A. A. Rotkovich, D. I. Tishkevich, S. A. German, A. A. Bondaruk, S. V. Leonchik, E. S. Dashkevich, V. M. Fedosyuk, A. V. Trukhanov
{"title":"用于伽马辐射屏蔽的环氧树脂-W 系统复合材料","authors":"A. A. Rotkovich, D. I. Tishkevich, S. A. German, A. A. Bondaruk, S. V. Leonchik, E. S. Dashkevich, V. M. Fedosyuk, A. V. Trukhanov","doi":"10.35596/1729-7648-2023-21-6-5-13","DOIUrl":null,"url":null,"abstract":"Сomposite materials based on the epoxy resin–W system with varying W content (0–80 %) were obtained using the method of chemical curing. Microstructural investigations of the samples showed that with increasing W content there is a more uniform distribution of grains in the epoxy resin matrix could be observed. Agglomeration of W grains is noted for samples with filler content up to 40 %. Statistical analysis of the grain size of the initial W powder revealed that the probable diameter of W grains is 475 nm. The values of effective and relative densities of the experimental samples were obtained using the Archimedes method. The effective density varied from 1.16 to 4.36 g/cm3 with W powder content rising. The relative density values received ranged from 91 to 94 %, indica ting that there were no significant defects in the samples. X-ray diffraction analysis showed the presence of vcc-W and WO2 phases, indicating the oxidation of W in the thin surface layer of the powder. Calculation in Phy-X/PSD software allowed to evaluate the gamma radiation shielding efficiency for the epoxy resin–W system composite materials in 0.8–2.5 MeV energy range. It was observed that samples with filler content of 60 and 80 % were the most suitable for radiation shielding. It was found that the addition of W powder to the epoxy matrix contributed to the reduction of half attenuation layer values by 3.5 times from 9.448 to 2.672 cm for samples with 0 and 80 % W content, respectively, for 1.25 MeV radiation energy. The obtained results demonstrate the high efficiency of the proposed composite materials for shielding gamma radiation, which makes them a perspective candidate for manufacturing radiation shields.","PeriodicalId":122672,"journal":{"name":"Doklady BGUIR","volume":"13 1","pages":""},"PeriodicalIF":0.0000,"publicationDate":"2024-01-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Composite Materials of Epoxy Resin–W System for Radiation Shielding Against Gamma Radiation\",\"authors\":\"A. A. Rotkovich, D. I. Tishkevich, S. A. German, A. A. Bondaruk, S. V. Leonchik, E. S. Dashkevich, V. M. Fedosyuk, A. V. Trukhanov\",\"doi\":\"10.35596/1729-7648-2023-21-6-5-13\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Сomposite materials based on the epoxy resin–W system with varying W content (0–80 %) were obtained using the method of chemical curing. Microstructural investigations of the samples showed that with increasing W content there is a more uniform distribution of grains in the epoxy resin matrix could be observed. Agglomeration of W grains is noted for samples with filler content up to 40 %. Statistical analysis of the grain size of the initial W powder revealed that the probable diameter of W grains is 475 nm. The values of effective and relative densities of the experimental samples were obtained using the Archimedes method. The effective density varied from 1.16 to 4.36 g/cm3 with W powder content rising. The relative density values received ranged from 91 to 94 %, indica ting that there were no significant defects in the samples. X-ray diffraction analysis showed the presence of vcc-W and WO2 phases, indicating the oxidation of W in the thin surface layer of the powder. Calculation in Phy-X/PSD software allowed to evaluate the gamma radiation shielding efficiency for the epoxy resin–W system composite materials in 0.8–2.5 MeV energy range. It was observed that samples with filler content of 60 and 80 % were the most suitable for radiation shielding. It was found that the addition of W powder to the epoxy matrix contributed to the reduction of half attenuation layer values by 3.5 times from 9.448 to 2.672 cm for samples with 0 and 80 % W content, respectively, for 1.25 MeV radiation energy. The obtained results demonstrate the high efficiency of the proposed composite materials for shielding gamma radiation, which makes them a perspective candidate for manufacturing radiation shields.\",\"PeriodicalId\":122672,\"journal\":{\"name\":\"Doklady BGUIR\",\"volume\":\"13 1\",\"pages\":\"\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2024-01-04\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Doklady BGUIR\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.35596/1729-7648-2023-21-6-5-13\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Doklady BGUIR","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.35596/1729-7648-2023-21-6-5-13","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0
摘要
利用化学固化法获得了基于环氧树脂-W 系统的不同 W 含量(0-80%)的С 复合材料。样品的微观结构研究表明,随着 W 含量的增加,环氧树脂基体中的晶粒分布更加均匀。在填料含量高达 40% 的样品中,可以观察到 W 晶粒的聚集。对初始 W 粉末晶粒大小的统计分析显示,W 晶粒的可能直径为 475 nm。实验样品的有效密度和相对密度值是用阿基米德法得到的。随着 W 粉末含量的增加,有效密度在 1.16 至 4.36 g/cm3 之间变化。得到的相对密度值在 91% 到 94% 之间,表明样品中没有明显的缺陷。X 射线衍射分析表明存在 vcc-W 和 WO2 相,表明 W 在粉末的薄表层被氧化。通过 Phy-X/PSD 软件的计算,可以评估环氧树脂-W 系统复合材料在 0.8-2.5 MeV 能量范围内的伽马辐射屏蔽效率。结果表明,填料含量为 60% 和 80% 的样品最适合屏蔽辐射。研究发现,在 1.25 MeV 辐射能量下,环氧树脂基体中添加 W 粉末可使 W 含量为 0% 和 80% 的样品的半衰减层值降低 3.5 倍,从 9.448 厘米降至 2.672 厘米。研究结果表明,所提出的复合材料具有很高的伽马辐射屏蔽效率,因此是制造辐射屏蔽的理想材料。
Composite Materials of Epoxy Resin–W System for Radiation Shielding Against Gamma Radiation
Сomposite materials based on the epoxy resin–W system with varying W content (0–80 %) were obtained using the method of chemical curing. Microstructural investigations of the samples showed that with increasing W content there is a more uniform distribution of grains in the epoxy resin matrix could be observed. Agglomeration of W grains is noted for samples with filler content up to 40 %. Statistical analysis of the grain size of the initial W powder revealed that the probable diameter of W grains is 475 nm. The values of effective and relative densities of the experimental samples were obtained using the Archimedes method. The effective density varied from 1.16 to 4.36 g/cm3 with W powder content rising. The relative density values received ranged from 91 to 94 %, indica ting that there were no significant defects in the samples. X-ray diffraction analysis showed the presence of vcc-W and WO2 phases, indicating the oxidation of W in the thin surface layer of the powder. Calculation in Phy-X/PSD software allowed to evaluate the gamma radiation shielding efficiency for the epoxy resin–W system composite materials in 0.8–2.5 MeV energy range. It was observed that samples with filler content of 60 and 80 % were the most suitable for radiation shielding. It was found that the addition of W powder to the epoxy matrix contributed to the reduction of half attenuation layer values by 3.5 times from 9.448 to 2.672 cm for samples with 0 and 80 % W content, respectively, for 1.25 MeV radiation energy. The obtained results demonstrate the high efficiency of the proposed composite materials for shielding gamma radiation, which makes them a perspective candidate for manufacturing radiation shields.