Investigation of Behaviour of Titanium Diboride Reinforced Boron Carbide-Silicon Carbide Composites against Cs-137 Gamma Radioisotope Source by Using Gamma Transmission Technique

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

Turkey Investigation of Grain Boundary Compositions and Magnetic Properties of Hot-Worked Nd 18 Tb 1 Fe 66

Magnetic properties which are related to the compositions on the grain boundaries of the NdFeB permanent magnets were studied at dierent hot working temperatures applied to the cast Nd18Tb1Fe66.5Co5Al1.5B8 ingots. Since the addition of Al caused the formation of hard magnetic µ phase between the magnetic NdFeB crystals after the pressing 800 • C Hc value increased to the highest value of 8.21 kOe. According to the SEM micrographs and EDS analysis, the increase in pressing temperature, the atomic ratios in the NdFeAl compositions approached to hard magnetic µ phase with the increase in pressing temperature and its exact composition was obtained in the sample hot deformed at 800 • C. Although the secondary µ phase with a high melting temperature is detremental to the alignment of c axis of the magnetic NdFeB grains along the pressing direction, we found that the magnetic properties of the magnets improve due to the presence of this hard magnetic phase on the grain boundaries

Gamma Attenuation Behavior of h-BN and h-BN-TiB 2

Hexagonal boron nitride (h-BN) and hexagonal boron nitride-titanium diboride (h-BN-$TiB_2$) composites are advanced materials for high-tech applications. They were investigated against gamma radioisotope sources Cs-137 and Co-60 which have gamma peaks 0.662 MeV for Cs-137, and 1.17 and 1.33 MeV for Co-60. Materials have been produced at 1800C temperature in argon atmosphere without pressure during 2 h time. Linear and mass attenuation coefficients were calculated for the materials. Gamma transmission technique was used in the experiments. The experimental investigated mass attenuation coefficients of the materials for Cs-137 and Co-60 gamma radioisotope sources were compared with XCOM computer code. For h-BN-$TiB_2$ composites the ratio of $TiB_2$ in the composites is 55% by weight. So gamma attenuation effects of adding $TiB_2$ to h-BN were discussed. It could be said that adding $TiB_2$ to h-BN increases the linear gamma attenuation of the samples

Gamma Attenuation Behavior of h-BN and h-BN-TiB2TiB_2 Composites

Hexagonal boron nitride (h-BN) and hexagonal boron nitride-titanium diboride (h-BN-$TiB_2$) composites are advanced materials for high-tech applications. They were investigated against gamma radioisotope sources Cs-137 and Co-60 which have gamma peaks 0.662 MeV for Cs-137, and 1.17 and 1.33 MeV for Co-60. Materials have been produced at 1800C temperature in argon atmosphere without pressure during 2 h time. Linear and mass attenuation coefficients were calculated for the materials. Gamma transmission technique was used in the experiments. The experimental investigated mass attenuation coefficients of the materials for Cs-137 and Co-60 gamma radioisotope sources were compared with XCOM computer code. For h-BN-$TiB_2$ composites the ratio of $TiB_2$ in the composites is 55% by weight. So gamma attenuation effects of adding $TiB_2$ to h-BN were discussed. It could be said that adding $TiB_2$ to h-BN increases the linear gamma attenuation of the samples

Radiation Shielding Effect of Boron Carbide Aluminum Metal Matrix Composite

Boralyn (Al/B₄C) composite material is produced chiefly of boron carbide and aluminum. Boron Carbide is an important material for the nuclear industry due to high neutron absorption cross-section. This composite is used as shielding materials to absorb neutrons in the nuclear reactors and control road materials. In this study we investigated Al/B₄C composites against gamma radiation. For that purpose, 5 wt.%, 10 wt.%, 15 wt.% and 20 wt.% reinforcement content were investigated. Cs-137 gamma radioisotope source which has 662 keV gamma energy photons were used. For each material, linear and mass attenuation coefficients were calculated. Theoretical mass attenuation coefficients were calculated from XCOM computer code. The theoretical results were compared with experimental results. The results were showed that increasing the amount of Boron Carbide compound content of boralyn composite material decrease the linear and mass attenuation coefficient of material

Shielding Effect of Boron Carbide Aluminium Metal Matrix Composite against Gamma and Neutron Radiation

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