1. Introduction
Neutron technologies have been fast developed and widely utilized in different applications, including neutron imaging for material characterization and medical diagnostics [
1,
2,
3], boron neutron capture therapy (BNCT) for cancer therapy [
4], neutron moisture gauge for soil water measurement [
5], and gemstone irradiation for color modification [
6]. Although the mentioned benefits have substantially raised our overall quality of life, possibly excessive exposure to both chronic and acute neutron radiations could harmfully affect the health of users and the general public that may lead to severe diseases or death [
7].
To reduce and/or limit the risks of excessive neutron exposure, appropriate and sufficient neutron-shielding equipment must be strictly utilized and applied in all nuclear facilities, as one of the three protective measures in radiation safety [
8]. In principle, hydrogen-rich materials, such as natural rubber (NR), polyethylene (PE), concrete, and paraffin [
9,
10,
11], are suitable and commonly used in neutron protection, as incident neutrons could scatter off hydrogen atoms and lose a relatively large portion of their initial kinetic energies, as shown in Equation (1):
where
Ek,
M,
mn, and β are the kinetic energy losses of the neutron after the scattering, the recoil nucleus mass, the neutron mass, and the recoil angle of the nucleus, respectively. However, despite their acceptable attenuation abilities, it is still possible to further enhance the shielding abilities of the materials by introducing elements or compounds consisting of high-neutron-absorption cross-section isotopes, such as pure boron (B), B
2O
3, and B
4C to the materials [
9,
10], by which the neutrons would be more efficiently absorbed and attenuated compared to those relying solely on neutron scattering, resulting in less materials required and potentially superior mechanical strength.
Recently, materials containing rare-earth oxides, especially Sm
2O
3, have gained great attention from researchers and product developers to replace typical boron compounds with samarium (Sm) that has an almost 8-fold higher neutron absorption cross-section (σ
abs) than that of B (σ
abs of Sm and B are 5922 and 767 barns, respectively) [
12], resulting in superior neutron-shielding capabilities compared to common borated materials at the same filler content. Furthermore, Sm and Sm
2O
3 have relatively higher atomic number (Z) and high density (
ρ) (Z = 62 and
ρ = 8.35 g/cm
3, respectively) than B and B-containing compounds, making the former suitable for self-attenuation of gamma rays emitted after the neutrons have been absorbed by the Sm. This dual-shielding property of Sm
2O
3 for both neutrons and gamma rays has resulted in a simpler material design and remarkable shielding performance, which are crucially useful and important for workers in proximity to nuclear facilities with a photon-neutron-mixed environment [
13]. Examples of Sm
2O
3-containing materials used in neutron protection are Sm
2O
3/UHMWPE composites [
14], Sm
2O
3/Portland cement pastes [
15], xPbO-(99-x)B
2O
3-Sm
2O
3 glass system [
16], and carbon-fiber reinforced Sm
2O
3/polyimide composites [
17], for which their neutron-shielding properties were found to be considerably higher than for borated materials, determined at the same filler content.
Among the mentioned examples, Sm
2O
3/UHMWPE composites are one of the most promising materials as they offer not only hydrogen-rich properties but also other preferable properties, such as exhibiting high impact and tensile strengths, excellent abrasion resistance, and a low frictional coefficient, making them suitable for use as fuel storage, casks for neutron transportation, movable partitions, and extruded profiles in nuclear facilities [
18]. Recently, our previous work investigated the potential of applying Sm
2O
3/UHMWPE composites as neutron-shielding materials by determining their shielding, mechanical, electrical, and physical properties. The main results revealed that the addition of Sm
2O
3 in UHMWPE composites noticeably enhanced abilities to attenuate neutrons, as the values of the half-value layer (HVL) decreased from 248.0 mm in a neat UHMWPE to just 3.1 mm in samples with 50 wt.% Sm
2O
3 [
14]. This enhanced the neutron-shielding properties of the Sm
2O
3/UHMWPE composites and substantially reduced the required material’s thickness and the costs associated with manufacturing, construction, and transportation of the shielding materials.
Nonetheless, although adding higher Sm
2O
3 contents to UHWMPE composites typically resulted in higher overall shielding properties, the poor surface compatibility between Sm
2O
3 and UHMWPE, as well as agglomerations of Sm
2O
3 particles, led to possible voids and non-uniform filler distribution in the matrix, resulting in reduced overall mechanical properties. These undesirable effects were evidenced by the decreases in tensile strength and elongation at break from 25.9 MPa and 1058% in a neat UHMWPE to 20.0 MPa and 117% in the samples containing 50 wt.% Sm
2O
3, respectively [
14]. Furthermore, another report by Cao et al. indicated similar effects from having high Sm
2O
3 contents in UHMWPE composites, as the tensile strength and surface hardness (Shore D) decreased from ~22.8 MPa and ~84, respectively, in a neat UHWMPE sample to ~17.0 MPa and ~76, respectively, in a sample with 50 wt.% Sm
2O
3 [
19]. This reduced the mechanical properties of the Sm
2O
3/UHMWPE composites and subsequently limited the durability and usability of the materials in actual applications.
To improve the surface compatibility, filler distribution, and wear/mechanical properties of the composites, a silane coupling agent could be used to treat surfaces of the filler, prior to further processes. The benefits of applying a silane coupling agent were emphasized in the report by Zhao et al., which showed that the surface treatment of nano-TiO
2 with 3-aminopropyltrimethoxysilane and 3-isocyanatopropyltrimethoxysilane by an aqueous process led to a significant reduction in particle hydrodynamic diameters and the polydispersity index, which enhanced the particle dispersion stability of the nano-TiO
2 during sample preparation [
20]. In addition, Arslan and Dogan investigated the effects of three different silane coupling agents, namely (3-aminopropyl) triethoxysilane, (3-glycidyloxypropyl) trimethoxysilane, and (3-trimethoxysilyl) propylmethacrylate, on the mechanical properties of the basalt fiber (BF) reinforced poly (butyleneterefthalate) (PBT) composites, which indicated that all treated BF/PBT composites had higher overall mechanical properties than the non-treated BF/PBT composites, as shown by the increases in tensile strength, flexural strength, and impact strength from 47.6 MPa, 95.3 MPa, and 20.0 kJ/m
2, respectively, in non-treated BF/PBT composites to 61.9–63.4 MPa, 97.8–106.4 MPa, and 20.5–24.0 kJ/m
2, respectively, in treated BF/PBT composites [
21]. These examples clearly suggested the advantages of utilizing appropriate silane coupling agents to improve filler distribution and the mechanical properties of the composites, which would be useful for use in radiation protection that normally contained high filler contents.
This work determined the simulated neutron and self-emitted gamma-shielding properties of Sm
2O
3/UHMWPE composites, using Monte Carlo coding (Particle and Heavy Ion Transport Code System (PHITS)) [
22], for which the Sm
2O
3 contents varied in the range 0–50 wt.%, in 5 wt.% increments, and the results were independently verified by using a web-based program, namely XCOM [
23]. The neutron energy investigated in this work was 0.025 eV for thermal neutrons, and the gamma energies were 0.334, 0.712, and 0.737 MeV (the energies of emitted gamma rays after neutron absorption by Sm). Shielding properties of interest were the linear attenuation coefficient (µ), the mass attenuation coefficient (µ
m), and the half-value layer (HVL). In addition, the recommended Sm
2O
3 contents in UHMWPE composites for actual use were determined by comparing the simulated neutron-shielding properties with those from a commercial 5% borated material. Furthermore, this work experimentally determined the effects of a surface treatment of Sm
2O
3, using a silane coupling agent (3-aminopropyltriethoxysilane; KBE903), on elemental and chemical composition, morphological, wear resistance, frictional, and mechanical properties of UHMWPE composites that contained 25 wt.% Sm
2O
3. The KBE903 contents used for the surface treatment of Sm
2O
3 were varied from 5 to 10 and 20 parts per hundred part (pph) of Sm
2O
3. The outcomes of this work should not only reveal the theoretical effectiveness of Sm
2O
3 to attenuate thermal neutrons and self-emitted gamma rays but also present an appropriate method to improve the particle distribution, wear resistance, and mechanical properties of Sm
2O
3/UHMWPE composites by the surface treatment of Sm
2O
3, using KBE903.