The design, fabrication and properties of B4C/Al neutron absorbers

Zhang, Peng; Li, Yuli; Wang, Wenxian; Gao, Zhanping; Wang, Baodong

doi:10.1016/j.jnucmat.2013.02.050

Cited by 127 publications

(42 citation statements)

References 24 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Boron Carbide is a material with higher hardness than aluminum with the reading of 2.75 Mohs compared to 9.3 Mohs. Thus, the increase in the quantity of Boron Carbide in the composites increases the hardness of the Al/B 4 C composites [7].…”

Section: Introductionmentioning

confidence: 96%

Radiation Shielding Effect of Boron Carbide Aluminum Metal Matrix Composite

et al. 2015

View full text Add to dashboard Cite

Boralyn (Al/B4C) composite material is produced chiey 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 coecients were calculated. Theoretical mass attenuation coecients 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 coecient of materials

show abstract

Section: Introductionmentioning

confidence: 96%

Radiation Shielding Effect of Boron Carbide Aluminum Metal Matrix Composite

et al. 2015

View full text Add to dashboard Cite

show abstract

“…* corresponding author; e-mail: akkasayhan@hotmail.com Boron carbide is a material having a higher strength than aluminum with the reading of 2.75 Mohs compared to 9.3 Mohs. Thus, the increase in the quantity of boron carbide in the composites increases the strength of the Al/B 4 C composites [10].…”

Section: Introductionmentioning

confidence: 97%

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

et al. 2015

View full text Add to dashboard Cite

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.

show abstract

“…B 4 C possesses high melting point, super-hardness and the good absorbing neutron property, so it has become a major focus in nuclear shielding field [1][2][3]. The boron includes 10 B and 11 B isotopes, while the nuclear reaction only happened between the 10 B and neutron, and the reaction products form as lithium and helium [4,5]. The average natural abundance of 10 B in boron is 19.9% and the thermal neutron absorption cross-section is 3837b [5].…”

Section: Introductionmentioning

confidence: 99%

“…The boron includes 10 B and 11 B isotopes, while the nuclear reaction only happened between the 10 B and neutron, and the reaction products form as lithium and helium [4,5]. The average natural abundance of 10 B in boron is 19.9% and the thermal neutron absorption cross-section is 3837b [5]. Thus, B 4 C is a perfect neutron shielding material.…”

Section: Introductionmentioning

confidence: 99%