Responsibility of Bi2O3 Content in Photon, Alpha, Proton, Fast and Thermal Neutron Shielding Capacity and Elastic Moduli of ZnO/B2O3/Bi2O3 Glasses

2021 ◽  
Author(s):  
Y. S. Rammah ◽  
F. I. El-Agawany ◽  
A. Gamal ◽  
I. O. Olarinoye ◽  
Emad M. Ahmed ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Elastic Moduli ◽  
Neutron Shielding ◽  
Bi2o3 Content

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.

Potential use of NR and wood/NR composites as thermal neutron shielding materials

2017 ◽  
Vol 59 ◽  
pp. 336-343 ◽  
Author(s):  
Keeratikarn Ninyong ◽  
Ekachai Wimolmala ◽  
Narongrit Sombatsompop ◽  
Kiadtisak Saenboonruang
Keyword(s):  
Thermal Neutron ◽  
Neutron Shielding ◽  
Potential Use

Gamma-ray/neutron shielding capacity and elastic moduli of MnO–K2O–B2O3 glasses co-doped with Er3+ ions

2020 ◽  
Vol 126 (12) ◽  
Author(s):  
Y. S. Rammah ◽  
C. Mutuwong ◽  
El Sayed Yousef ◽  
Shoroog Alraddadi ◽  
M. S. Al-Buriahi
Keyword(s):  
Elastic Moduli ◽  
Gamma Ray ◽  
Neutron Shielding ◽  
Co Doped

scholarly journals Research on Thermal Neutron Shielding Performance of TiB2-Al Composite Materials

2021 ◽  
Author(s):  
Chao Wang ◽  
Zhefu Li ◽  
Mengge Dong ◽  
Lu Zhang ◽  
Jianxing Liu ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Cross Section ◽  
Neutron Fluence ◽  
Thermal Neutrons ◽  
Neutron Shielding ◽  
Preparation Methods ◽  
Neutron Fluence Rate ◽  
Maximum Value ◽  
Al Composite ◽  
Macroscopic Cross Section

<p>Although the various excellent properties and preparation methods of TiB<sub>2</sub>-based composites have been extensively studied, their neutron shielding properties have not received as much attention. In this article, the neutron shielding performance of the previously prepared TiB<sub>2</sub>-Al composite will be studied. The photo neutron source device was used to carry out neutron irradiation tests on test samples with a thickness of 10 mm. The average thermal neutron shielding rate of TiB<sub>2</sub>-based boron-containing composites is 17.55%, and the shielding rate increases with the increase of BN content. The macroscopic cross-section of thermal neutrons of the composites generally shows a stable trend, and when the BN content is 10%, the thermal neutrons macroscopic cross section reaches the maximum value of 7.58cm<sup>-1</sup>. With the increase of the BN content, the thermal neutron fluence rate shows a gradually decreasing trend.</p>

B4C/NRL flexible films for thermal neutron shielding

2018 ◽  
Vol 29 (2) ◽  
Author(s):  
Yi-Chuan Liao ◽  
Dui-Gong Xu ◽  
Peng-Cheng Zhang
Keyword(s):  
Thermal Neutron ◽  
Neutron Shielding ◽  
Flexible Films

scholarly journals Prompt Gamma based Detection and Discrimination of 2 Neutron Capture Events for NCEPT Dose 3 Quantification

2021 ◽  
Author(s):  
Andrew Chacon ◽  
Marissa Kielly ◽  
Harley Rutherford ◽  
Daniel R. Franklin ◽  
Anita Caracciolo ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Neutron Capture ◽  
False Positives ◽  
Particle Therapy ◽  
In Vivo Dosimetry ◽  
Prompt Gamma ◽  
Depth Range ◽  
Neutron Shielding ◽  
Monte Carlo Simulation Study

Abstract Neutron Capture Enhanced Particle Therapy (NCEPT) boosts the effectiveness of particle therapy by capturing thermal neutrons produced by beam-target nuclear interactions in and around the treatment site, using tumour-specific 10B or 157Gd-based neutron capture agents. Neutron captures release high-LET secondary particles together with prompt gamma photons with energies of 478 keV (10B) or 7.94 MeV (157Gd). A key requirement for NCEPT’s translation is the development of in vivo dosimetry techniques which can measure both the direct ion dose and the dose due to neutron capture. In this work, we report signatures which can be used to discriminate between photons resulting from neutron capture and those originating from other processes. A Geant4 Monte Carlo simulation study into timing and energy thresholds for discrimination of prompt gamma photons resulting from thermal neutron capture during NCEPT was conducted. Three simulated 300×300×300 mm3 cubic PMMA targets were irradiated by 4He or 12C ion beams with a spread out Bragg peak (SOBP) depth range of 60 mm; one target is homogeneous while the others include 10×10×10 mm3 neutron capture inserts (NCIs) of pure 10B or 157Gd located at the distal edge of the SOBP. The arrival times of photons and neutrons entering a simulated 50×50×50 mm3 ideal detector were recorded. The majority of photons resulting from neutron capture were found to arrive at the detector at least 60 ns later than photons created by other processes. A range of candidate detector and thermal neutron shielding materials were simulated, and detections meeting the proposed acceptance criteria (i.e. falling within the target energy window and arriving 60 ns post beam-off) were classified as true or false positives, depending on their origin. The ratio of true / false positives (RTF) was calculated; for targets with 10B and 157Gd NCIs, the detector materials which resulted in the highest RTF were cadmium-shielded CdTe and boron-shielded LSO, respectively. The optimal irradiation period for both carbon and helium ions was 1 µs for the 10B NCI and 1 ms for the 157Gd NCI.

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