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Investigation on the Effects of Boron Carbide Particle Size on Radiation Shielding Properties of Boron Carbide-Titanium Diboride Composites

100%
Buyuk B., Tugrul A., Aktop S., Addemir A.
Acta Physica Polonica A
|
2013
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vol. 123
|
issue 2
177-179
EN
Boron carbide is a material which has wide application areas in industry including nuclear technology. Titanium diboride-boron carbide composites which were produced from different boron carbide particle sizes were studied for searching of the behaviour against the gamma ray. Micron size and submicron size boron carbide were used to produce composite materials. The volume of boron carbide and titanium diboride in the composites are 85% and 15%, respectively. For the investigation of the gamma radiation behaviour of these materials, Cs-137 radioisotope was used as gamma source in the experiments which has a single gamma-peak at 0.662 MeV. Gamma transmission technique was used for the measurements. The effects of boron carbide particle size on radiation attenuation of titanium diboride-boron carbide composites were evaluated in relation with gamma transmission and the results of the experiments were interpreted and compared with each other. It could be understood that decrease of particle size of boron carbide in boron carbide-titanium diboride composites causes higher linear and mass attenuation coefficient values. So, submicron size boron carbide used composite materials are more convenient than micron size boron carbide used composite materials as radiation shielding materials for nuclear applications.
2
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Investigation of Behaviour of Titanium Diboride Reinforced Boron Carbide-Silicon Carbide Composites against Cs-137 Gamma Radioisotope Source by Using Gamma Transmission Technique

100%
Buyuk B., Tugrul A., Akarsu A., Addemir A.
Acta Physica Polonica A
|
2012
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vol. 121
|
issue 1
135-137
EN
Boron carbide is a material which has wide application areas in industry including nuclear technology. Titanium diboride reinforced boron carbide-silicon carbide composites were studied for searching of the behaviour against the gamma ray. It has been adopted that depending on their properties such improved materials can be used in nuclear technology. For the investigation of the gamma radiation behaviour of these materials, Cs-137 radioisotope was used as gamma source in the experiments which have a single gamma-peak at 0.662 MeV. Gamma transmission technique was used for the measurements. Different reinforcing ratios, titanium diboride reinforced boron carbide-silicon carbide composites were evaluated in relation to gamma transmission and the results of the experiments were interpreted and compared with each other. It could be understood that the increasing ratio of titanium diboride in boron carbide-silicon carbide composites causes higher hardness, strength and linear attenuation coefficient values but decrease the mass attenuation coefficient.
3
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Shielding Effect of Boron Carbide Aluminium Metal Matrix Composite against Gamma and Neutron Radiation

76%
Akkas A., Tugrul A., Buyuk B., Addemir A., Marsoglu M., Agacan B.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-176-B-179
EN
In this study, boralyn (boron carbide-aluminum metal matrix composite material - Al/B₄C) composite materials were investigated on shielding effect against gamma and neutron radiations. The samples were prepared as 5 wt%, 10 wt%, 15 wt%, and 20 wt% reinforcement content and for each content of material has composed in five different average particle sized (3 μm, 53 μm, 113 μm, 200 μm, and 500 μm). Linear and mass attenuation coefficients were calculated experimentally for each composite material against Cs-137 gamma source. Theoretical mass attenuation coefficients of material were calculated by using XCOM computer code. Then the theoretical results were compared with experimental results. Then, macroscopic cross-section values were calculated experimentally for each composite material against Pu-Be neutron source. As the conclusion of the study, it could be understood that in spite of decrease of the attenuation coefficient against gamma radiation, the adding materials give rise to increase the shielding ability of material against neutron radiation.
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