Bu çalışmada, B₄C, B₂O₃, Sm₂O₃ ve Gd₂O₃ katkılı (%5, %10, %15, %20 ve %25 ağırlık oranlarında) parafin, polikarbonat ve polyester matrisli polimerlerin termal (2.53*10^-8 MeV) ve hızlı (2 MeV) nötron toplam makroskopik tesir kesitleri Monte Carlo simülasyonu kullanılarak hesaplanmıştır. Ayrıca, hızlı nötronların makroskopik etkin ayırma tesir kesiti (∑_R), polimerlerdeki ve katkı maddelerindeki elementlerin kütlesel ayırma tesir kesiti değerleri (〖 ∑〗_R⁄ρ) kullanılarak teorik olarak da hesaplanmıştır. Elde edilen sonuçlar, en yüksek termal nötron toplam makroskopik tesir kesiti Gd2O3 katkılı polikarbonat ve en yüksek hızlı nötron toplam makroskopik tesir kesiti Sm2O3 katkılı parafin ile elde edildiğini göstermiştir. Bunun yanında parafinin, tüm katkı maddeleri için en yüksek hızlı nötron toplam makroskopik kesitine sahip olduğu görülmüştür. Bu çalışmanın sonuçları, B₄C, B₂O₃, Sm₂O₃ ve Gd₂O₃ katkılı parafin, polikarbonat ve polyester matrisli polimerlerin termal ve hızlı nötronlara karşı zırhlama özelliklerinin iyi bir şekilde anlaşılmasını sağlamıştır. In this study, thermal (2.53*10^-8 MeV) and fast (2 MeV) neutron total macroscopic cross-sections of paraffin, polycarbonate, and polyester matrix polymers doped with B₄C, B₂O₃, Sm₂O₃, and Gd₂O₃ (at weight percentages of 5%, 10%, 15%, 20%, and 25%) were computed by using Monte Carlo simulations. Additionally, the macroscopic effective removal cross-section ) of fast neutrons was theoretically computed based on the mass removal cross-section values ) for various elements in polymers and additives. The obtained results show that the highest thermal neutron total macroscopic cross-section was obtained in polycarbonate doped with Gd2O3, and the highest fast neutron total macroscopic cross-section was observed in paraffin doped with Sm2O3. Besides, the paraffin provided the highest fast neutron total macroscopic cross-section for all additives. The results of this study provide a good understanding of shielding properties of paraffin, polycarbonate, and polyester matrix polymers doped with B₄C, B₂O₃, Sm₂O₃, and Gd₂O₃ against thermal and fast neutrons.

The significance of radiation shielding is on the rise due to the expanding areas exposed to radiation emissions. Consequently, there is a critical need to develop metal alloys and composites that exhibit excellent capabilities in absorbing neutron and gamma rays for effective radiation shielding. Low-density Ti-based alloys with controlled structural properties can be used for radiation protection purposes. The present research investigates boron-doped Ti-based alloy, Ti₅₀Cu₃₀Zr₁₅B₅, which is synthesized by arc melting technique, and its structural, mechanical properties, neutron, and gamma-ray transmission rate were investigated. Monte Carlo N-Particle simulation (MCNP6.2) code is used for calculating the Thermal (2.53 $\times$ 10⁻⁸ MeV) and fast (2 MeV) neutron transmission ratio (I/I₀) dependent on the sample thickness. The Phy-x program is employed for calculating the gamma-ray LAC, MAC, HVL, TVL, and MFP values. The calculated neutron shielding performance parameters of Ti₅₀Cu₃₀Zr₁₅B₅ alloy were compared with materials in the literature. It was found that Ti₅₀Cu₃₀Zr₁₅B₅ alloy demonstrated impressive physical characteristics, suggesting that it can serve as a promising alloy for neutron and gamma-ray shielding applications.

This study investigated the neutron shielding properties of epoxy-(20B, 38.2Sm, 6.46Gd) composites in the thermal, epithermal, intermediate, and fast neutron energy regions. The neutron macroscopic cross-section, neutron attenuation ratio as a function of shield thickness (ranging from 0.05 to 10 cm), and secondary gamma rays generated by neutron interactions were calculated using the MCNP6.2 Monte Carlo simulation code. The addition of B, Sm, and Gd significantly improved the neutron shielding performance of the epoxy matrix, particularly in the thermal and epithermal energy regions. The epoxy-38.2Sm composite exhibited the highest neutron macroscopic cross-section, with a value of 44.3 cm⁻¹ in the thermal energy region. Additionally, the most effective shielding material in the epithermal region was the epoxy-20B composite, with a macroscopic cross-section of 1.9 cm⁻¹. Although Gd has the highest thermal neutron absorption cross-section, it is less effective than B and Sm in thermal and epithermal energy regions. The results indicate that the epoxy-20B composite provides the most effective neutron shielding properties and emits low-energy secondary gamma radiation. In addition, the linear attenuation coefficient, mass attenuation coefficient, and half-value layer values of gamma-rays in the 0.1–5 MeV energy range were calculated using the Phy-x/PSD program. Across all energy values, the epoxy-38.2Sm composite exhibited the best gamma-ray shielding performance. Future studies suggest incorporating elements with high gamma-ray absorption properties, such as tungsten, lead, or bismuth, into this composition to further reduce secondary gamma radiation.