Abstract
The quest for next-generation radiation shielding hinges on finding lead-free alloys that balance high density with environmental safety. In this work, we targeted three transition metal arsenides (VAs, MoAs, and TaAs) to determine their efficacy against ionizing radiation across a wide energy range from 0.015 MeV to 15 MeV. By leveraging the Geant4 Monte Carlo toolkit and benchmarking against the XCOM database, we achieved high-fidelity simulations with deviations below 1%. Among the candidates, TaAs demonstrated the highest photon attenuation efficiency, characterized by a linear attenuation coefficient of μ = 1.463 cm−1 at 0.5 MeV and a half-value layer of λ½ = 0.47 cm at 0.5 MeV. Critically, at a thickness of 0.1 cm, TaAs delivers a dose reduction of over 50% relative to VAs. Statistical reliability was rigorously validated using the Kolmogorov–Smirnov test (p = 1.00), confirming no significant difference between simulated and theoretical XCOM data distributions. These findings establish TaAs not merely as a replacement for conventional materials, but as compact, lead-free shielding alternative optimized for space-constrained diagnostic systems.
Keywords: Lead-free alloys, Geant4 MC toolkit, Radiation shielding, Simulation, XCOM
Subject terms: Engineering, Materials science, Physics
Introduction
The mitigation of radiation exposure in medical diagnostics and nuclear facilities necessitates the continuous development of advanced shielding materials. However, a primary challenge lies in engineering barriers that reconcile high attenuation efficiency with lightweight and compact structural designs. Historically, radiation protection has relied on concrete and lead (Pb). While effective, Pb possesses significant drawbacks, including high toxicity, low mechanical strength, and a low melting point that can lead to radiation leakage under prolonged thermal exposure1. Similarly, concrete-based materials are susceptible to dehydration and cracking over time, which compromises their structural integrity and absorption efficiency due to density fluctuations2,3. To address these limitations, various material classes have emerged as potential candidates. Ceramic and glass systems offer transparency and ease of fabrication but are often limited by brittleness and lower adaptability in high-energy environments. Polymeric nanocomposites and ferrites provide flexible and tunable shielding properties through the incorporation of high-Z nanoparticles, such as bismuth or tungsten, yet they may struggle with thermal stability and high filler loading requirements4–20. In contrast, alloys offer a superior balance of mechanical durability and high mass density, making them ideal for high-intensity environments21–26. Recent studies have highlighted the transition toward lead-free alloy systems to reconcile high attenuation efficiency with environmental safety26–29. Specifically, experimental and theoretical investigations into lead-free alloy compositions have demonstrated that optimizing the atomic mass and density can significantly enhance gamma-ray shielding performance30. While other materials like polymeric nanocomposites and ferrites provide flexible shielding through high-Z nanoparticle fillers, transition metal alloys remain the most robust candidates for compact and sustainable shielding solutions.
This study addresses the need for high-performance shielding by investigating a new set of lead-free, transition metal arsenide-based alloys: VAs, MoAs, and TaAs. These materials were selected for their high mass densities—ranging from 6.88 to 12.21 g/cm3—as well as their chemically stable and cost-effective synthesis via traditional solid-state reaction. Utilizing the Geant4 Monte Carlo toolkit31,32, we simulated the linear attenuation coefficients (μ) and various shielding parameters (mean free path, radiation protection efficiency, and effective atomic number) across a wide energy spectrum of 0.015–15 MeV. The results are rigorously benchmarked against the XCOM database, Phy-X and PAGEX software33–35 and validated using the Kolmogorov–Smirnov test to establish TaAs as a highly compact and efficient solution for modern radiationenvironments. Finally, the scientific novelty of this work lies in investigating transition metal arsenides, a class of high-density materials largely unexplored for radiation protection. By establishing TaAs as a high-performance benchmark, this study provides the theoretical foundation required to shift from lead-based systems to more compact, high-Z alloy alternatives.
Materials and simulation framework
Three lead-free arsenide alloys (VAs, MoAs, and TaAs) were selected for this evaluation due to their optimal physicochemical profile, which combines chemical inertness, mechanical stability, and environmental safety with cost-effective fabrication. Critically, these alloys possess high densities of 6.88 g/cm³ (VAs), 8.72 g/cm³ (MoAs), and 12.21 g/cm³ (TaAs), a fundamental requirement for effective radiation shielding36–38. The modeled materials correspond to polycrystalline powders synthesized via a direct solid-state reaction route, following protocols established in prior literature39–41.
For the computational assessment, we employed the Geant4 Monte Carlo toolkit (a C + + based simulation framework) to model the transport and interaction of ionizing radiation within the target al.loys42. As a simulation toolkit, Geant4 requires users to possess a solid understanding of its structure and functionalities in order to effectively implement and customize its components. Users are expected to write their own code to tailor the simulations to specific applications. In this study, the Geant4 Monte Carlo toolkit was employed to simulate the linear attenuation coefficient (μ) of the selected alloys, based on the Beer–Lambert law43:
![]() |
1 |
Here,
denotes the intensity of the incident (primary) photon beam,
represents the intensity of the transmitted (attenuated) beam after passing through the material, and
corresponds to the thickness of the sample. Initially,
was obtained by simulating
primary photons in the absence of any shielding material. Subsequently, the transmitted intensity
was calculated after incorporating the simulated alloy samples into the geometry. In addition, Simulations were performed using G4EmLivermorePhysics physics list to accurately model low-energy electromagnetic interactions. Tracking was controlled with a 0.01 mm maximum step size and a 0.1 mm production cut for photons and electrons. Simple geometry has been used in this study. Figure 1 presents a schematic representation of the simulation geometry constructed using the Geant4 toolkit. The shielding sample, shown in pink, was modeled with a fixed thickness of 1 cm. A cylindrical sodium iodide (NaI) detector (yellow) with a radius of 7.5 cm and a length of 5 cm was placed at the left boundary of a cubic world volume measuring 50 × 50 × 50 cm3. A sensitive detector volume scored uncollided primary photons to ensure narrow-beam geometry compliance. Statistical convergence was monitored, with runtimes averaging 30 min per energy point to ensure δ < 0.1%. On the opposite side, a photon source (in blue) emitting photons of varying energies was positioned to direct a beam toward the detector. To ensure a well-collimated pencil beam, two lead (Pb) collimators were included in the setup: one with a 1 cm inner radius adjacent to the sample, and another encasing the detector (in gray).
Fig. 1.
a A collimated beam of photons (green) hits a shielding material (pink). The secondaries shown in red are negatively charged particles. b The simulation geometry employed in this study using the Geant4 Monte Carlo toolkit. The blue cylinder represents the photon emitter, gray cylinders correspond to lead collimators, the pink disk denotes the shielding material under investigation, and the yellow cylinder represents the NaI detector used for photon detection.
Statistical convergence was strictly monitored to ensure the reliability of the results. By simulating 106 primary photon histories per energy point, the relative statistical uncertainty (δ) for the transmitted flux was maintained at δ < 0.1%. The standard uncertainty σ(μ) for the linear attenuation coefficient (not shown) was calculated based on the propagation of these statistical fluctuations through the Beer-Lambert law:
![]() |
2 |
where I is the number of detected photons.
The results are benchmarked with the data obtained from XCOM database produced by National Institute of Standards and Technology, Gaithersburg, MD according to:
![]() |
3 |
From the simulated
, different important shielding parameters were calculated such as half-value layer (
), mean-free path (
), transmission factor (
), radiation protection efficiency (
), kinetic energy released in a material per unit mass KERMA (
relative to the air, the dose rate at a distance
from a source, and effective atomic number (
). These parameters can be calculated using the following equations:
![]() |
4 |
![]() |
5 |
![]() |
6 |
![]() |
7 |
![]() |
8 |
Here,
is the atomic mass,
is the number of atoms of the ith constituent element,
is the atomic number, and
is the mass density44.
![]() |
9 |
![]() |
10 |
Where
is the gamma constant,
is the activity of the source, and
is the distance from the source. More details of these parameters can be found in the literature45–49.
Results and discussion
Figure 2 shows the variation of the mass attenuation coefficient, or MAC, as a function of photon energy, on a log-log scale, for XAs samples with X = V, Mo, or Ta. The MAC values exhibit a clear three-region behavior, governing by the dominant photon interaction mechanism. In the low-energy range, below 0.1 MeV, the MAC values are significantly high for all investigated samples, as expected, due to the photo-electric effect (
), which dominates this region. It is worth mentioning that
is strongly dependent on the atomic number and explains why TaAs sample exhibits the highest MAC values, followed by MoAs and Vas. For example, at 0.015 MeV, the MAC records 74.776 cm²/g, 59.233 cm²/g, and 123.633 cm²/g for VAs, MoAs, and TaAs respectively. As energy increases, a steep decline is observed due to rapid drop in photo-electric cross-section. In the intermediate region, between up to 1 MeV, the MAC decreases more gradually as Compton scattering
becomes the dominant interaction mechanism. In this region, attenuation is primarily affected by electron density rather than atomic number, resulting in narrowing the difference between the samples. However, TaAs alloy still has a slight advantage due to its higher density and overall interaction probability. As photon energy increases, above 1.022 MeV, the MAC continues to decrease but tends to flatten due to the onset of pair-production (
) mechanisms. The hierarchy TaAs > MoAs > VAs arises from the Z-dependence of the photoelectric and pair-production cross-sections, combined with the higher mass density of TaAs, which increases the overall interaction probability. In the Compton region, differences narrow because electron density rather than Z dominates.
Fig. 2.

Mass attenuation coefficient (MAC) as a function of photon energy for VAs, MoAs, and TaAs alloys used in this study.
To quantify and validate these findings, Table 1 shows a detailed comparison of the linear attenuation coefficients (
) for all alloy samples in this study calculated using both the Geant4 MC toolkit and the XCOM photon cross-section database across the photon energy range of 0.015–15 MeV. Additionally, the percentage difference (
) between the two datasets is included to assess the accuracy of the Geant4 simulations. Across all alloy samples and energies, the
values show the expected energy dependence, high at low energies due to the dominance of
and gradually decreasing as photon energy increases due to the transition to
and, at higher energies,
. The percentage differences between Geant4 and XCOM are consistently low, typically well below 1% for MoAs and TaAs alloys, and remain within the acceptable uncertainty margin for VAs alloys where minor discrepancies appear at certain energy points, such as 0.06 MeV to 0.2 MeV, but even the largest deviation does not exceed approximately 3.8% which reflects strong overall agreement. These results confirm that the accuracy and power of the Geant4 MC toolkit in calculating
for different shielding materials. Moreover, the low
values across three distinct alloy systems reinforce the robustness and general applicability of the simulation approach.
Table 1.
Linear attenuation coefficient (µ) for VAs, MoAs, and TaAs alloys were evaluated using both Geant4 MC toolkit and XCOM database over a range of photon energies of 0.15 MeV to 15 MeV. The corresponding percentage differences (Δ%) between the two methods are also reported.
| Energy (MeV) | Linear attenuation coefficient μ (cm−1) | ||||||||
|---|---|---|---|---|---|---|---|---|---|
| VAs | MoAs | TaAs | |||||||
| XCOM | Geant4 | Δ% | XCOM | Geant4 | Δ% | XCOM | Geant4 | Δ% | |
| 0.015 | 514.4567 | 514.1333 | 0.0629 | 516.5125 | 516.5125 | 0.0000 | 1509.5614 | 1509.5614 | 0.0000 |
| 0.02 | 236.1539 | 235.2844 | 0.3682 | 564.0150 | 564.0150 | 0.0000 | 710.1344 | 710.1344 | 0.0000 |
| 0.03 | 77.1473 | 77.7474 | 0.7779 | 195.1373 | 195.1373 | 0.0000 | 242.6924 | 242.6924 | 0.0000 |
| 0.04 | 34.5727 | 34.9658 | 1.1369 | 89.2049 | 89.2049 | 0.0000 | 112.7202 | 112.7202 | 0.0000 |
| 0.05 | 18.6379 | 18.5114 | 0.6786 | 48.3662 | 48.3662 | 0.0000 | 62.3688 | 62.3688 | 0.0000 |
| 0.06 | 11.3732 | 11.0118 | 3.1780 | 29.3497 | 29.3497 | 0.0000 | 38.6926 | 38.6926 | 0.0000 |
| 0.08 | 5.4348 | 5.4386 | 0.0692 | 13.5457 | 13.5457 | 0.0000 | 69.1964 | 69.1964 | 0.0000 |
| 0.1 | 3.2465 | 3.2624 | 0.4883 | 7.6483 | 7.6483 | 0.0000 | 39.2684 | 39.2684 | 0.0000 |
| 0.15 | 1.5425 | 1.5666 | 1.5673 | 3.0633 | 3.0633 | 0.0001 | 14.1558 | 14.1558 | 0.0000 |
| 0.2 | 1.0708 | 1.0920 | 1.9735 | 1.8436 | 1.8436 | 0.0002 | 7.1760 | 7.1761 | 0.0000 |
| 0.3 | 0.7587 | 0.7553 | 0.4500 | 1.1147 | 1.1147 | 0.0003 | 3.1304 | 3.1304 | 0.0000 |
| 0.4 | 0.6352 | 0.6346 | 0.0986 | 0.8727 | 0.8727 | 0.0003 | 1.9605 | 1.9605 | 0.0002 |
| 0.5 | 0.5631 | 0.5616 | 0.2603 | 0.7490 | 0.7490 | 0.0006 | 1.4631 | 1.4631 | 0.0001 |
| 0.6 | 0.5129 | 0.5119 | 0.2000 | 0.6705 | 0.6705 | 0.0007 | 1.1968 | 1.1968 | 0.0003 |
| 0.8 | 0.4438 | 0.4461 | 0.5246 | 0.5703 | 0.5703 | 0.0008 | 0.9194 | 0.9194 | 0.0004 |
| 1 | 0.3962 | 0.4055 | 2.3301 | 0.5051 | 0.5051 | 0.0005 | 0.7720 | 0.7720 | 0.0003 |
| 1.5 | 0.3224 | 0.3259 | 1.0737 | 0.4090 | 0.4090 | 0.0002 | 0.5964 | 0.5964 | 0.0004 |
| 2 | 0.2822 | 0.2857 | 1.2453 | 0.3603 | 0.3603 | 0.0007 | 0.5274 | 0.5274 | 0.0001 |
| 3 | 0.2414 | 0.2473 | 2.4296 | 0.3152 | 0.3152 | 0.0005 | 0.4769 | 0.4769 | 0.0010 |
| 4 | 0.2225 | 0.2244 | 0.8590 | 0.2972 | 0.3172 | 6.7283 | 0.4648 | 0.4648 | 0.0009 |
| 5 | 0.2129 | 0.2113 | 0.7768 | 0.2903 | 0.2903 | 0.0000 | 0.4664 | 0.4664 | 0.0005 |
| 6 | 0.2081 | 0.2003 | 3.7825 | 0.2885 | 0.2885 | 0.0004 | 0.4739 | 0.4739 | 0.0001 |
| 8 | 0.2057 | 0.2123 | 3.2057 | 0.2928 | 0.2928 | 0.0003 | 0.4964 | 0.4964 | 0.0004 |
| 10 | 0.2076 | 0.2063 | 0.6211 | 0.3013 | 0.3013 | 0.0002 | 0.5219 | 0.5219 | 0.0007 |
| 15 | 0.2170 | 0.2172 | 0.0759 | 0.3250 | 0.3250 | 0.0009 | 0.5837 | 0.5837 | 0.00074 |
Figure 3 shows a graphical representation of the data in Table 1,
versus photon energy, for the three lead-free alloys studied in this work as obtained via Geant4 simulations compared to XCOM theoretical values to capture the key photon interaction with alloy samples. Across the entire spectrum, TaAs displays the highest
values, followed by MoAs and then VAs. For example, at 0.05 MeV, Geant4 yields
18.5 cm− 1, 48.4 cm− 1, and 62.4 cm− 1 for VAs, MoAs, and TaAs alloys respectively. In the intermediate energy region, 0.5 MeV for instance, the
values drop significantly across all alloy samples to 0.56 cm− 1, 0.75 cm− 1, and 1.46 cm− 1 for VAs, MoAs, and TaAs respectively. This region is dominated by
as mentioned elsewhere. As higher energies, for example 5 MeV,
values further decline, with Geant4 giving 0.21 cm− 1, 0.29 cm− 1, and 0.47 cm− 1 for VAs, MoAs, and TaAs respectively, preserving the trend of TaAs > MoAs > VAs. More importantly, the good agreement between the simulated
via Geant4 MC toolkit and the theoretical data obtained from XCOM standard database confirms the high reliability of the Geant4 model in simulating photon attenuation behavior predicted by standard theoretical databases.
Fig. 3.
Linear attenuation coefficients (μ) versus photon energy for a VAs, b MoAs, and c TaAs, calculated using Geant4 and benchmarked against XCOM values. The strong agreement supports simulation reliability.
Following the close numerical and graphical agreement between the data simulated using Geant4 and the theoretical data from XCOM database for VAs, MoAs, and TaAs alloy samples, a statistical evaluation was conducted to further validate the consistency between the two datasets. Figure 4 shows the cumulative distribution functions (
of
and applies the Kolmogorov-Smirnov (
test to quantitatively assess their distributional similarity along with the maximum deviation
and the associated
reported in each subplot. Starting with VAs alloy, the
test yield a
of 0.0761 and a
of 1.00, indicating no statistically significant difference between the obtained
from both Geant4 and XCOM. Similarly, MoAs and TaAs show
values of 0.04 and 0.10, respectively, both with
of 1.00. These
far exceed the typical threshold of 0.05, confirming strong statistical agreement between the two datasets for all alloys investigated in this study50–52. In addition, the nearly overlapping CDF curves visually reinforce this conclusion. The result further confirms Geant4 MC toolkit ability to simulate the ionizing radiation shielding properties with high statistical fidelity for dense, high-Z alloys.
Fig. 4.
Cumulative distribution functions (CDFs) of μ values obtained from Geant4 and XCOM for a VAs, b MoAs, and c TaAs. K–S test results confirm statistical consistency with p = 1.00 for all samples.
To better understand which interaction mechanism dominates at each energy region and how the material composition affects the interaction regime, Fig. 5 shows the percentage contribution of
to the total
as a function of photon energy for VAs, MoAs, and TaAs alloy samples. At low photon energies, below 0.1 MeV, the contribution from
is minimal, below 10% for all alloys, due to the overwhelming dominance of the
. In this regime, the
is heavily affected by the presence of high-Z elements, explaining the low relative contribution from Compton interactions. As energy increases into the intermediate range,
becomes the dominant interaction mechanism, with its contribution peaking (100%) near 1 MeV. Beyond 2 MeV, the Compton fraction declines as pair production mechanisms become significant, a trend most pronounced in the high-Z TaAs alloy. This behavior reinforces the established interaction hierarchy:
governs shielding in the low-energy regime (favoring high-Z materials), whereas
dominates attenuation across the intermediate energy range. Consequently, optimal material selection is strictly dependent on the incident radiation spectrum. To rigorously quantify the shielding efficiency of these alloys, we evaluated several key performance parameters.
Fig. 5.

Fractional contribution of Compton scattering to the total μ as a function of photon energy for VAs, MoAs, and TaAs, indicating interaction regime transitions.
Across the entire energy range, the total uncertainty in Geant4-derived µ does not exceed ~ 0.1%, in line with typical electromagnetic simulation studies.
Figure 6 presents the energy-dependent variation of two critical shielding parameters, (a) half-value layer (
) and (b) mean-free path (
) for the VAs, MoAs, and TaAs alloys. These parameters provide practical insight into the thickness requirements of shielding materials for effective gamma attenuation. Consistent with fundamental theory, both
and
exhibit a positive correlation with photon energy across all samples. This trend stems directly from the inverse relationship between incident energy and
, necessitating thicker material layers to compensate for the reduced interaction probability at higher energy levels. The lowest
and
values are observed at low energies where the photoelectric effect dominates, while the highest values occur at high energies where pair production begins to emerge, but attenuation is less efficient. At all energy levels, TaAs alloy displays the lowest
and
values, followed by MoAs and then VAs. For instance, at 0.5 MeV, the
values are approximately 0.47 cm, 0.92 cm, and 1.23 cm, for TaAs, MoAs, and VAs, respectively, corresponding to their respective
values. This hierarchy remains consistent across the spectrum and emphasizes the superior shielding efficiency of TaAs due to its higher mass density and atomic number.
Fig. 6.
a Half-value layer and b mean free path as functions of photon energy for VAs, MoAs, and TaAs alloys.
Table 2 provides a comparative assessment of
,
, and
at 0.5 MeV for the investigated arsenide alloys in this work alongside selected reference shielding materials, including Cr-based alloys, steel-based composites, and ordinary concrete. Among all listed materials, TaAs demonstrates the highest
of 1.463 cm− 1, outperforming even CrBi of
1.275 cm− 1, which is the most effective among the literature-reported Cr alloys in this table. Consequently, TaAs also exhibits the lowest
of 0.474 cm and
of 0.684 cm values, indicating the most compact and efficient shielding configuration among all compared materials. In contrast, VAs has a lower
of 0.563 cm− 1, corresponding to
and
values of 1.231 cm and 1.776 cm, respectively, but still superior to common materials such as steel-scrap of
0.266 cm− 1 and ordinary concrete of
0.340 cm− 1, which require significantly more thickness to achieve equivalent attenuation. MoAs, with intermediate performance of
0.749 cm− 1,
0.925 cm, and
1.335 cm, outperforms all steel-based and concrete references and even CrP and CrAs, making it a compelling candidate for mid-range shielding applications. Overall, the results highlight that the arsenide alloys investigated in this study, particularly TaAs, possess superior photon attenuation characteristics compared to several traditional and advanced shielding materials. The superiority of TaAs follows directly from enhanced photoelectric absorption at low energies due to its high Z constituents, sustained attenuation in the Compton region from higher electron density, and stronger pair-production probability above ~ 1.5 MeV. These mechanisms collectively explain the persistent ranking TaAs > MoAs > VAs across all energies.
Table 2.
Linear attenuation coefficent of arsenide-based alloys used in this study with those of conventional shielding materials and another alloys at a photon energy of 0.5 MeV.
Figure 7 maps the Air KERMA response across the photon energy spectrum. We observe a distinct two-phase behavior: a rapid exponential decay in the low-energy region that transitions into a stabilized decline at higher energies. Crucially, in the sub-0.1 MeV regime, TaAs outperforms the other alloys, generating the highest KERMA values. This dominance is not coincidental; it stems directly from the high density of the TaAs matrix, which amplifies photon interaction rates and forces a larger ejection of kinetic energy-carrying secondary particles into the adjacent air.As incident energy climbs toward 3 MeV, these material distinctions blur. The curves begin to converge, signaling the physical shift toward Compton scattering regime where interaction probability is largely indifferent to atomic number (Z). By the time we reach the upper energy limits, the profiles nearly overlap. At this stage, the shrinking interaction cross-sections become the limiting factor, restricting the efficiency of energy deposition in air regardless of the shielding medium’s density.
Fig. 7.

KERMA (kinetic energy released per unit mass) in air as a function of photon energy for VAs, MoAs, and TaAs, showing energy transfer behavior from photons to air across all alloys investigated in this work.
Figure 8 shows another important shielding parameter, effective atomic number (
) versus incident photon energy for VAs, MoAs, and TaAs alloy samples over the range of 0.01–15 MeV. At low photon energy levels, below 0.1 MeV, the
values are at their highest, as
is dominates. Here, TaAs shows the highest
followed by MoAs and VAs respectively, reflecting the actual atomic number hierarchy of their constituent element (Ta > Mo > V). This ordering directly correlates with the superior attenuation observed in TaAs in previous figures and tables. As photon energy increases into
region,
values gradually converge, indicating reduced sensitivity to atomic numbers.
is primarily influenced by electron density rather than Z, which explains the flattening of
curves and the reduced gap between materials in this range. Beyond 3 MeV to 5 MeV,
stabilizes, and in some cases, shows slight fluctuations due to the onset of
, which again has a modest Z-dependence. However, the differences between the alloys remain consistent, with TaAs maintaining the highest
throughout the spectrum. The high KERMA values at low energies reflect enhanced absorption via the photoelectric effect in high-Z TaAs, whereas the convergence at higher energies follows from the Z-independent nature of Compton scattering.
Fig. 8.
Effective atomic number versus photon energy for VAs, MoAs, and TaAs, illustrating Z-sensitivity at low energies and convergence under Compton-dominant conditions.
Figure 9 shows (a) the exposure buildup factor (EBF) and (b) the absorption buildup factor (EABF) as a function of photon energy across different selected penetration depths for VAs alloy samples. It is observed that EBF increases with both energy and penetration depth (mean-free path). In the low energy region, below 0.1 MeV, the EBF remains low for all depths due to the dominance of
and minimal photon scattering. However, at intermediate energies, up to 1.5 MeV, the EBF rises sharply to peak near 1 MeV, a region where
is the dominant interaction mechanism. To illustrate, at 1 MeV, the EBF escalates from ~ 3 at 1 mfp to over 104 at 40 mfp, indicating a substantial accumulation of secondary photons within deep shielding layers. A parallel trend is observed for EABF in Fig. 9b, which scales positively with both incident energy and penetration depth. These results confirm that as optical thickness increases, scattering effects progressively govern the radiation field, resulting in elevated buildup factors that are critical for determining the safety margins of thick shielding configurations. The increase in EBF and EABF with energy and depth results from the higher probability of multiple Compton scatterings, which generate additional secondary photons within thicker shielding layers.
Fig. 9.
a Exposure buildup factor (EBF), b absorption buildup factor (EABF) for VAs alloy versus photon energy for VAs at different penetration depths (1–40 mfp).
Figure 10 shows the specific absorbed fraction of energy (SAFE) versus photon energy for VAs at different penetration depths (1–40 mfp). The idea from this parameter is to quantify the fraction of energy absorbed in the target region per unit incident energy. As expected, SAFE decreases with energy in the Compton-dominant region due to reduced efficiency but increases again slightly at higher energies as
begins to contribute. SAFE also increases significantly with depth indicating enhanced energy deposition as the photon flux traverses deeper material. SAFE reflects how efficiently a material absorbs incident photon energy, meaning higher SAFE at greater depths corresponds to stronger energy deposition inside the shield. In contrast, increasing buildup factors indicate enhanced secondary-photon generation, which must be considered when designing thick shielding components.
Fig. 10.

specific absorbed fraction of energy (SAFE) versus photon energy for VAs at different penetration depths (1–40 mfp) for VAs sample.
Figure 11 displays the specific gamma-ray constant (Γ), expressed in R.m2/(Ci.hr), as a function of photon energy for VAs, MoAs, and TaAs, with an inset focusing on the lower energy region to highlight the effect of density on Γ behavior. Across the full energy spectrum, Γ exhibits a sharp inverse relationship with photon energy for all three alloys. This trend arises because higher-energy photons possess greater penetrability, thereby reducing the dose delivered per unit activity at a fixed distance. In the low-energy region, below 0.1 MeV, Γ values are elevated due to intense photon absorption and localized energy deposition. At 0.05 MeV, for example, TaAs shows a Γ value of ~ 1000 R.m2/(Ci.hr), compared to near 680 for MoAs and near 530 for VAs, marking a near 89% increase from VAs to TaAs. In the intermediate-energy region below 3 MeV, where
dominates, the decline in Γ becomes more gradual. At 0.5 MeV, TaAs retains a higher exposure potential of about 60 R.m2/(Ci.hr) compared to ~ 50 for MoAs and ~ 40 for VAs. However, as energy exceeds 5 MeV, the curves converge; at 10 MeV, the difference becomes marginal (~ 30 for TaAs, ~ 28 for MoAs, and ~ 26 for VAs). As highlighted in the inset, the Γ value at low energy is strongly governed by the material density, with TaAs of
12.21 g/cm3, maintaining a consistently higher exposure constant than its lighter counterparts.
Fig. 11.

Specific gamma-ray constant as a function of photon energy for VAs, MoAs, and TaAs. The inset highlights the density-dependent variation of
in the low-energy region.
Figure 12 shows the photon dose rate in air as a function of distance from monoenergetic gamma source shielded by VAs, MoAs, or TaAs alloys. The data reflects the expected decay in dose intensity, governed jointly by the inverse square law and the material-specific exponential attenuation. At the most critical shielding interface (0.1 cm), TaAs achieve the lowest dose rate, reducing exposure by over 50% relative to VAs. This superior performance is directly attributable to the high atomic number (Z) and density of the TaAs matrix. MoAs occupies an intermediate position, offering moderate dose reduction. This hierarchy persists at extended distances (0.5 cm and 1 cm); even at 5 cm, TaAs yields the lowest residual dose. These results underscore that intrinsic material properties remain the dominant factor in limiting exposure, particularly in compact shielding scenarios where maximizing attenuation within a constrained volume is essential. Overall, the bar graph confirms that TaAs provides the most effective near-field dose suppression due to its superior photon attenuation properties. These results validate TaAs as the optimal material among the studied alloys for high-intensity gamma radiation environments requiring compact and efficient shielding, while MoAs offers a suitable compromise between attenuation and material density.
Fig. 12.
Bar graph of photon dose rate in air at different selected distances from a gamma source shielded by VAs, MoAs, or TaAs.
Conclusion
This study rigorously evaluated the radiation shielding efficacy of three transition metal arsenide alloys (VAs, MoAs, and TaAs) using the Geant4 Monte Carlo toolkit. Our findings establish TaAs as the superior candidate for high-intensity photon attenuation. At 0.5 MeV, TaAs exhibited a linear attenuation coefficient of
, representing about 160% improvement over VAs and significantly outperforming traditional shielding materials such as ordinary concrete and steel-based composites. Furthermore, TaAs demonstrated the lowest half-value layer
, enabling a dose rate reduction of over 50% compared to VAs at a thickness of 0.1 cm. The strong statistical agreement with XCOM (
) confirms the reliability of these results. These findings do not merely replicate known data but advance the field by identifying transition metal arsenides as a high-performance class of materials previously overlooked in shielding literature. Ultimately, this study serves as a predictive roadmap for future experimental synthesis, establishing TaAs as a robust and compact lead-free solution for modern diagnostic and industrial applications where space constraints and sustainability are paramount.
Acknowledgements
The author would like to thank Dr. Murad Yaghi from the department of data science and AI, school of computing and informatics, Al Hussein Technical University, for his technical help and support in creating and using the Geant4 MC code and in the analysis of the simulated data.
Author contributions
Morad Khalid Hamad : Conceptualization, Data curation, Formal analysis, acquisition, Investigation, Methodology, Project administration, Resources, Software, Supervision, Validation, Visualization, Writing – original draft, Writing – review & editing.
Funding
Not applicable.
Data availability
All data related to this article are available from the corresponding author upon reasonable request.
Declarations
Competing interests
The author declares that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.
Declaration of using AI tool
During the preparation of this work, the author(s) used an AI tool in order to improve language and readability. After using this tool/service, the author reviewed and edited the content as needed and takes full responsibility for the content of the publication.
Footnotes
Publisher’s note
Springer Nature remains neutral with regard to jurisdictional claims in published maps and institutional affiliations.
References
- 1.Flora, G., Gupta, D. & Tiwari, A. Toxicity of lead: a review with recent updates. Interdiscip. Toxicol.5 (2), 47–58. 10.2478/v10102-012-0009-2 (2012). [DOI] [PMC free article] [PubMed] [Google Scholar]
- 2.Lee, C., Lee, Y. H. & Lee, K. J. Cracking effect on gamma-ray shielding performance in concrete structure. Prog. Nucl. Energy. 49 (4), 303–312. 10.1016/j.pnucene.2007.01.006 (2007). [Google Scholar]
- 3.Singh, K., Singh, N., Kaundal, R. & Singh, K. Gamma-ray shielding and structural properties of PbO–SiO2 glasses. Nucl. Instrum. Methods Phys. Res. Sect. B266 (6), 944–948. 10.1016/j.nimb.2008.02.004 (2008). [Google Scholar]
- 4.Mhareb, M. Optical, Structural, radiation shielding, and mechanical properties for borosilicate glass and glass ceramics doped with Gd2O3. Ceram. Int.49 (22), 36950–36961. 10.1016/j.ceramint.2023.09.026 (2023). [Google Scholar]
- 5.Alqahtani, M. Y. et al. Structural, morphology, and radiation shielding properties of Mg2FeTiO6 ceramic modified with different concentrations of ZnO. J. Mater. Sci. Mater. Electron.33, 18829–18845. 10.1007/s10854-022-08732-6 (2022). [Google Scholar]
- 6.Mhareb, M. et al. Structural and radiation shielding properties of BaTiO3 ceramic with different concentrations of Bismuth and Ytterbium. Ceram. Int.46 (18), 28877–28886. 10.1016/j.ceramint.2020.08.055 (2020). [Google Scholar]
- 7.Hamisu, A. et al. The use of nanomaterial polymeric materials as ionizing radiation shields. Radiat. Phys. Chem.216, 111448. 10.1016/j.radphyschem.2023.111448 (2024). [Google Scholar]
- 8.Zailan, F. D. et al. Improved mechanical, magnetic and radiation shielding performance of rubbery polymer magnetic nanocomposites through incorporation of Fe3O4 nanoparticles. Compos. Part A Appl. Sci. Manufac.186, 108385. 10.1016/j.compositesa.2024.108385 (2024). [Google Scholar]
- 9.Trukhanov, A. et al. Evolution of the structural parameters and magnetic characteristics in ferrite/polymer nanocomposites. J. Alloys Compd.986, 174048. 10.1016/j.jallcom.2024.174048 (2024). [Google Scholar]
- 10. Setiawan, V., Veeravelan, K., Akouibaa, A., & Heryanto, H. Comparative half-value layer study of novel PbO-B2O3-CuO-CaO glasses versus previous reports. Nexus Future Mater.1, 126–130. 10.70128/585024 (2024). [Google Scholar]
- 11.Biradar, S., Dinkar, A. & Devidas, G. B. A comprehensive study of the effect of BaO doping on the physical, mechanical, optical, and radiation shielding properties of borate-based glasses. Nexus Future Mater.1, 108–119. 10.70128/584259 (2024). [Google Scholar]
- 12.Alajerami, Y. S. M. et al. Structural, optical, and radiation shielding features for a series of borate glassy system modified by molybdenum oxide. Eur. Phys. J. Plus. 136, 583. 10.1140/epjp/s13360-021-01582-x (2021). [Google Scholar]
- 13.Maghrbi, Y., Chouchen, M. & Rahmouni, H. B. Exploring transmission factor in high-density glasses: the effects of ZnO and Bi2O3 concentrations. Nexus Future Mater.1, 120–125. 10.70128/585023 (2024). [Google Scholar]
- 14.Zehra Merve Cinan. Innovative phosphate glasses of advanced material designs for radiation shielding. Nexus Future Mater.1, 92–101.10.70128/584052 (2024). [Google Scholar]
- 15.Ahmed, E. K., Mahran, H. M., Alrashdi, M. F. & Elsafi, M. Studying the shielding ability of different cement mortars against gamma ray sources using waste iron and BaO microparticles. Nexus Future Mater.1, 1–5. 10.70128/583327 (2024). [Google Scholar]
- 16.Yasmin, S., Saifuddin, M., Chakraborty, S. R., Meaze, A. H. & Barua, B. S. Evaluation of TeO2-WO3-Bi2O3 glasses for their potential in radiation shielding with the utilization of the Phy-X software program. Nexus Future Mater.1, 51–55. 10.70128/584048 (2024). [Google Scholar]
- 17.Sayyed, M. et al. Effects of MoO3 on the structural, physical, mechanical, optical, and ionizing shielding of borate-germanate-telluride glass system. Ceram. Int.50 (22), 46008–46017. 10.1016/j.ceramint.2024.08.442 (2024). [Google Scholar]
- 18.Hamad, M. K. Effect of WO3 on structural, optical, mechanical, and ionizing radiation shielding properties of borate-tellurite glass network. Ceram. Int.51 (8), 9763–9771. 10.1016/j.ceramint.2024.12.407 (2025). [Google Scholar]
- 19.Hamad, M. K. Enhancing ionizing radiation shielding properties with PbO and ZnO substitutions in B2O3–BaO–TiO2 novel glass system. Radiat. Phys. Chem.229, 112499. 10.1016/j.radphyschem.2024.112499 (2025). [Google Scholar]
- 20.Ruiz, E. L. Radiation shielding analysis of barium-titanium-borate glasses doped with zinc oxide. Nexus Future Mater.1, 80–85. 10.70128/584050 (2024). [Google Scholar]
- 21.Gaikwad, K. B., Algethami, M., More, C. V., Sayyed, M. & Pawar, P. P. Enhanced radiation shielding properties of advanced ceramic materials. J. Alloys Compd.1033, 181384. 10.1016/j.jallcom.2025.181384 (2025). [Google Scholar]
- 22.Hamad, M. K. et al. Assessing the efficiency of lead-free XCr2Te4 chalcogenide spinels alloys in ionizing radiation attenuation: a study with MCNP-code. Radiat. Phys. Chem.219, 111652. 10.1016/j.radphyschem.2024.111652 (2024). [Google Scholar]
- 23.Darwish, M. A., Hussein, M. M., Saafan, S. A., Abd-Elaziem, W., Zhou, D., Silibin, M. V., Trukhanov, S. V., Abmiotka, N. V., Sayyed, M., Tishkevich, D. I., & Trukhanov, A. V. Impact of the Mg/Zn ratio on features of structural and magnetic properties in A-site stoichiometric nanosized spinel ferrites. J. Alloys Compd.968, 172278. 10.1016/j.jallcom.2023.172278 (2023). [Google Scholar]
- 24.Hamad, M. K. On the ionizing radiation protection properties of different chromium-based alloys: a study with the Geant4 Monte Carlo toolkit. Ann. Nucl. Energy. 213, 111134. 10.1016/j.anucene.2024.111134 (2025). [Google Scholar]
- 25.Sayyed, M., Mahmoud, K., Mohammed, F. Q. & Kaky, K. M. A comprehensive evaluation of Mg-Ni based alloys radiation shielding features for nuclear protection applications. Nucl. Eng. Technol.56 (5), 1830–1835. 10.1016/j.net.2023.12.040 (2024). [Google Scholar]
- 26.Farrag, E. A., Hamad, M. K., Ali, A., Abdelmonem, A. & Al-Taani, H. Unveiling the shielding potential: exploring photon and neutron attenuation in a novel lead-free XCr2Se4 chalcogenide spinals alloys with MCNP 4 C code. Radiat. Phys. Chem.226, 112337. 10.1016/j.radphyschem.2024.112337 (2024). [Google Scholar]
- 27.Tishkevich, D. I. et al. Heavy alloy based on tungsten and bismuth: fabrication, crystal structure, morphology, and shielding efficiency against gamma-radiation. RSC Adv.13 (35), 24491–24498. 10.1039/d3ra04509a (2023). [DOI] [PMC free article] [PubMed] [Google Scholar]
- 28.Manjunatha, Biradar, S. et al. Experimental investigation on the role of Bi³⁺ composition in structural, elastic, and radiation shielding properties of multifunctional cobalt-nickel nanoferrites. J. Alloys Compd.1033, 181255. 10.1016/j.jallcom.2025.181255 (2025). [Google Scholar]
- 29.Saleh, A., El-Feky, M., Hafiz, M. & Kawady, N. Experimental and theoretical investigation on physical, structure and protection features of TeO2–B2O3 glass doped with PbO in terms of gamma, neutron, proton and alpha particles. Radiat. Phys. Chem.202, 110586. 10.1016/j.radphyschem.2022.110586 (2022). [Google Scholar]
- 30.Sayyed, M., Mahmoud, K., Mohammed, F. Q., & Kaky, K. M. Comprehensive study on structure, mechanical and nuclear shielding properties of lead free Sn–Zn–Bi alloys as a powerful radiation and neutron shielding material. Radiat. Phys. Chem.56(5), 1830-1835. 10.1016/j.net.2023.12.040 (2022). [Google Scholar]
- 31.Agostinelli, S. et al. Geant4—a simulation toolkit. Nucl. Instrum. Methods Phys. Res. Sect. A Accel. Spectrom. Detect. Assoc. Equip.506 (3), 250–303 (2003). 10.1016/S0168-9002(03)01368-8
- 32.Rodrigues, P. et al. Application of GEANT4 radiation transport toolkit to dose calculations in anthropomorphic phantoms. Appl. Radiat. Isot.61 (6), 1451–1461. 10.1016/j.apradiso.2004.05.073 (2004). [DOI] [PubMed] [Google Scholar]
- 33.Berger, M. J. et al. XCOM: photon cross sections database. NBSIR 87-3597. (2010). 10.18434/T48G6X
- 34.Şakar, E., Özpolat, Ö. F., Alım, B., Sayyed, M. & Kurudirek, M. Phy-X/PSD: development of a user friendly online software for calculation of parameters relevant to radiation shielding and dosimetry. Radiat. Phys. Chem.166, 108496. 10.1016/j.radphyschem.2019.108496 (2019). [Google Scholar]
- 35.Prabhu, S., Jayaram, S., Bubbly, S. & Gudennavar, S. A simple software for swift computation of photon and charged particle interaction parameters: PAGEX. Appl. Radiat. Isot.176, 109903. 10.1016/j.apradiso.2021.109903 (2021). [DOI] [PubMed] [Google Scholar]
- 36.Data retrieved from the Materials Project for VAs. (mp-19940) from database version v2025.04.10. 10.17188/1195125
- 37.Data retrieved from the Materials Project for MoAs. (mp-9998) from database version v2025.04.10. 10.17188/1317616
- 38.Data retrieved from the Materials Project for TaAs. (mp-1936) from database version v2025.04.10. 10.17188/1194366
- 39.Curley, J. J., Piro, N. A. & Cummins, C. C. A terminal molybdenum arsenide complex synthesized from yellow arsenic. Inorg. Chem.48 (20), 9599–9601. 10.1021/ic9016068 (2009). [DOI] [PubMed] [Google Scholar]
- 40.Li, Z. et al. Weyl semimetal TAAS: crystal growth, morphology, and thermodynamics. Cryst. Growth. Des.16 (3), 1172–1175. 10.1021/acs.cgd.5b01758 (2016). [Google Scholar]
- 41.Smith, J. F. The As-V (Arsenic-Vanadium) system. J. Phase Equilib.12 (4), 428–431. 10.1007/bf02645961 (1991). [Google Scholar]
- 42.Allison, J. et al. Recent developments in Geant4. Nucl. Instrum. Methods Phys. Res. Sect. A Accel. Spectrom. Detect. Assoc. Equip.835, 186–225. (2016). 10.1016/j.nima.2016.06.125
- 43.Swinehart, D. F. The Beer-Lambert Law. J. Chem. Educ.39 (7), 333. 10.1021/ed039p333 (1962). [Google Scholar]
- 44.Manohara, S., Hanagodimath, S., Thind, K. & Gerward, L. On the effective atomic number and electron density: A comprehensive set of formulas for all types of materials and energies above 1 keV. Nucl. Instrum. Methods Phys. Res. Sect. B. 266 (18), 3906–3912. 10.1016/j.nimb.2008.06.034 (2008). [Google Scholar]
- 45.Sayyed, M. et al. Developing G-T-B glass system doped holmium oxide for radiation absorption and optical applications. J. Sci. Adv. Mater. Devices. 10 (2), 100872. 10.1016/j.jsamd.2025.100872 (2025). [Google Scholar]
- 46.Mahdi, R. I. et al. Engineered composition and morphology: Unveiling 2D Bi₂(W₁₋ₓMox)O₆ nanosheets for enhanced optical and ionizing protection applications. Mater. Today Commun.45, 112415. 10.1016/j.mtcomm.2025.112415 (2025). [Google Scholar]
- 47.Mhareb, M. et al. Novel hafnium oxide doped G-T-B Glass: Structural, physical, mechanical, optical, and radiation shielding investigation. Results Phys.70, 108161. 10.1016/j.rinp.2025.108161 (2025). [Google Scholar]
- 48.Al-Ghamdi, H. et al. Impact of TiO2-doped bismuth-boro-tellurite glasses: fabrication, physical and optical properties, and γ-ray protection competence for optical and radiation shielding applications. J. Electron. Mater.54, 1432–1443. 10.1007/s11664-024-11616-6 (2025). [Google Scholar]
- 49.Kaky, K. M., Altimari, U. & Kadhim, A. J. Analytical and comparative study on the impact of CAO on the Γ-Ray shielding performance of Borate-Based glasses. Nexus Future Mater.210.70128/592452 (2025).
- 50.Hamad, M. K. Bragg-curve simulation of carbon-ion beams for particle-therapy applications: a study with the GEANT4 toolkit. Nucl. Eng. Technol.53 (8), 2767–2773. 10.1016/j.net.2021.02.011 (2021). [Google Scholar]
- 51.Kolmogorov–Smirnov test. In Springer eBooks (pp. 283–287). (2008). 10.1007/978-0-387-32833-1_214
- 52.Massey, F. J. The Kolmogorov–Smirnov test for goodness of fit. J. Am. Stat. Assoc.46 (253), 68. 10.2307/2280095 (1951). [Google Scholar]
- 53.Bashter, I. Calculation of radiation attenuation coefficients for shielding concretes. Ann. Nucl. Energy. 24 (17), 1389–1401. 10.1016/S0306-4549(97)00003-0 (1997). [Google Scholar]
Associated Data
This section collects any data citations, data availability statements, or supplementary materials included in this article.
Data Availability Statement
All data related to this article are available from the corresponding author upon reasonable request.

















