Thermally insulating GdBO 3 ceramics with neutron shielding performance

2021 ◽  
Author(s):  
Cheng Dong ◽  
Yuanbing Li ◽  
Shujing Li ◽  
Wenbao Jia ◽  
Ruoyu Chen ◽  
...  
Keyword(s):  
Neutron Shielding

scholarly journals Enhancement of the Shielding Capability of Soda–Lime Glasses with Sb2O3 Dopant: A Potential Material for Radiation Safety in Nuclear Installations

2020 ◽  
Vol 11 (1) ◽  
pp. 326
Author(s):  
M.I. Sayyed ◽  
K.A. Mahmoud ◽  
O.L. Tashlykov ◽  
Mayeen Uddin Khandaker ◽  
M.R.I. Faruque
Keyword(s):  
Attenuation Coefficient ◽  
Elastic Moduli ◽  
Gamma Ray ◽  
Radiation Safety ◽  
Soda Lime ◽  
Mass Attenuation Coefficient ◽  
Transmission Factor ◽  
Linear Attenuation Coefficient ◽  
Neutron Shielding ◽  
Removal Cross Section

Elastic moduli were theoretically computed using the Makishima–Mackenzie model for SiO2–Na2O–CaO glasses doped with Sb2O3 contents. The calculated elastic moduli (Young’s, bulk, shear, and longitudinal modulus) were observed to increase with an increase in the Sb2O3 contents. The microhardness showed an increase, while Poisson’s ratio decreased with the rise of the Sb2O3 contents. In addition, gamma-ray and neutron shielding parameters were evaluated for the investigated glasses. The linear attenuation coefficient (LAC) was simulated using the Monte Carlo N-particle transport code (MCNP-5). Other parameters, such as the mass attenuation coefficient (MAC), transmission factor (TF), and half-value layer, were calculated based on the simulated LAC. The addition of Sb2O3 content was observed to enhance the investigated glasses’ shielding parameters, where the highest LAC was achieved for the SCNSb10 glass with 10 mol% Sb2O3 and decreased from 0.441 to 0.154 cm−1 at gamma energies between 0.248 and 1.406 MeV. Furthermore, the fast neutron effective removal cross-section (∑R) was computed theoretically. The calculated results showed that the highest ∑R was equal to 0.0341 cm2g−1 and was obtained for the SCNSb0 glass, which had no Sb2O3 content, while the lowest ∑R was equal to 0.0286 cm2 g−1 for the SCNSb10 glass sample. The present work was carried out to examine the advantages of the soda–lime glasses with different Sb2O3 contents in several photon shielding applications, especially for radiation safety in nuclear installations.

Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding

2020 ◽  
Vol 0 (0) ◽  
Author(s):  
Bünyamin Aygün ◽  
Erdem Şakar ◽  
Abdulhalik Karabulut ◽  
Bünyamin Alım ◽  
Mohammed I. Sayyed ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Fast Neutron ◽  
Cross Sections ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Effective Neutron ◽  
Simulation Codes

AbstractIn this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.

New Neutron Shielding in the Edelweiss-III Experiment

2014 ◽  
Vol 176 (5-6) ◽  
pp. 995-1001
Author(s):  
X.-F. Navick ◽  
Keyword(s):  
Neutron Shielding

Experimental Research on Peridotite Concrete for Neutron Shielding

2013 ◽  
Vol 423-426 ◽  
pp. 1031-1035
Author(s):  
Jin Jun Wang ◽  
Guo Feng Li ◽  
De Chuan Meng
Keyword(s):  
Neutron Shielding ◽  
Crystal Water ◽  
Concrete Aggregates ◽  
Mix Proportion ◽  
Concrete Mix ◽  
Energy Neutron ◽  
Transmission Data ◽  
Shielding Material ◽  
Different Thickness ◽  
Thermal Stability Of

Peridotite containing high crystal water is used as concrete aggregates in this research. The mineral composition and thermal stability of peridotite are experimentally analyzed, and the concrete mix proportion design is optimized. The neutron shielding performance of peridotite concrete specimens are tested using 241Am-Be neutron source. The transmission data of different thickness and different energy neutron are calculated. It concludes that peridotite concrete has a good performance in neutron shielding and peridotite is an excellent neutron shielding material.

Neutron Shielding of Underground Nuclear Explosives

1971 ◽  
Vol 11 (3) ◽  
pp. 357-366 ◽  
Author(s):  
Joseph B. Green ◽  
Richard M. Lessler
Keyword(s):  
Neutron Shielding
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