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Wang J, Sun Q, Gao J, Xie Y, Si Q, Liang X, Liu J, Hu D, Huang P, Wang S, Liu G, Mi A. Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104603] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/05/2023]
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2
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Wang B, Qiu T, Yuan L, Fang Q, Wang X, Guo X, Zhang D, Lai C, Wang Q, Liu Y. A comparative study between pure bismuth/tungsten and the bismuth tungsten oxide for flexible shielding of gamma/X rays. Radiat Phys Chem Oxf Engl 1993 2023. [DOI: 10.1016/j.radphyschem.2023.110906] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 03/11/2023]
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3
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Yilmaz M, Pekdemir ME, Özen Öner E. Evaluation of Pb doped Poly(lactic acid) (PLA) / Poly(ethylene glycol) (PEG) blend composites regarding physicochemical and radiation shielding properties. Radiat Phys Chem Oxf Engl 1993 2023. [DOI: 10.1016/j.radphyschem.2022.110509] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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4
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Barala SS, Manda V, Jodha AS, C A, Gopalani D. Thermal stability of gamma irradiated
ethylene propylene diene monomer
composites for shielding applications. J Appl Polym Sci 2022. [DOI: 10.1002/app.52975] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]
Affiliation(s)
| | - Vikram Manda
- Hari Shankar Singhania Elastomer & Tyre Research Institute Mysuru India
| | | | - Ajay C
- Hari Shankar Singhania Elastomer & Tyre Research Institute Mysuru India
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Synthesizing of Metallized Acrylic Containing Both Gadolinium and Lead as a Transparent Radiation Shielding Material and Its Physical Properties. METALS 2022. [DOI: 10.3390/met12060990] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Abstract
In this study, a series of optically transparent metallized acrylics containing Gd and Pb were synthesized by the bulk polymerization of Gd(MAA)3, Pb(MAA)2 and AM according to different polymerization procedures. The variation of their optic transmittance and mechanical performance with Gd contents was investigated. Then, quasi-static uniaxial tensile tests under different strain rates and temperatures were performed to study the influence of strain rate and temperature on the mechanical properties of radiation-shielding metallized acrylic containing both Gd and Pb. The tensile responses of this material distinctly exhibit nonlinear characteristics and strongly depend on both temperature and strain rate. Based on the experimental results, a modified Zhu–Wang–Tang (ZWT) constitutive model, in which the standard elastic component was replaced by the Mooney–Rivlin hyperelastic model, was implemented to characterize the observed both hyperelastic and viscoelastic behaviors. The constitutive parameters were expressed as functions of temperature and determined by experimental data. The model fitting results indicate that the selected constitutive model can accurately describe the nonlinear tensile stress–strain responses of metallized acrylic containing Gd and Pb. Furthermore, the great difference in constitutive parameters implies that the viscoelastic behavior of the as-prepared metallized acrylic affects the response to quasi-static tensile loading the most.
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A. Abu Saleem R, Abdelal N, Alsabbagh A, Al-Jarrah M, Al-Jawarneh F. Radiation Shielding of Fiber Reinforced Polymer Composites Incorporating Lead Nanoparticles-An Empirical Approach. Polymers (Basel) 2021; 13:3699. [PMID: 34771256 PMCID: PMC8587508 DOI: 10.3390/polym13213699] [Citation(s) in RCA: 10] [Impact Index Per Article: 3.3] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 09/14/2021] [Revised: 10/20/2021] [Accepted: 10/21/2021] [Indexed: 11/17/2022] Open
Abstract
In the present work, an empirical approach based on a computational analysis is performed to study the shielding properties of epoxy/carbon fiber composites and epoxy/glass fiber composites incorporating lead nanoparticle (PbNPs) additives in the epoxy matrix. For this analysis, an MCNP5 model is developed for calculating the mass attenuation coefficients of the two fiber reinforced polymer (FRP) composites incorporating lead nanoparticles of different weight fractions. The model is verified and validated for different materials and different particle additives. Empirical correlations of the mass attenuation coefficient as a function of PbNPs weight fraction are developed and statistically analyzed. The results show that the mass attenuation coefficient increases as the weight fraction of lead nanoparticles increases up to a certain threshold (~15 wt%) beyond which the enhancement in the mass attenuation coefficient becomes negligible. Furthermore, statistical parameters of the developed correlations indicate that the correlations can accurately capture the behavior portrayed by the simulation data with acceptable root mean square error (RMSE) values.
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Affiliation(s)
- Rabie A. Abu Saleem
- Nuclear Engineering Department, Jordan University of Science and Technology, P.O. Box 3030, Irbid 22110, Jordan; (A.A.); (M.A.-J.); (F.A.-J.)
| | - Nisrin Abdelal
- Mechanical Engineering Department, Jordan University of Science and Technology, P.O. Box 3030, Irbid 22110, Jordan;
| | - Ahmad Alsabbagh
- Nuclear Engineering Department, Jordan University of Science and Technology, P.O. Box 3030, Irbid 22110, Jordan; (A.A.); (M.A.-J.); (F.A.-J.)
| | - Maram Al-Jarrah
- Nuclear Engineering Department, Jordan University of Science and Technology, P.O. Box 3030, Irbid 22110, Jordan; (A.A.); (M.A.-J.); (F.A.-J.)
| | - Fatima Al-Jawarneh
- Nuclear Engineering Department, Jordan University of Science and Technology, P.O. Box 3030, Irbid 22110, Jordan; (A.A.); (M.A.-J.); (F.A.-J.)
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Wang J, Zhou H, Gao Y, Xie Y, Zhang J, Hu Y, Wang D, You Z, Wang S, Li H, Liu G, Mi A. The Characterization of Silicone-Tungsten-Based Composites as Flexible Gamma-Ray Shields. MATERIALS (BASEL, SWITZERLAND) 2021; 14:5970. [PMID: 34683561 PMCID: PMC8537426 DOI: 10.3390/ma14205970] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 08/22/2021] [Revised: 10/05/2021] [Accepted: 10/08/2021] [Indexed: 11/16/2022]
Abstract
Robots are very essential for modern nuclear power plants to monitor equipment conditions and eliminate accidents, allowing one to reduce the radiations on personnel. As a novel robot, a soft robot with the advantages of more degrees of freedom and abilities of continuously bending and twisting has been proposed and developed for applications in nuclear power industry. Considering the radiation and high-temperature environment, the overall performance improvement of the flexible materials used in the soft nuclear robot, such as the tensile property and gamma-ray shielding property, is an important issue, which should be paid attention. Here, a flexible gamma-ray shielding material silicone-W-based composites were initially doped with nano titanium oxide and prepared, with the composition of 20 silicone-(80-x) W-(x) TiO2, where x varied from 0.1 to 2.0 wt.%. Structural investigations on SEM and EDS were performed to confirm the structure of the prepared composites and prove that all the chemicals were included in the compositions. Moreover, the tensile property of the composites at 25, 100, and 150 °C were investigated to study the effect of working temperature on the flexibility of the compositions. The attenuation characteristics including the linear attenuation coefficients and mass attenuation coefficients of the prepared silicone-W or silicone-W-TiO2-based composites with respect to gamma ray were investigated. The stability of the silicone-tungsten-TiO2-based composite at high temperature was studied for the first time. In addition, the influence of nano TiO2 additive on the property's variation of silicone-W-based composites was initially studied. The comparison of the properties such as the tensile elongation, thermal stability, and gamma-ray shielding of the synthesized silicone-W and silicone-W-TiO2 composites showed that the addition of nano TiO2 powders could be useful to develop novel gamma-ray-shielding materials for radiation protection of soft robots or other applications for which soft gamma-ray-shielding materials are needed.
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Affiliation(s)
- Jie Wang
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Haoyu Zhou
- Department of Engineering Physics, Tsinghua University, Beijing 100084, China;
| | - Yong Gao
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Yupeng Xie
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Jing Zhang
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Yaocheng Hu
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Dengwang Wang
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Zhiming You
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Sheng Wang
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Haipeng Li
- Shaanxi Engineering Research Center of Advanced Nuclear Energy, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; (J.W.); (Y.G.); (Y.X.); (J.Z.); (Y.H.); (D.W.); (Z.Y.); (H.L.)
| | - Guoming Liu
- China Nuclear Power Engineering Co., Ltd., Beijing 100840, China; (G.L.); (A.M.)
| | - Aijun Mi
- China Nuclear Power Engineering Co., Ltd., Beijing 100840, China; (G.L.); (A.M.)
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Wang J, Zheng T, Gao Y, Wang D, Cui W, Fan J, You Z, Zhang J, Du X, Qiao Z, Wang X, Wang S, Xu Z, Wang C. Preparation and properties characterization of a novel soft robots partially made of silicone/W-based composites for gamma ray shielding. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103531] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Mansouri E, Mesbahi A, Malekzadeh R, Mansouri A. Shielding characteristics of nanocomposites for protection against X- and gamma rays in medical applications: effect of particle size, photon energy and nano-particle concentration. RADIATION AND ENVIRONMENTAL BIOPHYSICS 2020; 59:583-600. [PMID: 32780196 DOI: 10.1007/s00411-020-00865-8] [Citation(s) in RCA: 16] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 02/02/2020] [Accepted: 07/28/2020] [Indexed: 06/11/2023]
Abstract
In recent decades, nanomaterials have been extensively investigated for many applications. Composites doped with different metal nanoparticles have been suggested as effective shielding materials to replace conventional lead-based materials. The use of concretes as structural and radiation protective material has been influenced by the addition of nanomaterials. Several elements with high atomic number and density, such as lead, bismuth, and tungsten, have the potential to form nanoparticles that offer significant enhancements in the shielding ability of composites. Their performance for a range of particle concentrations, particle sizes, and photon energies have been investigated. This review is an attempt to gather the data published in the literature about the application of nanomaterials in radiation shielding, including the use of polymer composites and concretes for protection against X-rays and gamma radiation.
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Affiliation(s)
- Elham Mansouri
- Drug Applied Research Center, Tabriz University of Medical Sciences, Tabriz, Iran
- Molecular Medicine Research Center, Tabriz University of Medical Sciences, Tabriz, Iran
| | - Asghar Mesbahi
- Molecular Medicine Research Center, Tabriz University of Medical Sciences, Tabriz, Iran.
- Department of Medical Physics, School of Medicine, Tabriz University of Medical Sciences, Tabriz, Iran.
| | - Reza Malekzadeh
- Department of Medical Physics, School of Medicine, Tabriz University of Medical Sciences, Tabriz, Iran
| | - Ahmad Mansouri
- Department of Materials Engineering, University of Tabriz, 51666-16471, Tabriz, Iran
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Gamma-ray attenuation behaviors of hematite doped polymer composites. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103504] [Citation(s) in RCA: 17] [Impact Index Per Article: 4.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/21/2022]
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Belgin EE, Aycik GA. Preparation, characterization and comparative ionizing electromagnetic radiation performances: part I—metal oxide reinforced polymeric composites. J Radioanal Nucl Chem 2020. [DOI: 10.1007/s10967-020-07245-y] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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12
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Effect of gamma irradiation and lead content on the physical and shielding properties of PVC/NBR polymer blends. Polym Bull (Berl) 2019. [DOI: 10.1007/s00289-019-03022-4] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Hammannavar PB, Lobo B. Experimental study of the microstructure and optical properties of PVA-PVP blend filled with lead nitrate. ACTA ACUST UNITED AC 2018. [DOI: 10.1016/j.matpr.2018.01.048] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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15
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Eren Belgin E, Aycik GA, Kalemtas A, Pelit A, Dilek DA, Kavak MT. Usability of natural titanium-iron oxide as filler material for ionizing electromagnetic radiation shielding composites; preparation, characterization and performance. J Radioanal Nucl Chem 2015. [DOI: 10.1007/s10967-015-4643-y] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Eren Belgin E, Aycik G, Kalemtas A, Pelit A, Dilek D, Kavak M. Preparation and characterization of a novel ionizing electromagnetic radiation shielding material: Hematite filled polyester based composites. Radiat Phys Chem Oxf Engl 1993 2015. [DOI: 10.1016/j.radphyschem.2015.06.008] [Citation(s) in RCA: 28] [Impact Index Per Article: 3.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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17
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Eren Belgin E, Aycik GA. Preparation and radiation attenuation performances of metal oxide filled polyethylene based composites for ionizing electromagnetic radiation shielding applications. J Radioanal Nucl Chem 2015. [DOI: 10.1007/s10967-015-4052-2] [Citation(s) in RCA: 33] [Impact Index Per Article: 3.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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The Effect of Various Waste Materials' Contents on the Attenuation Level of Anti-Radiation Shielding Concrete. MATERIALS 2013; 6:4836-4846. [PMID: 28788363 PMCID: PMC5452844 DOI: 10.3390/ma6104836] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 07/06/2013] [Revised: 08/07/2013] [Accepted: 10/14/2013] [Indexed: 11/27/2022]
Abstract
Samples of concrete contain various waste materials, such as iron particulates, steel balls of used ball bearings and slags from steel industry were assessed for their anti-radiation attenuation coefficient properties. The attenuation measurements were performed using gamma spectrometer of NaI (Tl) detector. The utilized radiation sources comprised 137Cs and 60Co radioactive elements with photon energies of 0.662 MeV for 137Cs and two energy levels of 1.17 and 1.33 MeV for the 60Co. Likewise the mean free paths for the tested samples were obtained. The aim of this work is to investigate the effect of the waste loading rates and the particulate dispersive manner within the concrete matrix on the attenuation coefficients. The maximum linear attenuation coefficient (μ) was attained for concrete incorporates iron filling wastes of 30 wt %. They were of 1.12 ± 1.31×10−3 for 137Cs and 0.92 ± 1.57 × 10−3 for 60Co. Substantial improvement in attenuation performance by 20%–25% was achieved for concrete samples incorporate iron fillings as opposed to that of steel ball samples at different (5%–30%) loading rates. The steel balls and the steel slags gave much inferior values. The microstructure, concrete-metal composite density, the homogeneity and particulate dispersion were examined and evaluated using different metallographic, microscopic and measurement facilities.
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