Study of the Effect of Boron Carbide Content in Concrete as Radiation Shielding Application

2012 ◽  
Vol 535-537 ◽  
pp. 1877-1880 ◽  
Author(s):  
Mohd Reusmaazran Yusof ◽  
Yusof Abdullah ◽  
Zaifol Samsu
Keyword(s):  
Boron Carbide ◽  
Thermal Neutron ◽  
Attenuation Coefficient ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Fine Aggregates ◽  
Neutron Attenuation ◽  
Result Show ◽  
Boron Carbide B4c ◽  
Carbide Content

Keywords: Boron carbide, concrete, shielding, neutron, attenuation. Abstract. Boron carbide (B4C) is a ceramic material which is effectively absorb thermal neutron due to wide neutron absorption cross section. In this work, B4C is added into concrete as fine aggregates to test the attenuation properties by getting the attenuation coefficient of the concrete/ B4C. The samples of concrete/ B4C were exposing to the thermal neutron radiation source (241-Americium-Berylium) at the dose rate of 29.08 mR/h. The result show that the attenuation coefficient of the sample with 20wt% B4C is 0.299 cm-1 and the sample without B4C is 0.238 cm-1 and hence, concrete/ B4C is suitable as a shielded for thermal neutron radiation.

scholarly journals Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities

2019 ◽  
Vol 36 (1) ◽  
pp. 19-21
Author(s):  
Rini Murtafi'atin ◽  
Widarto Widarto ◽  
Susilo Susilo ◽  
Ngurah Made Dharma Putra
Keyword(s):  
Attenuation Coefficient ◽  
Germanium Detector ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Radiation Level ◽  
Boron Neutron Capture ◽  
Neutron Attenuation ◽  
Density Analysis ◽  
Shielding Material

This research aimed to determine the potential of barite concrete as a neutron radiation shielding material in the development of boron neutron capture therapy, by obtaining its neutron attenuation coefficient. Barite concrete samples were supplied by the Center of Accelerator Science and Technology in Yogyakarta, Indonesia. The experiment consisted of two parts, namely density analysis and determination of the neutron attenuation coefficient. For the latter, plutonium-beryllium was used as the neutron source, while a high purity germanium detector was used to measure the neutron radiation level. The results showed that barite concrete with a 2130 kg.m–3 density had a neutron attenuation coefficient of 0.0871 cm–3.

scholarly journals A study of the use of palm fiber and palm shell as a thermal neutron radiation shielding material

2019 ◽  
Vol 14 ◽  
pp. 100468 ◽  
Author(s):  
Evi Christiani Sitepu ◽  
Timbangen Sembiring ◽  
Kerista Sebayang ◽  
Iwan Sumirat ◽  
Martha Rianna ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Palm Fiber ◽  
Palm Shell ◽  
Shielding Material

Processing and properties of boron carbide (B4C) reinforced LDPE composites for radiation shielding

2020 ◽  
Vol 46 (1) ◽  
pp. 343-352 ◽  
Author(s):  
Suna Avcıoğlu ◽  
Merve Buldu ◽  
Figen Kaya ◽  
Cem Bülent Üstündağ ◽  
Erol Kam ◽  
...  
Keyword(s):  
Boron Carbide ◽  
Radiation Shielding ◽  
Ldpe Composites ◽  
Boron Carbide B4c

High temperature resistant polyimide/boron carbide composites for neutron radiation shielding

2019 ◽  
Vol 159 ◽  
pp. 355-361 ◽  
Author(s):  
Xiaomin Li ◽  
Juying Wu ◽  
Changyu Tang ◽  
Zhoukun He ◽  
Ping Yuan ◽  
...  
Keyword(s):  
High Temperature ◽  
Boron Carbide ◽  
Neutron Radiation ◽  
Radiation Shielding

scholarly journals The Effect of Thermal Neutron Radiation on the Chromosomes of Datura

1953 ◽  
Vol 39 (4) ◽  
pp. 292-297 ◽  
Author(s):  
H. T. Yost ◽  
W. R. Singleton ◽  
A. F. Blakeslee
Keyword(s):  
Thermal Neutron ◽  
Neutron Radiation
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