Fabrication and characterization of GdxFe2O3(100-x) /PVA (x=0, 5, 10, 20) composite films for radiation shielding

Macroscopic and microscopic radiation effects on glass materials

“…过渡金属氧化物一般存在于玻璃体系的间隙或取代基体元素位置， 可在一定程度上提升 玻璃的辐照屏蔽性能。 V 2 O 5 可以作为调节剂增强玻璃的光学、电学性能等。在低浓度掺杂下(0-4mol%)的 热稳定性能较好， 且光学带隙及 Urbach 能下降 (光学带隙从 3.19eV 下降至 1.85eV， Urbach 能从 0.141eV 降至 0.131eV) ，可作为玻璃体系的调节剂 [128] 。根据 Tekin 等 [129] 对钒掺杂硼 酸锌玻璃的研究(掺杂浓度 1-4mol%) ，玻璃密度随着 V 2 O 5 浓度的增加而降低，对γ射线 的屏蔽效果不佳。根据 Kavun 等 [115] 的最新研究，高浓度掺杂的磷硼锂玻璃，质量衰减系数 随着 V 2 O 5 浓度增加而增加，表现出较好的屏蔽性能。 掺杂氧化铬的玻璃有着较好的光学性能等，铬离子一般以三价和六价形式存在，且两种 离子可以不同比例共存，铬离子掺杂表现出较好的辐照屏蔽性能。根据 Aktas 等 [110] 对硼硅 F o r R e v i e w O n l y 酸玻璃掺杂氧化铬的研究，玻璃密度(未掺杂为 2.02g/cm 3 )随着氧化铬含量的增加而增 加至 3.15g/cm 3 ，当氧化铬含量为 5wt%，光子能量为 59.54keV 时，质量衰减系数增加至 0.324cm 2 /g (未掺杂为 0.231cm 2 /g) 。 Shaaban 等 [72] 对 Cr 掺杂硼硅酸盐玻璃的研究认为， [74] 此玻璃体系的快中子有效去除截 面为 0.122cm -1 ,高于水、石墨和混凝土，有着优良的屏蔽性能。根据 Mario 等 [75] 的研究也 表明，掺杂 Cd 的玻璃的屏蔽性能要优于同为过渡元素的 Zn、Ag。…”

Recent Progress in Gd-Containing Materials for Neutron Shielding Applications: A Review

“…The integration of Gd nanofillers in PMCs has brought remarkable improvements in both radiation shielding performance and mechanical properties. Nevertheless, recent studies revealed that excessive Gd content may have unfavorable impacts, i.e., a linear decrease in thermal stabilities of Gd x Fe 2 O 3 /PVA composites [ 84 ]. Likewise, He et al [ 85 ] reported that the addition of nano-Gd 2 O 3 is unfavorable to the thermal stability of the salicylic acid polyphenylene sulfide (SAPPS) composites.…”

Study of the Structural, Morphological, Strength and Shielding Properties of CuBi2O4 Films Obtained by Electrochemical Synthesis

“…Recently, significant attention has been directed towards advancements in producing various composite shielding materials. These include amorphous glasses or ceramics [27][28][29][30]; polymer matrices embedded with rare-earth metal particles or oxide inclusions (such as iron oxide and bismuth) [31,32]; and composite multilayer films, which are primarily used for electromagnetic radiation shielding [33,34]. At the same time, the assessment of the shielding efficiency of these films is determined both during full-scale experiments using various reference sources of ionizing radiation (Co 57 , Co 60 , Na 22 and Cs 137 ) [35,36] and by simulation of the processes of ionizing radiation interaction with matter using program code based on the Monte Carlo method [37,38].…”