The Experts below are selected from a list of 198 Experts worldwide ranked by ideXlab platform
S.e. Gwaily - One of the best experts on this subject based on the ideXlab platform.
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Natural rubber composites as thermal neutron radiation shields: I. B4C/NR composites
Polymer Testing, 2002Co-Authors: S.e. Gwaily, M.m. Badawy, H. H. Hassan, M. MadaniAbstract:Abstract Different amounts of boric acid (H3BO3) were mixed with a conductive natural rubber (loaded with 40 phr of HAF carbon black) to get thermal neutron radiation shielding composites. It was found that the total Macroscopic Cross-Section reaches 0.29 cm−1 at 30 phr of H3BO3. The dependence of thermal and electrical properties of such composites on the concentration of H3BO3 was also studied. Thermal oxidative aging was found to markedly affect the above properties.
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Ethylene-propylene diene rubber/low density polyethylene/boron carbide composites as neutron shields
Polymer Degradation and Stability, 1995Co-Authors: Mohamed Mamdouh Abdel Aziz, S.e. Gwaily, A.s. Makarious, A. El-sayed AbdoAbstract:Abstract Composites of ethylene-propylene diene rubber and low density polyethylene were prepared with two different concentrations of boron carbide powder, namely, 47 and 57 wt%. The composites were investigated for their gamma and slow neutron radiation shielding properties. In addition, the temperature dependence of the electrical and thermal properties of the composites in the temperature range 30–150 °C, has been studied. The initial 1.5 cm thickness of the composite sample containing 57 wt% boron carbide sharply reduced the initial direct slow neutron flux by about 85%. The total Macroscopic Cross-Section of this sample is 0.215 cm−1.
M. Madani - One of the best experts on this subject based on the ideXlab platform.
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Natural rubber composites as thermal neutron radiation shields: I. B4C/NR composites
Polymer Testing, 2002Co-Authors: S.e. Gwaily, M.m. Badawy, H. H. Hassan, M. MadaniAbstract:Abstract Different amounts of boric acid (H3BO3) were mixed with a conductive natural rubber (loaded with 40 phr of HAF carbon black) to get thermal neutron radiation shielding composites. It was found that the total Macroscopic Cross-Section reaches 0.29 cm−1 at 30 phr of H3BO3. The dependence of thermal and electrical properties of such composites on the concentration of H3BO3 was also studied. Thermal oxidative aging was found to markedly affect the above properties.
A. El-sayed Abdo - One of the best experts on this subject based on the ideXlab platform.
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Insulating epoxy/barite and polyester/barite composites for radiation attenuation.
Applied Radiation and Isotopes, 2013Co-Authors: M.a. El-sarraf, A. El-sayed AbdoAbstract:Abstract A trial has been made to create insulating Epoxy/Barite (EP/Brt) ( ρ =2.85 g cm −3 ) and Crosslinked Unsaturated Polyester/Barite (CUP/Brt) ( ρ =3.25 g cm −3 ) composites with radiation attenuation and shielding capabilities. Experimental work regarding mechanical and physical properties was performed to study the composites integrity for practical applications. The properties were found to be reasonable. Radiation attenuation properties have been carried out using emitted collimated beam from a fission 252 Cf (100 µg) neutron source, and the neutron–gamma spectrometer with stilbene scintillator. The pulse shape discriminating (P.S.D) technique based on the zero Cross-over method was used to discriminate between neutron and gamma-ray pulses. Thermal neutron fluxes, measured using the BF 3 detector and thermal neutron detection system, were used to plot the attenuation relations. The fast neutron Macroscopic effective removal Cross-Section Σ R , gamma ray total attenuation coefficient µ and thermal neutron Macroscopic Cross-Section Σ have been evaluated. Theoretical calculations have been achieved using MCNP-4C2 code to calculate Σ R , µ and Σ . Also, MERCSF-N program was used to calculate Macroscopic effective removal Cross-Section Σ R . Measured and calculated results have been compared and were found to be in reasonable agreement.
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Ethylene-propylene diene rubber/low density polyethylene/boron carbide composites as neutron shields
Polymer Degradation and Stability, 1995Co-Authors: Mohamed Mamdouh Abdel Aziz, S.e. Gwaily, A.s. Makarious, A. El-sayed AbdoAbstract:Abstract Composites of ethylene-propylene diene rubber and low density polyethylene were prepared with two different concentrations of boron carbide powder, namely, 47 and 57 wt%. The composites were investigated for their gamma and slow neutron radiation shielding properties. In addition, the temperature dependence of the electrical and thermal properties of the composites in the temperature range 30–150 °C, has been studied. The initial 1.5 cm thickness of the composite sample containing 57 wt% boron carbide sharply reduced the initial direct slow neutron flux by about 85%. The total Macroscopic Cross-Section of this sample is 0.215 cm−1.
Tomasz Piotrowski - One of the best experts on this subject based on the ideXlab platform.
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Neutron shielding evaluation of concretes and mortars: A review
Construction and Building Materials, 2021Co-Authors: Tomasz PiotrowskiAbstract:Abstract The purpose of this research is to present a complex method for the evaluation of the shielding efficiency of concretes and mortars used in biological shields against ionizing radiation, especially against neutrons. Since the commonly used fast neutron effective removal Cross-Section calculation does not take into account thermal neutron absorption reactions, an original method adopted from the fast neutron effective removal Cross-Section calculation based on the Macroscopic Cross-Section calculation for compositions is therefore proposed. This method was used to compare the shielding efficiency of concretes and mortars previously investigated by researchers in the literature. It was used also to prove the efficiency of material modification by polymers, gadolinium and boron compounds, which significantly improves thermal neutron absorption. The proposed complex neutron shielding evaluation method will be very useful in the design of tailored shielding concrete in the future.
Smita Joshi - One of the best experts on this subject based on the ideXlab platform.
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Multicomponent red mud-polyester composites for neutron shielding application
Materials Chemistry and Physics, 2019Co-Authors: Sapana Guru, S. S. Amritphale, Jyotishankar Mishra, Smita JoshiAbstract:Abstract Novel polyester composites for neutron shielding have been formulated by using processed red mud which is an aluminium industry waste and pure phase material. A method for making neutron shielding materials utilizing processed red mud with boric acid with polyester matrix has been developed. The developed neutron shielding materials have been studied for fast and thermal neutron shielding by using 12 Ci Am Be radiation source. The total Macroscopic Cross Section of red mud-polyester composites has been calculated and compared in this paper. Developed composites were characterised by X-ray powder diffraction, SEM, FTIR, and thermal analysis etc. Mechanical properties were also measured.
