New shielding composite paste for mixed fields of fast neutrons and gamma rays

Elwahab, Nesreen R. Abd; Helal, Nadia; Mohamed, Tarek A.; Shahin, F.; Ali, Fadel M.

doi:10.1016/j.matchemphys.2019.05.059

Cited by 51 publications

(18 citation statements)

References 12 publications

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“…The HVL and TVL values are between 5.46 to 8.35 and 18.1 to 27.8 cm at 1.25 MeV photon energies in the paste of HDPE, commercial borax (BX), sand, and Portland cement for 241 Am‐Be neutrons, and 60 Co gamma rays 94 …”

Section: Resultsmentioning

confidence: 99%

“…[88][89][90][91][92][93] The HVL and TVL values are between 5.46 to 8.35 and 18.1 to 27.8 cm at 1.25 MeV photon energies in the paste of HDPE, commercial borax (BX), sand, and Portland cement for 241 Am-Be neutrons, and 60 Co gamma rays. 94 F I G U R E 2 0 Thermal conductivity values of 89%, 87%, 69%, 67% Portland Cement, 1% to 3% percentage PU-Plaster and 10% to 30% percentage arsenic and lead oxide phase change materials samples, respectively In our work; arsenic oxide doped HVL values were calculated between 3.918 to 13.246 cm, 3.917 to 13.223 cm, 3.097 to 13.487 cm and 3.097 to 13.463 cm; TVL values were calculated between 13.017 to 44.002 cm, 13.011 to 43.926 cm, 10.289 to 44.802 cm and 10.289 to 44.723 cm; MFP values were calculated between 5.653 to 19.110 cm, 5.651 to 19.077 cm, 4.469 to 19.458 cm and 4.468 to 19.423 cm from 121.7817 to 1408.01 keV gamma irradiation energy regions for CCN1-CCN4 PCMs, respectively. Furthermore, lead oxide doped HVL values were calculated between 1.456 to 13.093 cm, 1.456 to 13.071 cm, 0.618 to 13.022 cm and 0.618 to 13.001 cm; TVL values were calculated between 4.836 to 43.495 cm, 4.836 to 43.419 cm, 2.053 to 43.259 cm, and 2.053 to 43.185 cm; MFP values were calculated between 2.101 to 18.889 cm, 2.100 to 18.857 cm, 0.891 to 18.787 cm, and 0.892 to 18.755 cm from 121.7817 to 1408.01 keV gamma irradiation energy regions for CCN5-CCN8 PCMs, respectively.…”

Section: Hvl Tvl Mfp and Rpementioning

confidence: 99%

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Gamma irradiation, thermal conductivity, and phase change tests of the cement‐hyperbranched poly amino‐ester‐block‐poly cabrolactone‐polyurathane plaster‐lead oxide and arsenic oxide composite for development of radiation shielding material

Cinan

Baskan

Erol

et al. 2021

Intl J of Energy Research

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Summary The work which has been done on cement‐polymer composite based shielding materials was comprehensively described in the present article, the choice of the study presented here is based on the choice of the researches. The new Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane Plaster‐concrete composites mixed with different percentage soft lead oxide and arsenic oxide is used to research gamma‐ray shielding and thermal conductivity characteristics. The synthesis of new Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane copolymer was achieved by Atom Transfer Reaction and Condensation Polymerization methods. The characterization of Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane Plaster was made with the Nuclear Magnetic Resonance, Fourier Transform Infrared Spectroscopy, Differential Scanning Calorimetry, Gel Permeation Chromatography, Thermogravimetric Analysis, Scanning Electron Microscope methods. The transmitted fluxes of gamma‐rays that were emitted from Eu152 source was detected by a High Purity Germanium (HPGe) detector system at Karadeniz Technical University‐Department of Physics in Trabzon and analyzed by a GammaVision (Version:6.07‐Ortec, Oak Ridge, TN) computer program. The composite phase change materials including 89, 87, 69, 67% Portland cement, 1% and 3% PU‐Plaster, 10% and 30% weight percent lead oxide and arsenic oxide was irradiated in the various gamma ray photon energy region (121.78, 344.28, 778.90, 964.08, 1085.87, 1112.07, and 1408.01 keV) for 3600 seconds. Then, linear attenuation coefficients, mass attenuation coefficients, half‐value layer, tenth value layer, mean free path, radiation protection efficiency, and gamma‐rays absorption of concrete‐the Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane copolymers specimens were experimentally investigated. Thermal properties and morphological analysis of the irradiated substances were explored handling differential scanning calorimetry, thermogravimetric analysis, and scanning electron microscope methods of the nano lead oxide and arsenic oxide including composite phase change material via gamma irradiation were submitted. Moreover, the effect of the Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane amount on the radiation attenuation of the composite material was investigated. Gamma attenuation experiments have been performed to specify lead equivalent values for the improved composite material. The composite equivalent thickness values from 0.5 to 0.6 cm sample thickness and 0.665 cm radius were obtained. Via crosschecking the acquired data from concrete samples with and without lead and arsenic, it was observed that, if the powder of lead oxide and arsenic oxide to cement ratio of 10% and 30% by weight is added in the concrete mixture, the concrete‐the Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane composite can be used as a suitable shield against gamma rays. Also, mass attenuation coefficients were calculated as theoret...

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Section: Resultsmentioning

confidence: 99%

Section: Hvl Tvl Mfp and Rpementioning

confidence: 99%

Gamma irradiation, thermal conductivity, and phase change tests of the cement‐hyperbranched poly amino‐ester‐block‐poly cabrolactone‐polyurathane plaster‐lead oxide and arsenic oxide composite for development of radiation shielding material

Cinan

Baskan

Erol

et al. 2021

Intl J of Energy Research

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“…The effective fast neutron removal cross sections (Σ R ) can be determined using the NXcom program (Yılmaz et al 2011;Cataldo et al 2019). There are some studies reported on the use of polymers as efficient neutron shielding materials (El Abd and Elkady 2014;Elmahroug et al 2014;Jumpee and Wongsawaeng 2015;Mann et al 2015a, b;Elwahab et al 2019;Kaçal et al 2019;Abdalsalam et al 2020).…”

Section: Polymers For Neutron Shieldingmentioning

confidence: 99%

Polymeric composite materials for radiation shielding: a review

et al. 2021

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The rising use of radioactive elements is increasing radioactive pollution and calling for advanced materials to protect individuals. For instance, polymers are promising due to their mechanical, electrical, thermal, and multifunctional properties. Moreover, composites made of polymers and high atomic number fillers should allow to obtain material with low-weight, good flexibility, and good processability. Here we review the synthesis of polymer materials for radiation protection, with focus on the role of the nanofillers. We discuss the effectivness of polymeric materials for the absorption of fast neutrons. We also present the recycling of polymers into composites.

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“…where N i is the volumetric density of the ith nuclide, N A is the Avogadro's number (6.023 × 10 23 ), while A i and ρ i are the partial density (g cm −3 ) and atomic weight of the ith nuclide in the mixture respectively. The inverse of macroscopic cross sections gives average distance a neutron would travelled in a material before an interaction could occurred, and it is called mean free path (mfp) λ (m) [7,8]. From Equation (3), it is obvious that a light nucleus (such as hydrogen) would be more effective in fast neutron shielding.…”

Section: Introductionmentioning

confidence: 99%

Fabrication and Characterization of Clay-Polyethylene Composite Opted for Shielding of Ionizing Radiation

et al. 2021

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This study fabricated and characterized a self-sustaining hydrogenous content clay-polyethylene composite opted for ionizing radiation shielding. Composites designated A–G were fabricated each containing 0–30 wt% of recycled low density polyethylene (LDPE), respectively. To know the effects of the incorporated LDPE on the morphology, microstructural, compressive strength, thermal property and displacement effect on the vital elements were studied using scanning electron microscopy (SEM), X-ray diffractometry (XRD), universal mechanical testing machine, differential thermal analysis (DTA), Rutherford backscattering (RBS) technique and particle induced X-ray emission (PIXE), respectively. The bulk densities of the clay composites ranged between 1.341 and 2.030 g/cm3. The samples’ XRD analysis revealed similar patterns, with a sharp and prominent peak at angle 2θ equals ~26.11°, which matched with card number 16-0606 of the Joint Committee on Powder Diffraction Standards (JCPDS) that represents Aluminum Silicate Hydroxide (Al2Si2O5(OH)4), a basic formula for Kaolin clay. The compressive strength ranged between 2.52 and 5.53 MPa. The ratio of Si to Al in each composite is about 1:1. The dehydroxylation temperature for samples ranged between 443.23 °C and 555.23 °C.

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New shielding composite paste for mixed fields of fast neutrons and gamma rays

Cited by 51 publications

References 12 publications

Gamma irradiation, thermal conductivity, and phase change tests of the cement‐hyperbranched poly amino‐ester‐block‐poly cabrolactone‐polyurathane plaster‐lead oxide and arsenic oxide composite for development of radiation shielding material

Gamma irradiation, thermal conductivity, and phase change tests of the cement‐hyperbranched poly amino‐ester‐block‐poly cabrolactone‐polyurathane plaster‐lead oxide and arsenic oxide composite for development of radiation shielding material

Polymeric composite materials for radiation shielding: a review

Fabrication and Characterization of Clay-Polyethylene Composite Opted for Shielding of Ionizing Radiation

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