scholarly journals Investigation of fast neutron shielding properties of new polyurethane-based composites loaded with B4C, BeO, WO3, ZnO, and Gd2O3 micro-and nanoparticles

2019 ◽  
Vol 25 (4) ◽  
pp. 211-219 ◽  
Author(s):  
Asghar Mesbahi ◽  
Khatibeh Verdipoor ◽  
Farhad Zolfagharpour ◽  
Abdolali Alemi
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
Neutron Cross Section ◽  
Radiation Shielding ◽  
Fast Neutrons ◽  
Nano Composites ◽  
Monte Carlo Code ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Polyurethane Matrix

Abstract The aim of the current research was to study the radiation shielding properties of polyurethane-based shielding materials filled with B4C, BeO, WO3, ZnO, and Gd2O3 particles against fast neutrons. The macroscopic cross sections of composites containing micro- and nanoparticles with a diameter of 10 µm and 50 nm were calculated using MCNPX (2.6.0) Monte Carlo code. The results showed that adding nano-scaled fillers to polyurethane matrix increases attenuation properties of neutron shields compared to micro-scaled fillers for intermediate and fast neutrons. Among the studied composites, WO3 and Gd2O3 nano-composites presented higher neutron cross section compared to others.

scholarly journals Fast Neutron and Gamma-Ray Attenuation Properties of Some HMO Tellurite-Tungstate-Antimonate Glasses: Impact of Sm3+ Ions

2021 ◽  
Vol 11 (21) ◽  
pp. 10168
Author(s):  
Ghada ALMisned ◽  
Huseyin O. Tekin ◽  
Hesham M. H. Zakaly ◽  
Shams A. M. Issa ◽  
Gokhan Kilic ◽  
...  
Keyword(s):  
Cross Section ◽  
Radiation Shielding ◽  
Fast Neutrons ◽  
Monte Carlo Code ◽  
Attenuation Coefficients ◽  
Effective Removal ◽  
Removal Cross Section ◽  
Mass Attenuation Coefficients ◽  
Shielding Properties ◽  
Mass Attenuation

Characteristics of tellurite-tungstate-antimonate glasses containing heavy metal oxide were investigated in detail using two methods: the MCNPX Monte Carlo code and the Phy-X/PSD platform. The influence of Sm2O3, translocating with TeO2 at ratios of 0.2, 0.5, 0.8, 1, and 1.5 mol% on radiation shielding properties of glasses, was set forth with five glass structures determined according to the (75-x)TeO2-15Sb2O3-10WO3-xSm2O3 glass composition. Densities of the glasses were prepared by doping a low ratio of Sm2O3 that varied between 5.834 and 5.898 g/cm3. Sample densities, which have an important role in determining radiation shielding character, increased depending on the increase in Sm2O3 concentration. Effective removal cross-section (∑R) values against fast neutrons, as well as linear and mass attenuation coefficients, half-value layer, mean free path, variation of effective atomic number against photon energy, exposure, and energy built-up factors, were simulated with the help of these two methods. As a result of these estimates, it can be concluded that values obtained using both methods are consistent with each other. From the obtained values, it can be concluded that the SM1.5 sample containing 1.5 mol% would have the most efficient role in radiation shielding. An increase of Sm2O3 resulted in a significant increase in linear and mass attenuation coefficients and effective removal cross-section values belonging to fast neutrons and, in addition, resulted in a decrease in the half value layer. Doping HMO glasses with Sm2O3 was observed to contribute directly to the development of radiation shielding properties of the glass.

scholarly journals Investigations of gamma ray and fast neutron shielding properties of tellurite glasses with different oxide compositions

2016 ◽  
Vol 94 (11) ◽  
pp. 1133-1137 ◽  
Author(s):  
M.I. Sayyed
Keyword(s):  
Photon Energy ◽  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Fast Neutrons ◽  
Tellurite Glasses ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Mass Attenuation

In the present paper, the basic radiation parameters of tellurite glasses with different forming oxides (B2O3, BaO, K2O, V2O5, WO3, and ZnO) have been studied over a wide photon energy range from 1 keV to 100 GeV, using WinXCom program. These parameters are the mass attenuation coefficient (μ/ρ), effective atomic number (Zeff), and electron density (Ne,eff). In addition, the macroscopic effective removal cross sections (ΣR) for fast neutrons have been calculated. The dependence of different parameters on incident photon energy and chemical content has been discussed. Among the selected glass systems TeO2–WO3 and TeO2–B2O3 showed superior shielding properties for gamma-ray and neutrons, respectively. It is shown that the selected glass systems have higher values of the mass attenuation coefficients (μ/ρ) than concretes and 0.7SiO2:0.3BaO glass. These results indicate that tellurite glasses can be used as radiation shielding materials.

scholarly journals The Impact of PbF2-Based Glasses on Radiation Shielding and Mechanical Concepts: An Extensive Theoretical and Monte Carlo Simulation Study

2021 ◽  
Author(s):  
A. El-Denglawey ◽  
Shams A.M. Issa ◽  
Yasser B. Saddeek ◽  
Huseyin O. Tekin ◽  
Hesham M.H. Zakaly
Keyword(s):  
Monte Carlo ◽  
Cross Sections ◽  
Radiation Shielding ◽  
Fast Neutrons ◽  
Monte Carlo Code ◽  
Lead Fluoride ◽  
Monte Carlo Simulation Study ◽  
Simulation Techniques ◽  
Quenching Method ◽  
The Impact

Abstract This work aimed to investigate the impact of Lead-fluoride based glasses via theoretical and simulation techniques on mechanical and radiation shielding parameters. Accordingly, a glass composition PbF2 blended with TeO2-B2O3-Bi2O3 glasses were synthesised by using melt-quenching method. Using Fluka Monte Carlo code, the radiation shielding properties have measured. Moreover. Comparatively higher density PbF80= 6.163g/cm3 with 80 mol % Bi2O3, greater µ, µm and Zeff and lower T1/2, l, tenth value layer values achieved for TeO2-B2O3-Bi2O3/PbF2 glass pointed it out as the best shield of gamma. Besides, the computed effective removal cross-sections against fast neutrons (ΣR) observed that the PbF80 sample has commensurately greater with value 5.2954 (cm-1) The results observed that the variation Bi2O3/PbF2 improves the gamma protection ability of Lead-fluoride based glasses. The longitudinal modulus-L, shear modulus-S, bulk modulus-K, and Young’s modulus-Y raised from 15.89 to 25.9 -GPa, from 8.49 to 12.09 -GPa, from 4.58 to 9.77 -GPa, and from 15.74 to 25.69 -GPa, respectively. The results indicate that the highest Bi2O3/PbF2 ratio encoded PbF80 has the best shielding and mechanical competence with measurable physical properties.

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.

Simulating the radiation shielding properties of TeO2–Na2O–TiO glass system using PHITS Monte Carlo code

2021 ◽  
Vol 196 ◽  
pp. 110566
Author(s):  
Jamila S. Alzahrani ◽  
Miysoon A. Alothman ◽  
Canel Eke ◽  
Hanan Al-Ghamdi ◽  
Dalal Abdulldh Aloraini ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Radiation Shielding ◽  
Glass System ◽  
Monte Carlo Code ◽  
Shielding Properties

scholarly journals Are Further Cross Section Measurements Necessary for Space Radiation Protection or Ion Therapy Applications? Helium Projectiles

2020 ◽  
Vol 8 ◽  
Author(s):  
John W. Norbury ◽  
Giuseppe Battistoni ◽  
Judith Besuglow ◽  
Luca Bocchini ◽  
Daria Boscolo ◽  
...  
Keyword(s):  
Radiation Protection ◽  
Cross Section ◽  
Cross Sections ◽  
Nuclear Reactions ◽  
Production Cross ◽  
Cosmic Ray ◽  
Space Radiation ◽  
Radiation Shielding ◽  
Light Ions ◽  
Ion Therapy

The helium (4He) component of the primary particles in the galactic cosmic ray spectrum makes significant contributions to the total astronaut radiation exposure. 4He ions are also desirable for direct applications in ion therapy. They contribute smaller projectile fragmentation than carbon (12C) ions and smaller lateral beam spreading than protons. Space radiation protection and ion therapy applications need reliable nuclear reaction models and transport codes for energetic particles in matter. Neutrons and light ions (1H, 2H, 3H, 3He, and 4He) are the most important secondary particles produced in space radiation and ion therapy nuclear reactions; these particles penetrate deeply and make large contributions to dose equivalent. Since neutrons and light ions may scatter at large angles, double differential cross sections are required by transport codes that propagate radiation fields through radiation shielding and human tissue. This work will review the importance of 4He projectiles to space radiation and ion therapy, and outline the present status of neutron and light ion production cross section measurements and modeling, with recommendations for future needs.

The Thermal Neutron Cross Section and the Resonance Integral of 184Os, 190Os, 192Os, 64Zn, 68Zn and 59Co

1968 ◽  
Vol 9 (2-3) ◽  
Author(s):  
J. I. Kim ◽  
F. Adams
Keyword(s):  
Neutron Activation ◽  
Thermal Neutron ◽  
Cross Section ◽  
Cross Sections ◽  
Neutron Cross Section ◽  
Resonance Integral ◽  
Activation Measurement ◽  
Thermal Neutron Cross Section ◽  
Neutron Cross Sections

SummaryBy neutron activation measurement with a cadmium filter, using gold as a standard monitor, the thermal neutron cross sections and the resonance integrals of

Cross section measurements for the reactions of fast neutrons with indium

1976 ◽  
Vol 54 (7) ◽  
pp. 757-765 ◽  
Author(s):  
D. C. Santry ◽  
J. P. Butler
Keyword(s):  
Neutron Flux ◽  
Cross Section ◽  
Neutron Spectrum ◽  
Cross Sections ◽  
Fission Neutron ◽  
Activation Method ◽  
Fast Neutrons ◽  
Fission Neutron Spectrum

Excitation curves for the reactions 115In(n,n′) 115Inm, 113In(n,n′)113Inm, and 115In(n,2n)114Inm have been measured by the activation method. The neutron flux at energies below 5.1 MeV was determined with a calibrated neutron long counter while at higher energies, measurements were made relative to the known cross section for the 32S(n,p) reaction. Effective cross sections for a 235U fission-neutron spectrum calculated from our measured excitation curves are 173 ± 9 mb for 115In(n,n′)115Inm, 123 ± 24 mb for 113In(n,n′)113Inm, and 0.64 ± 0.06 mb for 115In(n,2n)114Inm.

scholarly journals nxs: a program library for neutron cross section calculations

2012 ◽  
Vol 45 (3) ◽  
pp. 603-607 ◽  
Author(s):  
Mirko Boin
Keyword(s):  
Crystal Structure ◽  
Instrument Development ◽  
Cross Section ◽  
Graphical User Interface ◽  
Cross Sections ◽  
Neutron Cross Section ◽  
Absorption Cross ◽  
Program Library ◽  
Imaging Experiment ◽  
Experiment Validation

A collection of routines for calculating neutron scattering and absorption cross sections on the basis of crystal structure descriptions is presented and implemented in the new and reusablenxsprogram library. An example program providing a graphical user interface to thenxsfunctions is created to demonstrate their usage. The flexibility of the library and the possibilities for multiple areas of application are shown by further examples involving Monte Carlo neutron simulations concerned with imaging experiment validation and neutron instrument development.

scholarly journals Resonance phenomena in the interaction of fast neutrons with beryllium and aluminium

1947 ◽  
Vol 192 (1028) ◽  
pp. 114-127 ◽  
Keyword(s):  
Energy Level ◽  
Cross Section ◽  
Neutron Energy ◽  
Cross Sections ◽  
Accurate Determination ◽  
Fast Neutrons ◽  
Transmission Method ◽  
The Cross ◽  
Scattering Cross Sections

The total scattering cross-sections of beryllium and aluminium have been measured by a transmission method for neutrons of energies between 0∙35 and 0∙55 MeV and 1∙8 and 4∙0 MeV. Resonances have been found in the scattering by beryllium at a neutron energy of 2∙6 MeV and in the scattering by aluminium at neutron energies of 2∙4 and 2∙9 MeV. It has been shown that the cross-section for the reaction 9 Be ( n , α ) 6 He also has a resonance at 2∙6 MeV, and an accurate determination of the cross-section for this reaction has been made. A discussion is given of the properties of the energy level in 10 Be responsible for the resonances in the case of beryllium.

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