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 ◽  
...  
2018 ◽  
Vol 1120 ◽  
pp. 012100
Author(s):  
Evi Christiani Sitepu ◽  
Timbangen Sembiring ◽  
Kerista Sebayang ◽  
Iwan Sumirat

2012 ◽  
Vol 535-537 ◽  
pp. 1877-1880 ◽  
Author(s):  
Mohd Reusmaazran Yusof ◽  
Yusof Abdullah ◽  
Zaifol Samsu

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.


2019 ◽  
Vol 36 (1) ◽  
pp. 19-21
Author(s):  
Rini Murtafi'atin ◽  
Widarto Widarto ◽  
Susilo Susilo ◽  
Ngurah Made Dharma Putra

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.


2018 ◽  
Vol 9 (08) ◽  
pp. 20193-20206 ◽  
Author(s):  
Md. Akhlak Bin Aziz ◽  
Md. Faisal Rahman ◽  
Md. Mahidul Haque Prodhan

The paper compares  Lead, Copper and Aluminium as gamma radiation shielding material using both experimental and simulation techniques. Cs- 137 (662KeV), Na-22 (511KeV) and Na- 22(1274KeV) were used as gamma radiation sources and a sodium iodide (NaI) detector was used to detect the radiation. Variations were noted for detected gamma count rates by changing shielding material thickness. In the experimental approach, thickness was varied by placing sheets of a particular test material one by one. For simulation, Monte Carlo n- Particle (MCNP) code version 4c was used and the geometry of the whole experimental setup was plotted in it. The results were then compared for each test material and it was found that lead is the best shielding material for gamma radiation followed by copper and aluminium.


2021 ◽  
Vol 11 (9) ◽  
pp. 4010
Author(s):  
Seon-Chil Kim

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.


2021 ◽  
pp. 109851
Author(s):  
Sungwon Sim ◽  
Dongho Jeon ◽  
Do Hoon Kim ◽  
Woo sung Yum ◽  
Seyoon Yoon ◽  
...  

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

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