4C composites are good candidates for demanding military applications such as vehicle and body armor.

Ulexite/HDPE-Bi2O3/HDPE layered composites for neutron and gamma radiation shielding

In this study, 5, 10, and 15 wt% ulexite (NaCaB5O6(ΟH)6·5H2O, hydrated sodium calcium borate hydroxide) and 15 wt %Bi2O3 filled high density polyethylene (HDPE) composite materials were fabricated through conventional melt-extrusion processing techniques in the form of a layered structure in order to absorb both neutron radiations and the secondary radiations resulting from neutron induced reactions. In the layered structure, HDPE was used to slow down neutrons, while ulexite and Bi2O3 were used to capture thermal neutrons and secondary gamma radiations, respectively. The properties of ulexite/HDPE and Bi2O3/HDPE composites were investigated through scanning electron microscopy (SEM), X-ray diffraction (XRD), thermogravimetric analysis (TGA). The mechanical properties (tensile and hardness) of composite materials were also investigated. The results showed that the addition of ulexite and Bi2O3 particles does not change the thermal and mechanical properties of the HDPE composites significantly. Total macroscopic cross-section of the composites was determined using a 239Pu–Be (α,n) neutron source, while their linear and mass attenuation coefficients were determined using a137Cs gamma-ray source. The results show that ulexite filled HDPE composites enhance neutron shielding property and Bi2O3 filled HDPE composites provide good shielding performance for gamma rays.

Gamma, charged particle and neutron radiation shielding capacities of ternary composites having polyester/barite/tungsten boride

The presented work investigates the photon, charged particle and neutron radiation shielding performances of polyester-based composites filled with barite and/or tungsten boride by using experimental, theoretical, and Monte Carlo simulation techniques. The amount of barite/tungsten boride varying from 0 wt% to 50 wt% in the material and polyester resin were exploited as filler and base materials, respectively. Experimental evaluation of BaWB composites has been performed with help of an HPGe detector based gamma spectrometer as well as 22Na, 133Ba, 137Cs and 60Co radioactive point sources with energies in the range of 276.4–1332.5 keV. The experimental data were compared to those theoretically calculated in WinXCOM as well as Monte Carlo (MC) simulations, i.e., MCNP6, GEANT4 and FLUKA codes. The obtained mass attenuation coefficients for the produced composites were in good agreement with the results of MC simulations and WinXCOM software. Comparing to the other polymer composite samples, the sample with the maximum tungsten boride weight percentage has the best radiation shielding property because of having the highest attenuation coefficients and lowest absorption thicknesses.

Eco-friendly transparent glass prepared from rice straw ash for neutron and charged particle radiation shielding

The current study aimed to fabricate and investigate new glass system incorporating silica from rice straw ash (RSA). The effect of adding different concentrations of bismuth oxide (Bi2O3) on the glass's structure was examined using FTIR. The A.C. conductivity of the prepared glasses over the frequency range (120 Hz − 100 kHz) and the temperature range (300–620 oK) have been measured. Based on its electron density, a substance's electrical conductivity can alter as photon energy increases. For the current investigated glasses, the electron density (Neff) and electrical conductivity relation over the energy range (0.015–10 MeV) were calculated. Glass samples' ability to attenuate radiation such as neutrons, electrons, protons, and alpha particles has been investigated. For neutrons, the effective removal cross-section (∑R, cm−1) and the total macroscopic cross-section (∑T, cm−1) are calculated. For charged particles like protons (H+) and alpha (He2+), SRIM software has been used to determine the glass Mass Stopping Power (MSP) and the Projected Range (PR). For electrons (β−), MSP and the Continuous Stopping Down Approximation (CSPA) were calculated using ESTAR (NIST). On the other hand, Phy X/Zextra software was used to determine glasses effective atomic numbers (Zeff) over a broad energy range. As a result, BSiBi20 glass with the highest Bi2O3 concentrations (20 mol. %) shows superior shielding features for fast neutrons (∑R = 0.128 cm−1) compared to the competitors like ordinary concrete (O.C.). For charged particles, BSiBi20 glass achieves the lowest MSP, CSPA, and the highest Zeff values over the entire energy range. The KERMA (Kinetic Energy Released per unit Mass of the Absorbing material) calculations indicated a significant influence on the elemental composition of the glass system in the intermediate photon energy regime.