XCOM Code Research Articles

Investigation of nano MgO loaded polyvinyl chloride polymer in protective clothing as a nonlead materials

Recently, investigation of advanced shielding materials to be used as an alternative to lead apron has become important. In the current study, MgO loaded into PVC matrix as a non-lead modern shielding composite was modeled to evaluate its performance on radiation protective clothing (RPC). Parameters such as mass attenuation coefficient (MAC), mean free path (MFP), flux buildup factor (FBF), transmission factor (TF) and lead equivalent value (LEV) of samples were calculated using MCNPX Code. The simulation of the MCNP code was validated, by comparing the mass attenuation of concrete sample, with standard XCOM data and very good agreement was attended between XCOM and MC Code results. The MAC of nano and micro-sized samples were also compared with pure PVC and it was found that the nano MgO particle exhibits higher attenuation compared to micro MgO particle and pure PVC. The results show that, the MAC of samples increased to 63.13 % in 1.332 MeV with increasing filler concentration of nano MgO to 50 wt% relative to pure PVC. Investigation of LEV shows that nano MgO sample has more effective than Pb in 1.173 and 1.332 MeV gamma ray energy so that it provides 36.46 % and 11.13 % lighter RPC than Pb ones.

Calculating the gamma-ray attenuation properties for some materials with the WinXcom software

This research investigated the attenuation properties of gamma ray for some materials, lead (Pb) and tin (Sn), in the energy region from 0.1 - 3 MeV using X-COM code. As a result of increasing photon energy, both MAC and LAC of a selected material decreased. Lead (Pb) offers more effective shielding of gamma rays than tin (Sn) since it has the highest μ and μm values coupled with the lowest HVL and TVL.

Effect of colemanite mineral on gamma radiation attenuation properties of vinyl ester resin

In this study, it is aimed to experimentally and theoretically obtain the gamma radiation attenuation properties of vinyl ester resin (VE) containing different rates of colemanite (CO) mineral and to compare these results. In the first stage, experimental measurements were performed using a gamma spectroscopy system containing a NaI(Tl) detector at three different gamma energies (511, 835 and 1275 keV) emitted from two different radioactive sources (22Na and 54Mn). As a result of the experiments, linear attenuation coefficients (LACs) of VE samples were obtained. The variation of LACs according to the density of the samples were investigated. The obtained results showed that LACs increased the density of the VE samples increased. Using the experimental LAC results, the half (HVL) and tenth (TVL) value layer thickness, mean free path (MFP) and transmission rate values were calculated. In the second stage of the study, LACs were calculated theoretically with the help of XCOM code using the chemical contents of VE samples. As a result of the comparison of the LACs obtained experimentally and using the XCOM code, it was observed that they were in good agreement. In addition, the results obtained with the XCOM code gave information about the variation of the attenuation coefficient in different energy regions. Based on all these data, it was concluded that as the amount of colemanite in the vinyl ester resin examined in the study increased, the gamma radiation shielding performance increased.

Gamma-ray attenuation properties of polymer biomaterials: Experiment, XCOM and GAMOS results

This study aims to compute and measure the linear attenuation coefficients of two biomaterials used in the human body as synthetic materials. These are used as bone cement and have applications in contact lens production and dentistry (coded as P1) also glass ionomer cement is a frequently preferred material in restorative dentistry applications (coded as P2). In the computational part of the study, a mono-energetic photon source between 1 keV and 20 MeV was used in the simulations performed using the GAMOS 6.2 program. In the experimental part, the linear attenuation coefficients of polymer materials were measured by using different radioactive sources at 6 different certain energies ranging from 511 to 1332 keV. A gamma spectrometer consisting of a NaI (Tl) detector was used for this purpose. Using the XCOM code, the experimental and simulation results were compared to the theoretical results, and a very good agreement was found between them. The simulation results demonstrated that the Monte Carlo technique can be used as an alternative to calculating the mass attenuation coefficients at the desired gamma energy, particularly for physically difficult to produce samples.

CoCrFeNiSi high entropy alloy: Synthesis, structural and radiation shielding properties

High entropy alloys (HEAs) have emerged as a distinct class of alloys with unique design strategies, different from traditional alloys. These alloys hold great promise for diverse applications, and the investigation of their nuclear radiation shielding properties has become an important and emerging area of research. In this experimental study, an equimolar CoCrFeNiSi HEA was prepared using the ball milling method. The focus was on characterizing the crystalline structure, morphological features, and radiation shielding properties of the synthesized HEA. X-ray diffraction analysis revealed that the HEA exhibited a face-centered cubic (FCC) phase structure. The crystallite size was significantly reduced from 23.63 nm to 3.22 nm, indicating the refinement of the microstructure. The homogeneity of the alloy was confirmed through scanning electron microscopy with energy-dispersive X-ray spectroscopy (SEM-EDX), which showed that the five elements were uniformly distributed within the powder alloy. To evaluate the radiation shielding properties, linear attenuation coefficients (LAC) of the CoCrFeNiSi HEA powder were measured using a 662 keV gamma source and a NaI(Tl) detector system (ORTEC® 905–4). The experimental LAC values were determined to be 0.2140 ± 0.01 cm⁻1. Theoretical calculations using MCNP6.2 and XCOM code were also performed and showed good agreement with the experimental results. Comparing the CoCrFeNiSi HEA with common shield materials such as thin films, glass systems, and some composites, it was found that the HEA outperformed them in terms of radiation shielding effectiveness. This demonstrates the potential of the CoCrFeNiSi HEA as an advanced alternative to conventional shielding materials, with potential applications in various fields.

Optical properties and radiation shielding competence of Bi/Te-BGe glass system containing B2O3 and GeO2

In this study we present the optical features including several parameters, gamma-ray photon and fast neutron absorption parameters of quaternary glasses with the chemical structure: xBi2O3 + (80-x)TeO2 + 10B2O3 + 10GeO2 for x = 40, 50, and 60 mol% and coded as Bi/Te-BGe1, Bi/Te-BGe2, and Bi/Te-BGe3 respectively. The FLUKA Monte Carlo and XCOM code were used to evaluate the photon shielding parameters of the glasses for energies between 0.284 and 2.506 MeV. The optical quantities such as the molar refractivity Rm, molar polarizability αmol, reflectance loss (Rloss), optical transmission (Topt), metallization criterion (M) and the static dielectric constant εstaof the glasses were estimated to understand their optical characteristic. Mass attenuation coefficient of 0.345, 0.368, and 0.386 cm2/g was obtained for Bi/Te-BGe1–3 respectively at 0.284 MeV. Evaluated Zeff ranged from 30.94 to 53.22, 32.73 – 56.29, 34.52 – 58.75 for the Bi/Te-BGe1–3 glasses respectively. The HVL within the investigated energy similar to other estimated photon shielding parameters showed great enhancement as the density and Bi2O3 content of the glasses improved. Similar improvement on the fast neutron removal cross section also increased from 0.1141 to 0.1178 cm−1 as bismuth oxide increases in the glass system. The estimated optical parameters also showed great dependence on the chemical structure of the glasses. The present Bi/Te-BGe1–3 glasses showed excellent fast neutron and photon absorption capacity compared to some common shields; this makes them potentially useful for radiation protection applications.

A study on radiation shielding potentials of green and red clayey soils in Turkey reinforced with marble dust and waste tire

The increasing radiation applications in our daily life makes it essential to protect ourselves from the harms of radiation by using alternative, cheap and natural materials. The present study aimed to analyze the radiation shielding abilities of green and red clayey soils from Oltu/Erzurum in Turkey, reinforced with waste tires and marble dust. For the purpose to investigate the shielding features of the samples, radiation attenuation parameters were determined by using EpiXS software, which can calculate partial or total cross-sections, partial or total mass attenuation coefficients, electron densities, effective atomic numbers, and buildup factors for energy absorption and exposure between 1keV and 1GeV. We compared the obtained mass attenuation coefficients and total atomic cross-section values of the samples with those of a widely used shielding material, ordinary concrete, to make a meaningful evaluation about the shielding potentials of the samples. To validate obtained values by EpiXS, we also calculated the mass attenuation coefficients of the samples by XCOM code, and compatible results were obtained. Among all the studied clayey soil samples, green clay reinforced with marble dust and waste tire has the highest shielding capability. It can also be mentioned that reinforcement with marble dust and waste tire improves the shielding ability of the clayey soils.

Radiation shielding properties of concrete containing magnetite

In this study, linear attenuation coefficients of concretes containing different rates of basalt-magnetite aggregates were measured for gamma energies of 511, 662, 835, 1173, 1275 and 1332 keV emitted from 22Na, 137Cs, 54Mn and 60Co radioactive sources respectively, using the gamma spectroscopy system containing NaI(Tl) detector. According to the ratio of basalt-magnetite aggregate used in concretes, the variation of linear attenuation coefficient was investigated. The measured linear attenuation coefficient (μ) results were compared with the theoretical values obtained using the XCOM code. Experimental and theoretical results were observed to be compatible with each other. In addition, using the experimentally obtained linear attenuation coefficients, Half Value Layer (HVL), Tenth Value Layer (TVL), Mean free path (MFP) and radiation protection efficiency (RPE) values were also determined. It can be seen from those of results that the linear attenuation coefficients are linearly related to the basalt-magnetite ratio in the concrete. While it is also linearly related to radiation protection efficiency (RPE), inverse linear relations have been observed for the values of Half Value Layer (HVL), Tenth Value Layer (TVL) and Mean free path (MFP).It can be concluded that the using basalt-magnetite as aggregate in concrete is an important material to develop concrete in terms of radiation shielding.

Study on the radiation shielding features of some chemical compounds

In the present work, radiation shielding features of some chemical compounds were studied in terms mass attenuation coefficient (urn), total atomic cross section (6t), electronic cross section (6e), effective atomic number (Zeff) and Effective electron density (Neff). Measurement was done using transmission experiment includes NaI (Tl) detector and radioactive sources. Measured results of were compared with theoretical results obtained from XCOM code. Gamma ray sourcesemit energies 122KeV to 1330 KeV were used to irradiate inorganic materials.Behavior of the selected compounds with incident energy was studied in detailed. Obtained shielding parameters were observed to vary with the intensity of photons and decreased with increment of energy. From the measured results, it is observed that Barium sulfateand ferric oxide have the highest mass attenuation coefficient (µm) as compared to other materials.Finally, it was suggested that barium sulfate and ferric oxide are good candidates in the preparation of efficient gamma ray shielding materials.

Conductive natural and waste rubbers composites-loaded with lead powder as environmental flexible gamma radiation shielding material

It is well known that materials with lead (Pb) content are very effective as protective materials against radiation. Natural rubber (NR) has been loaded with 30 phr of N220 black (critical concentration) as a conductive and reinforcing filler. These rubber matrices are loaded with different concentrations of Pb powder (up to 100 phr) as filler. Gamma attenuation study was carried out using 3″ × 3″ NaI (Tl) (scintillation detector) gamma-ray spectrometer for (Cs-137), (Co-60), (Ba-133), and (Eu-152). The effect on the shielding property of Pb/NR composite was studied by varying the content of Pb and photon energy. It was found that the addition of Pb filler remarkably increases the linear attenuation coefficient (μ) of Pb/NR composites, especially for low photon energy. Linear attenuation coefficient experimental measures and theoretical calculations (using the XCOM code) were performed. It was noted that there is a reasonable agreement between measured and calculated results. In this paper, gamma-ray radiation shielding parameters are also studied for composites based on waste rubber. Its experimental results showed that Pb/W/NR composites have better γ shielding ability compared to Pb/NR ones at the Pb contents so, these are promising materials for fabricating protecting clothes against radiation in addition to their low cost and effective aid to get a clean environment.

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.

Radiation shielding features of zirconolite silicate glasses using XCOM and FLUKA simulation code

This work aimed to investigate the ionizing radiation shielding features of zirconia silicate SiO2Na2OCaO —xZrO2 (SCNZ) glass system. The mass attenuation coefficients (μ/ρ) were generated by FLUKA Monte Carlo simulation code and the obtained data was verified via the calculated data from XCOM software over an extended photon energy range of 0.015 – 20 MeV. The obtained values of μ/ρ were used to evaluate several important shielding parameters such as half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), and effective electron density (Neff). Results reveal that μ/ρ, MFP, HVL, Zeff, and Neff of the investigated glasses strongly depend on photon energy and chemical composition. Additionally, by using GP fitting parameters, the exposure buildup factor (EBF) of the investigated glasses were calculated. Results show that the greatest values of buildup factors exhibit at higher energies for all glass samples. Finally, the values of fast neutron removal cross section (ΣR) and the kinetic energy loss rate (Mass Stopping Power, MSP) of alphas and protons passing through the studied glasses were evaluated. Results display that the insertion of ZrO2 improves the nuclear shielding capability of SCNZ glasses. Especially, SCNZ7 glass owns superior shielding ability for charged particles as well as gamma radiation.

Scanning electron microscopy (SEM), energy-dispersive X-ray (EDX) spectroscopy and nuclear radiation shielding properties of [α-Fe3+O(OH)]-doped lithium borate glasses

Goethite [α-Fe3+O(OH)]-doped lithium borate glasses in the chemical form of [(100 − x) Li2B4O7 mineral x = 10, 20, 30, 40 wt%] were synthesized and investigated in terms of their ability to protect the human being and environment from ionizing radiation. Elemental analysis of four different goethite [α-Fe3+O(OH)]-doped lithium borate glass samples called GOG10, GOG20, GOG30 and GOG40 prepared in different contribution rates was tested using energy-dispersive X-ray technique. In addition, the surface morphology of the manufactured glass samples was determined by scanning electron microscopy. The glass samples subject to the study were evaluated in terms of radiation shielding properties by calculating the shielding parameters such as mass attenuation coefficient (μm), half value layer, mean free path, effective atomic number (Zeff), exposure and energy absorption build-up factors, effective removal cross section (ΣR) for fast neutron and RDD (for gamma and neutron) with the help of the XCOM and MCNPX simulation code. Mass stopping power and projected ranges values of the studied glass samples were calculated in order to consider the shielding performance against proton and alpha particles. The results showed that increase in goethite additive increases the gamma protection capacity of glasses. As a result, the glass sample with the highest goethite contribution encoded with GOG40 has better shielding efficiency in terms of the gamma and neutron radiation shielding.

Shielding capabilities study of light-gray, pale-pink and orange-pink Zacatecan quarries against ionizing photons using EDXRF and XCOM code

In this work the shielding capacity of three quarries widely used in the construction industry in Mexico has been determined. The reported features include the mass interaction coefficients, the linear attenuation coefficients and the average value layers. The Energy Dispersed X-Ray Fluorescence (EDXRF) shows that an element such as oxygen (contained in Portland concrete and gypsum, but not in quarries), which alone is irrelevant to shield ionizing energies, may become relevant to explain the shielding capacity of materials. The total linear attenuation coefficients and the half value layers were calculated for photon energies related to the medical field. Our results show that light-gray, pale-pink and orange-pink Zacatecan quarries shield ionizing photons below 70 keV three times better that gypsum and that they shield even better than Portland concrete. The experimental photon transmission of 0.662 MeV γ-rays in terms of the thickness of the G1, G2 and G3 quarries, adjusts without significant differences to the provisions of the attenuation law.

Evaluation of photon, neutron, and charged particle shielding competences of TeO2-B2O3-Bi2O3-TiO2 glasses

In this study, photon, neutron and charged particle shielding competences of five different glass systems which have the common chemical composition TeO2-B2O3-Bi2O3-TiO2 and contain different mole ratios of TeO2 in each sample were studied comprehensively. The fundamental photon shielding parameters, mass attenuation coefficient (µ/ρ), half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), and electron density (Neff) were evaluated in the range of 0.015–20 MeV. The µ/ρ values of all investigated glasses were simulated by using Geant4 Monte Carlo simulation code. Besides, the simulation work was supported utilizing the web version of XCOM code and the outcomes from two methods were compared. A good agreement between two methods was observed. Results reveal that µ/ρ, MFP, HVL, Zeff and Neff parameters of the investigated glasses strongly depend on photon energy and chemical composition. Also, the energy absorption buildup factors (EABF) and exposure buildup factors (EBF) of the proposed glasses were calculated via G-P fitting parameters for photon energies in between 0.15 and 15 MeV. Results show that the greatest values of buildup factors take place at higher energies for all glasses. Finally, calculation of the fast neutron removal cross section (ΣR) values of the glasses were performed. According to our calculations, ΣR values vary between 0.1169 cm−1 for TBBT30 sample with TeO2 = 30 mol% (ρ = 6.39 g/cm3) and 0.1048 cm−1 for TBBT88 sample with TeO2 = 88 mol% (ρ = 5.39 g/cm3). Consequently, it can be said that the TBBT30 glass seems to be the most promising shield to be utilized for both gamma and neutron shielding implementations among investigated TBBT glasses.

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

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

Preparation and characterization of bismuth-filled high-density polyethylene composites for gamma-ray shielding

An attempt has been made to prepare the nonlead-based gamma shielding materials by adding different weight percentages (0%, 10%, 20%, and 40%) of bismuth in high-density polyethylene (HDPE) matrix. Gamma shielding parameters such as linear attenuation coefficient (μ), mass attenuation coefficient (μm), half-value layer, tenth value layer relaxation length (λ), and percentage attenuation were determined for all synthesized samples using 3“×3” NaI (Tl) detector for 59.54 keV energy. The results obtained from attenuation studies have shown that the shielding efficiency of synthesized HDPE+Bi composites increases with an increase in the weight percentage of bismuth. The experimentally obtained mass attenuation coefficient values are compared with Monte Carlo simulation using Monte Carlo N-particle code and XCOM code and are in good agreement with each other. The mechanical parameters such as tensile strength, tensile modulus, and elongation at the break were also determined for synthesized composites. Among the prepared composites, HDPE containing 40 wt% of bismuth (HDPE+40% Bi) has shown good radiation shielding property for 59.54 keV gamma rays along with good mechanical properties. Therefore, HDPE+40% Bi can be considered as a better lead-free shielding material for low-energy gamma rays.

Attenuation Parameters and Effective Atomic Numbers of Concretes Containing Pumice for Some Photon Energies by Experiment, Simulation and Calculation

Photon mass attenuation coefficients ( µ ) and effective atomic numbers ( Z eff ) of three types of concretes containing pumice mineral in different rates (0%, 50% and 100%) were studied by photon transmission experiments and by simulations for 511, 835 and 1275 keV energies. Experimental procedure was realized by using a 3ʺ×3ʺ NaI(Tl) connected to a 16k multichannel analyzer detector system. In simulations, Geant4 Monte Carlo simulation toolkit was used to estimate the total mass attenuation coefficients. For theoretical calculations, web version of XCOM code was used at 1 keV – 100 GeV energy region for comparison. Also, mean free paths and half value layer thicknesses of concretes were calculated at this energies by means of attenuation coefficients obtained by three methods. Results from each method were found to be in a reasonably good agreement.

Evaluation of the shielding parameters of alkaline earth based phosphate glasses using MCNPX code

Abstract Glass systems of composition 16XO–3Al2O3–6CuO–20Na2O–55P2O5 (where X = Sr, Ca, Mg and Ba mol%) have been investigated to check its potential utilize as gamma ray shielding material. Different shielding quantities namely mass attenuation coefficient (µ/ρ), effective atomic number (Zeff), half value layer (HVL) and mean free path (MFP) have been evaluated using MCNPX code and XCOM program at different photon energies between 0.015 and 10 MeV. The obtained data revealed good agreement between the µ/ρ values derived from XCOM and MCNPX code (version 2.6.0). It is found that the mass attenuation coefficients of BaO-doped phosphate glass are higher than those of the other alkaline earth elements–doped glasses, whereas MgO possess the lowest values. This indicates that the BaO-doped phosphate glass is the superior gamma radiation attenuator among the studied glass samples. The gamma shielding performance of the glasses under study has been compared to some commercial glasses and different concrete samples in terms of MFP.

Photon and neutron shielding features of quarry tuff

The shielding characteristics of quarry tuff (cantera) against photons and 241AmBe neutrons, were determined. The effective atomic number of cantera, the Exposure and the Energy absorption buildup factors for photons in cantera were also calculated. The XCOM code was used to calculate the photon interaction coefficients. Also, Monte Carlo method was used to model a photon transmission experiment in cantera. Collided and uncollided photon fluence, Kerma in air, and Ambient dose equivalent were estimated. With the uncollided photon fluence the linear attenuation coefficients were determined and compared with those calculated with the XCOM code. The linear attenuation coefficient for 0.662 MeV photons was compared with the coefficient measured with a NaI(Tl)-based γ-ray spectrometer and a 137Cs source. The Monte Carlo model was also used to estimate the neutron spectra of 241AmBe neutrons in function of cantera thickness, the Effective and the Ambient dose equivalent for the collided and uncollided neutrons. Cantera has good shielding properties for low energy photons and poor shielding features against 241AmBe neutrons.