Shielding Analysis Research Articles

Ballistic and Electromagnetic Shielding Properties of Epoxy Resin Reinforced with Carbon Black and Jute Fabric

This study explores the development of a multifunctional composite material by incorporating carbon black (CB) into an epoxy matrix reinforced with 30 vol.% jute fabric. The objective was to evaluate the impact of CB on the composite’s tensile properties, ballistic performance, and electromagnetic shielding effectiveness (SE) within the X-band frequency range (8.2–12.4 GHz). The epoxy composite with 30 vol.% jute and 5 vol.% CB (EJ30/CB5) exhibited 15% improvements in its tensile strength and elastic modulus compared to the epoxy composite with 30 vol.% jute (EJ30) only. Ballistics tests indicated no significant increases in absorbed energy or limit velocity, which may be attributed to the structural rigidity introduced by the CB. An electromagnetic shielding analysis revealed that the CB addition significantly enhanced the SE from ~2 dB in neat epoxy to 5–8 dB in EJ30/CB5, with absorption emerging as the primary shielding mechanism. The findings highlight the potential of CB- and jute-reinforced epoxy composites for applications requiring both mechanical robustness and electromagnetic interference shielding.

COG 11.3 New Features

COG is a high fidelity, multi-particle, Monte Carlo radiation transport code in development at LLNL since 1980 in support of multiple applications including nuclear criticality safety, radiation shielding, radiography, and subcritical multiplicity analysis. COG 11.3 is the latest version scheduled for public release in 2024 representing the culmination of ten years of development since previous releases. This paper describes the major new features available in COG 11.3 including: (a) updated nuclear data libraries; (b) updated activation data; (c) advanced LLNL Fission Reaction Event Yield Algorithm; (d) new time-tagged list-mode detector feature; (e) new spontaneous fission source feature; (f) new alpha and deuteron particle transport; (g) updated electron transport (implementing EGS5 with internal electron library generation using PEGS5); (h) three new estimators for the effective delayed neutron fraction; (i) new input pre-processor options for user-friendly generation of three-dimensional rectangular and triangular lattice geometries; (j) new parallel-processing capabilities for the inverse reactor period and CritDetVR features using MPI; (k) a new imaging detector feature; and (l) details of the modernized COG website at https://cog.llnl.gov. Like previously released versions, COG11.3 will be available to users through RSICC at ORNL, the Nuclear Energy Agency Data Bank at OECD, and by special arrangement through LLNL.

Radiation Shielding and Activation Analyses for Neutron Activation Measurement Facility at Advanced Radiation Technology Institute, Jeongup

Radiation Shielding and Activation Analyses for Neutron Activation Measurement Facility at Advanced Radiation Technology Institute, Jeongup

Contributon-Informed Approach to RPV Irradiation Study Using Hybrid Shielding Methodology

An important aspect of pressurized water reactor (PWR) lifetime monitoring is supporting radiation shielding analyses which can quantify various in-core and out-core effects induced in reactor materials by varying neutron–gamma fields. A good understanding of such a radiation environment during normal and accidental operating conditions is required by plant regulators to ensure proper shielding of equipment and working personnel. The complex design of a typical PWR is posing a deep penetration shielding problem for which an elaborate simulation model is needed, not only in geometrical aspects but also in efficient computational algorithms for solving particle transport. This paper presents such a hybrid shielding approach of FW-CADIS for characterization of the reactor pressure vessel (RPV) irradiation using SCALE6.2.4 code package. A fairly detailed Monte Carlo model (MC) of typical reactor internals was developed to capture all important streaming paths of fast neutrons which will backscatter the biological shield and thus enhance RPV irradiation through the cavity region. Several spatial differencing and angular segmentation options of the discrete ordinates SN flux solution were compared in connection to a SN mesh size and were inspected by VisIt code. To optimize MC neutron transport toward the upper RPV head, which is a particularly problematic region for particle transport, a deterministic solution of discrete ordinates in forward/adjoint mode was convoluted in a so-called contributon flux, which proved to be useful for subsequent SN mesh refinement and variance reduction (VR) parameters preparation. The pseudo-particle flux of contributons comes from spatial channel theory which can locate spatial regions important for contributing to a shielding response.

Phy-X/PSD and Gate/Geant4 analysis of gamma-ray shielding in novel tellurite-based glasses

Phy-X/PSD and Gate/Geant4 analysis of gamma-ray shielding in novel tellurite-based glasses

Optimization Analysis of Electric Field Shielding in Multi-Target Areas Using Transmission Lines Based on AHP-Improved PSO

To address the optimization problem of electric field intensity in multi-target areas under transmission lines, this work suggests combining the enhanced improved particle swarm optimization (IPSO) with the analytical hierarchy process (AHP). First, using finite element simulation software, a transmission line shielding model was created. Next, the number, erection height, and phase spacing of the shielding lines were studied in relation to electric field strength. Drawing on these results, field strength shielding in many target locations was optimized using the AHP-IPSO algorithm. Research has demonstrated that the electric field intensity beneath a transmission line can be greatly decreased by installing shielded cables, and that the peak field intensity can be decreased by 28.4% by installing three insulated wires. The AHP-IPSO algorithm effectively solved the multi-factor electric field shielding optimization problem, thus offering a novel method for addressing such problems. Compared to other algorithms, the AHP-IPSO algorithm exhibits better optimization performance and offers better shielding efficiency, while also accounting for the economic aspects of shielded wire erection.

Stress transfer, stress shielding, and micro-movement analysis in the implanted femoral bone region with various hip implant stem materials: A finite element approach

This study analyzed stress distribution, stress shielding, and bone-implant micro-movement in different zones of implanted femur bone with hip implant stem composed of Inconel 718, 316 Stainless Steel, Ti6Al7Nb, Ti6Al4V, Ti-12Mo-6Zr-2Fe (TMZF), and Ti-33.6Nb-4Sn (TNS). A 3D model of a well-known hip implant “Summit” was placed in an adult femur bone, and walking, standing, and sitting load instances were simulated as loading conditions using a finite element model (FEM). Increasing hip implant material hardness reduces stress transmission in Gruen zones 1, 2, 5, 6, and 7 of the femur bone but increases it in Gruen zone 3. It also enhances stress holding in the implant body and elevates the Stress Shielding index (SSI) at seven Gruen zones for each load case. TMZF and TNS hip implants in Gruen regions 5 and 7 have negative SSI values under specific load situations. At Gruen zone 3, the SSI value for implanted femur bone increases with hip implant stem material hardness and SSI values variation in implanted femur bone for hip implants of different materials at each loading scenario is within 10 %. However, SSI values do not follow any pattern at Gruen zone 4. Less stiff implants demonstrate increased micro-movement in bone-implant contact zones 1 and 2 due to higher stress transfer. Greater stiffness (Inconel 718) caused increased micro-movement in zone 3. The overall micro-movement (Average and Highest) found an incremental trend for hip implants with higher stiffer to lower materials. The lowest stiff material (TNS) is still in the range of appropriate micro-movement for promoting osteointegration. This study indicates TNS as a superior hip implant stem material due to its enhanced stress distribution, reduced SSI in most Gruen zones on implanted femurs, and acceptable micro-movement over the implant-bone area of contact. Further research is required to minimize SSI, particularly in Gruen zone 3, when using TNS hip implants in implanted femurs.

Spectroscopic, calorimetric, and radiation shielding analysis of lead-free transparent dysprosium-doped phosphate glasses

Eco-friendly phosphate glasses with 50P2O5-(50 – x)BaO-xDy2O3 (x = 0, 0.5, 1.0, 2.0, 3.0, 4.0 mol %) compositions were prepared and studied focusing on their potential for radiation attenuation and shielding applications. The glasses were synthesized by melting and subsequently characterized by X-ray diffraction (XRD), Fourier transform-infrared (FT-IR) spectroscopy, densitometry, refractive index, optical absorption, and differential scanning calorimetry (DSC). XRD confirmed the amorphous nature of the glasses, while FT-IR spectra indicated that the glass structure was preserved upon Dy2O3 inclusion. It was observed that both the density and refractive index generally increased with higher Dy2O3 content. Optical absorption data showed a linear increase in Dy3+ ion absorption with Dy2O3 concentration, confirming the effective incorporation of Dy3+ ions. Tauc and Urbach plots were also employed to analyze the absorption edges of the glasses. DSC thermograms revealed that the glass transition temperatures increased while glass stability improved with higher Dy2O3 content. The radiation shielding properties were assessed by evaluating parameters such as mass attenuation coefficients, linear attenuation coefficients, tenth value layer, mean free path, effective conductivity, and effective electron density against gamma-ray photons. Dysprosium doping was found to enhance gamma-ray shielding (from 1 keV to 100 GeV) based on theoretical methods. Additionally, the 3 mol % Dy2O3 doped sample exhibited greater fast neutron removal cross-sections. However, the undoped barium phosphate host demonstrated better stopping potential and lower projected ranges against ions (protons and carbon). Photon trajectories and dose attenuation properties were also investigated using the Particle and Heavy Ions Transport System (PHITS) Monte Carlo code, indicating that the Dy3+ doped lead-free transparent glass protects against ionizing radiation. Hence, the barium phosphate host and Dy3+-doped counterparts are attractive for use in ionizing radiation and nuclear facilities, such as hospitals, research centers, and industries.

Radiation Shielding Analysis of Multi-Component Glasses: Effects of Varying BaO, PbO2 and Gd2O3 Concentrations

This work investigates the impact of BaO, PbO2, and Gd2O3 on newly developed borate glasses’ radiation shielding characteristics. The transmission factor (TF) of the glasses is almost zero at the low energy of 0.0395 MeV, which indicates favorable low-energy photon shielding. The maximum TF is reported at 1.46 MeV for the free Gd2O3 glass sample, ranging from 0.89 (0.5 cm thickness) to 0.73 (1.5 cm thickness). Moreover, with more BaO, PbO2, and Gd2O3 content added to the glasses, the TF decreases, indicating an enhancement in the efficiency of the glasses’ radiation protection with the introduction of BaO, PbO2, and Gd2O3. There is a 4.309 to 5.068 g cm−3 increase in the glasses’ density, and, as a result, the mean free path decreases, suggesting improved performance for radiation protection with the adding of more BaO, PbO2, and Gd2O3 contents to the glasses. At 0.122 MeV, the free Gd2O3 glass’s half value layer value is 0.098 cm, while the tenth value layer is 0.325 cm.

Numerical Analysis of the In-Bore Magnetic Shielding of the Series-Enhanced Electromagnetic Railgun

Numerical Analysis of the In-Bore Magnetic Shielding of the Series-Enhanced Electromagnetic Railgun

Analysis of Cable Shielding and Influencing Factors for Indirect Effects of Lightning on Aircraft

Analysis of Cable Shielding and Influencing Factors for Indirect Effects of Lightning on Aircraft

Reusing of Both Agricultural and Industrial Wastes as Replacement Materials for Construction Industy: Radiation Shielding Analysis

Reusing and recycling wastes to produce new materials are seen as costeffective, sustainable solution for the economic and environmental problems especially in the agricultural and construction sectors in the worldwide. In the paper, four groups of waste samples including both agricultural and industrial wastes (tincal waste, Bayburt stone waste, tea waste, eggshell waste, marble dust waste and peanut shell waste) were produced by mixing in different ratios. The radiation protection parameters were found by Phy-X/PSD code and radiation shielding abilities of the samples were examined. Mass attenuation coefficient data were also compared by Xcom. In addition, spectroscopic results were provided based on XRD and SEM-EDS spectroscopic techniques. It is obtained that the shielding performances of the samples including tincal waste and Bayburt stone waste with the highest amount of marble dust waste and eggshell waste are the highest, respectively. The lowest protection property is obtained for the sample with Bayburt stone waste with marble dust waste and peanut shell waste consisting of lower Ca and higher C contents. It is observed that there is a direct relation between the amount of Ca and the radiation shielding capability of the samples. It is also determined that neutron shielding potential is the highest for tincal waste with marble dust and tea waste. It can be concluded that the newly prepared samples consisting of wastes in order to support reusing and recycling have good protective properties and use of the samples as replacement materials instead of cement or aggregate can be recommended.

Impact of Bi2O3 on the Structural, Optical, Radiation Shielding, and Dielectric Analysis of Lead Borosilicate Glasses Doped with TiO2

Objective: The principal aim of this investigation was to assess the impact of bismuth oxide on the optical properties, radiation shielding characteristics, and dielectric behavior of lead borosilicate glasses doped with titanium oxide at a low concentration. Method: We intended to utilize the conventional rapid melt quenching method to produce glasses with the following chemical composition: 25 PbO+ 15 B2O3 + 0.1 TiO2 + (59.9-x) SiO2 : x Bi2O3(0≤x≤12). Findings: XRD and SEM analyses were used to confirm the samples' non-crystalline properties, while DTA investigations were used to evaluate the samples' ability to form glass. The numerous structural elements were identified through the utilization of FT–IR and Raman analyses. The optical characteristics of glasses are determined by optical absorption studies. The findings derived from optical absorption spectral analyses revealed a progressive increase in the concentration of octahedral Ti4+ ions with the mol% Bi2O3 concentration. In order to analyse the glasses' dielectric properties, an impudence analyser was employed. The results obtained from these inquiries indicate that glasses do contain Bi2O3 at concentrations lower than 12 mol% experience a progressive increase in dielectric constant values. Further investigation is conducted into the radiation shielding properties of the glasses. Novelty: The findings indicate that the values of the glasses' optical band gap, radiation shielding ability, dielectric constant, and thermal stability are all directly correlated with their Bi2O3 concentration. Keywords: FT­IR, Raman, OBG, MAC, Activation Energy

Dysprosium-enriched polymer nanocomposites: Assessing radiation shielding and optical properties

This paper includes a comprehensive analysis of the radiation shielding, optical properties, and structural makeup of polymer composites that contain Dy2O3 additions. XRD-pattern investigates the effect of loading Dy2O3 content on PS, with the average crystallite size of Dy2O3 decreases from 39 nm to 30 nm as Dy2O3 increases from 2.5 to 7.5 wt% in the PS matrix. The optical properties of the nanocomposites showed that with the increase in the Dy2O3 content, the transmittance, as well as the direct and indirect band gap, decreased. The EgIndirect bandgap decreased from 3.1 to 2.75 eV with a Dy2O3 increase from 0 to 7.5 wt%, while the Egdirect Bandgap reduced from 4.6 to 4.35 eV. While the Urbach energy Eu and the refractive index increase, Eu rises from 0.48 to 0.60 e V, and n improves from 1.4 to 1.78 from 0 to 7.5 wt%. In order to conduct an accurate analysis of the gamma-ray attenuation capabilities of the selected new polymer composites, these composites were manufactured with varying proportions of the additive components. With the assistance of a Na(Tl) detector, experimental assessments were carried out on the gamma rays throughout a broad spectrum of photon energies, ranging from 81 keV up to 1416 keV. The sample encased in PS/Dy7.5 demonstrates excellent radiation attenuation, and it is important to note that this novel polymer shielding material does not include any hazardous components.

Structural, radiation shielding, thermal and dynamic mechanical analysis for waste rubber/EPDM rubber composite loaded with Fe2O3 for green environment

Increasing waste rubber recycling produces a specious range of products for many valuable applications. Waste Rubber/EPDM composite with different concentrations was prepared. Infrared spectroscopy (FTIR) is used to identify the chemical composition. A water absorption test, Dynamic mechanical analysis (DMA), and Thermal Gravimetric Analysis (TGA) were performed. The (75/25) WR/EPDM rubber composite exhibited the best behavior with the highest mechanical performance. Fe2O3 was added to (75/25) WR/EPDM rubber composite. Water absorption, FTIR, TGA, and DMA were investigated. The composite performance was improved with increasing Fe2O3 content. The linear attenuation coefficients (μ) were also measured as a function of the concentrations of Fe2O3 for γ-ray energy 662 keV by using 137Cs point source; the radiation shielding can be denoted by numbers of parameters like mass attenuation coefficient (μm), half value layer (HVL), Tenth value layer TVL and radiation protection efficiency (RPE%), radiation protection efficiency increased as Fe2O3 increased.

Nuclear analysis for the test cell lithium system interface cell during operation and shutdown

This paper presents the shielding analyses, which will be provided for supporting the design of the Test Cell Lithium System Interface Cell (TLIC) and safety assessment. The study considers the radiation decay source from IFMIF-DONES operation with beam-on. Radiation shielding simulations have been performed for the safety concerns. Detailed simulation geometry was created from CAD drawing for the TLIC. Neutron transport calculation was performed for all TLIC components concerned. The particle flux, biological dose and absorbed dose maps are provided in the study. A series of neutron transport are performed using the MCNP Monte Carlo McDeLicious neutron source code coupled with FISPACT for inventory calculations for TLIC design.

Numerical analysis of shielding of vibrations transmitted through the ground

Numerical analysis of shielding of vibrations transmitted through the ground

Bismuthite and cassiterite-doped borosilicate glass systems for X-rays attenuation: Fabrication and characterisation

For the first time, X-ray shielding glass (XSG) was fabricated using rice husk (RH) silica, bismuth, and tin mineral ores. The objective was to promote waste valorisation and circular economy by minimising the use of analytical grade silicon and metal oxides in large-scale radiation shielding glass production. The physical, structural, and low-energy X-ray attenuation properties of the new bismuthite and cassiterites-doped glass were characterised using XRD, FTIR, and low-energy mobile X-ray shielding analyses. The X-ray shielding parameters linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half value layer (HVL), tenth value layer (TVL), and mean free path (MFP) were comparatively examined alongside commercial lead/barium XSG used in hospital radiology units. XRD results showed that glasses with 0, 5 and 15 wt% dopants contain nanocrytallites measuring 19.43, 38.85 and 42.44 nm, respectively, with peaks in the 2Θ (28°) vicinity. FTIR revealed structural modifications that demonstrate the network modulation capabilities of cassiterite-sourced Sn ions. At 70 kVp tube voltage, the MAC of the 20 wt% dopant glass compares favourably with commercial Pb/Ba glass, while the 25 wt% variant has lower values than commercial Pb/Ba glass at 80 kVp tube voltage. The HVL and MFP of 25 wt% dopant glass compared favourably with commercial glass at 60 kVp X-ray tube voltage, suggesting the new glasses with x = 15, 20, 25 wt% dopants are competitive candidates for viewing window applications in low energy X-ray radiology units. Future studies will investigate the radiation attenuation efficiency of the new glass systems using point gamma sources.

ParaStell: parametric modeling and neutronics support for stellarator fusion power plants

The three-dimensional variation inherent to stellarator geometries and fusion sources motivates three-dimensional modeling to obtain accurate results from computational modeling in support of design and analysis of first wall, blanket, and shield (FWBS) systems. Manually constructing stellarator fusion power plant geometries in computer-aided design (CAD) and defining the corresponding fusion source can be cumbersome and challenging. The open-source parametric modeling toolset ParaStell has been developed to automate construction of such geometries in low-fidelity. Low-fidelity modeling is useful during the conceptual phase of engineering design as a means of rapidly exploring the design space of a given device. The modeling capability of ParaStell includes in-vessel components and magnets, for any given stellarator configuration, using a parametric definition and plasma equilibrium data. Furthermore, the toolset automates the generation of detailed, tetrahedral neutron source definitions and DAGMC geometries for use in neutronics modeling. ParaStell assists rapid design iteration, parametric study, and design optimization of stellarator fusion cores. As a demonstration of the design iteration capability, the effect of the three-dimensional parameter space on tritium breeding and magnet shielding is investigated, using the WISTELL-D configuration as a design basis. Blanket and shield thicknesses are varied in three dimensions, using the space available between the plasma edge and magnet coils as a constraint. The corresponding effects on tritium breeding ratio and magnet heating are tallied using the open-source Monte Carlo particle transport code OpenMC. The inclusion of additional and higher-fidelity modeling capabilities is planned for ParaStell’s future, as well as its implementation in machine-driven optimization.

Re-evaluation of shielding ability and induced activity of KSTAR with increased neutron yields

To determine the viability of the 2-fold neutron yield increase of the Korea Superconducting Tokamak Advanced Research (KSTAR) owing to the installation of a second neutral beam injection system to increase the plasma density and a divertor material change from graphite to tungsten to reduce the heat load, we performed a radiological evaluation and shielding analysis of an existing building structure and the KSTAR with an increased neutron yield per shot. According to the shielding analysis results, the weekly and annual doses outside the building did not exceed the criteria, and the fluxes and doses in the plasma experimental room were unaffected by the divertor material change. The maximum dose rate in the working area in the tokamak was 2.16E+03 μSv/h at the surface-plasma-facing components. However, the dose rate was reduced to the background level one month after a 1-shot operation of 300 s. Ar-41 was the major nuclide for the air activation calculations; however, the effluent level exceeded the derived air concentration after the 1-shot operation ended. The residual activity concentration of Ar-41 was reduced below the derived air concentration after 243 min. The annual operating condition of the KSTAR is suggested based on the evaluation results.