Effect of particle size and percentages of Boron carbide on the thermal neutron radiation shielding properties of HDPE/B4C composite: Experimental and simulation studies

2016 ◽  
Vol 127 ◽  
pp. 182-187 ◽  
Author(s):  
Zahra Soltani ◽  
Amirmohammad Beigzadeh ◽  
Farhood Ziaie ◽  
Eskandar Asadi
Keyword(s):  
Particle Size ◽  
Boron Carbide ◽  
Thermal Neutron ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Simulation Studies ◽  
Effect Of Particle Size ◽  
Shielding Properties

The effect of particle size on radiation shielding properties for bismuth borosilicate glass

2020 ◽  
Vol 172 ◽  
pp. 108791 ◽  
Author(s):  
W. Cheewasukhanont ◽  
P. Limkitjaroenporn ◽  
S. Kothan ◽  
C. Kedkaew ◽  
J. Kaewkhao
Keyword(s):  
Particle Size ◽  
Borosilicate Glass ◽  
Radiation Shielding ◽  
Effect Of Particle Size ◽  
Shielding Properties

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 Shielding Performance of Radiation-Shielding Materials According to Particle Size and Clustering Effects

2021 ◽  
Vol 11 (9) ◽  
pp. 4010
Author(s):  
Seon-Chil Kim
Keyword(s):  
Particle Size ◽  
Polymer Material ◽  
Energy Region ◽  
High Energy ◽  
Radiation Shielding ◽  
High Energy Region ◽  
Particle Structure ◽  
Effect Of Particle Size ◽  
Extensive Body ◽  
Shielding Material

In the field of medical radiation shielding, there is an extensive body of research on process technologies for ecofriendly shielding materials that could replace lead. In particular, the particle size and arrangement of the shielding material when blended with a polymer material affect shielding performance. In this study, we observed how the particle size of the shielding material affects shielding performance. Performance and particle structure were observed for every shielding sheet, which were fabricated by mixing microparticles and nanoparticles with a polymer material using the same process. We observed that the smaller the particle size was, the higher both the clustering and shielding effects in the high-energy region. Thus, shielding performance can be improved. In the low-dose region, the effect of particle size on shielding performance was insignificant. Moreover, the shielding sheet in which nanoparticles and microsized particles were mixed showed similar performance to that of the shielding sheet containing only microsized particles. Findings indicate that, when fabricating a shielding sheet using a polymer material, the smaller the particles in the high-energy region are, the better the shielding performance is. However, in the low-energy region, the effect of the particles is insignificant.

Effect of addition of molybdenum on photon and fast neutron radiation shielding properties in ceramics

2019 ◽  
Vol 45 (17) ◽  
pp. 23681-23689 ◽  
Author(s):  
Berna Oto ◽  
Esra Kavaz ◽  
Halil Durak ◽  
Aydın Aras ◽  
Zekiye Madak
Keyword(s):  
Fast Neutron ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Shielding Properties

scholarly journals New Composite Material Based on Heavy Concrete and Basalt-Boron Fiber for Neutron Radiation Shielding Properties

2019 ◽  
pp. 19-25 ◽  
Author(s):  
I. Romanenko ◽  
M. Holiuk ◽  
A. Nosovsky ◽  
T. Vlasenko ◽  
V. Gulik
Keyword(s):  
Composite Material ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Nuclear Industry ◽  
Protective Properties ◽  
Horizon 2020 ◽  
Boron Fiber ◽  
Fast Fission ◽  
Fission Neutrons ◽  
Shielding Properties

It is necessary to have reliable radiation protection for safe operation of different radiation sources. Radiation shielding properties have been studied for a long time both in our country and abroad. However, there is a strong necessity to develop new composite materials, which will provide protection against radiation and have improved mechanical and economic characteristics. The paper describes a new composite material for neutron radiation shielding properties based on heavy concrete with serpentinite aggregate and with basalt-boron fiber with different concentrations of fiber boron oxide for using in biological shielding in nuclear industry. Protective properties of the new composite material were investigated with different neutron sources: 1) neutrons with 14 MeV energy; 2) fast fission neutrons for U-235; 3) fast fission neutrons for U-235 after passing a water layer. The simulation of the neutron radiation in presented composite material with adding crushed stone aggregate and serpentinite aggregate is performed by Monte Carlo Serpent code. It is shown that basalt-boron fibers in concrete improve the protective properties of concrete against neutron irradiation for neutrons with different energies, but the most effective is the addition of a basalt-boron fiber in the case of thermal neutrons. This research was supported by Horizon 2020 ERA-NET Support Programme, Research Grant Agreement No 7.9-3/18/7 (“Development of Boron-Infused Basalt-Fiber Reinforced Concrete for Nuclear and Radioactive Waste Management Applications”). Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a joint programme of the members of the EUROfusion consortium (2014-2020), Work Package PMI. Also, this research was carried out with the financial support of the IAEA, within the terms and conditions of the Research Contract20638 in the framework of the Coordinated Research Project (CRP) “Accelerator Driven Systems (ADS) Applications and Use of Low-Enriched Uranium in ADS (T33002)’’ within the Project “The Two-Zone Subcritical Systems with Fast and Thermal Neutron Spectra for Transmutation of Minor Actinides and Long-Lived Fission Products”.

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
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