Polyimide nanocomposites in ternary structure: “A novel simultaneous neutron and gamma‐ray shielding material”

2020 ◽  
Vol 31 (11) ◽  
pp. 2466-2479
Author(s):  
Oktay Baykara ◽  
Şerife G. İrim ◽  
Abdulmounem A. Wis ◽  
Mustafa A. Keskin ◽  
Guralp Ozkoc ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Shielding Material ◽  
Ternary Structure

A novel comprehensive utilization of vanadium slag: As gamma ray shielding material

2016 ◽  
Vol 318 ◽  
pp. 751-757 ◽  
Author(s):  
Mengge Dong ◽  
Xiangxin Xue ◽  
He Yang ◽  
Dong Liu ◽  
Chao Wang ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Vanadium Slag ◽  
Comprehensive Utilization ◽  
Shielding Material

scholarly journals Calculation of Gamma-ray Attenuation Parameters for Locally Developed Ilmenite-magnetite (I-M) Concrete

2016 ◽  
Vol 40 (1) ◽  
pp. 11-21 ◽  
Author(s):  
Md Hossain Sahadath ◽  
Ripan Biswas ◽  
Md Fazlul Huq ◽  
Abdus Sattar Mollah
Keyword(s):  
Computer Program ◽  
Gamma Ray ◽  
Attenuation Coefficients ◽  
Wide Range ◽  
Gamma Ray Attenuation ◽  
Mass Attenuation Coefficients ◽  
Shielding Properties ◽  
Academy Of Sciences ◽  
Shielding Material ◽  
Good Agreement

The mass attenuation coefficients (?/?) of locally developed ilmenite-magnetite (I-M) concrete over a wide range of photon energy were calculated analytically using Matlab and compared with the values obtained from widely used XCom computer program. A good agreement between the calculated and XCom generated value was found. The linear attenuation coefficients and relaxation lengths were calculated for the same energy range. The transmission curves were drawn for some common gamma-ray energies and half value layer and tenth value layer were calculated. The results of this study will provide some useful information about the shielding material data base for practical shielding calculation. The results will also illustrate the effectiveness of I-M concrete so far as its shielding properties are concerned.Journal of Bangladesh Academy of Sciences, Vol. 40, No. 1, 11-21, 2016

scholarly journals Impact of B2O3 on Physical, Optical Characteristics and Radiation Attenuation Factors of Borotellurite Glasses

2022 ◽  
Author(s):  
R. El-Mallawany ◽  
Weam aboutaleb ◽  
M.A. Naeem ◽  
S.M. Kotb ◽  
M.E. Krar ◽  
...  
Keyword(s):  
Photon Energy ◽  
Gamma Ray ◽  
Wave Length ◽  
Effective Atomic Number ◽  
Uv Spectra ◽  
Physical Parameters ◽  
Simulation Code ◽  
Optical Energy Band Gap ◽  
Removal Cross Section ◽  
Shielding Material

Abstract Borotellurite glasses with a composition [(60-X)TeO2-(20+X)B2O3-10Li2O-10Bi2O3] where x= 5-20 in steps of 5 mol% have been synthesized. Glass density, molar volume, oxygen packing density, and many other physical parameters were measured. UV-spectra in the wave length range (200-800) nm have been measured for the whole glass series. The optical energy band gap Eopt , refractive index, and optical basicity were measured. The mass absorption coefficients (μm) are determined experimentally by the HPGe detector and compared with the theoretical values obtained by XCOM program and MCNP5 simulation code within (0.121–1.408) MeV photon energy range. Half value layer (HVL), effective atomic number and electron density (Zeff and Neff), and macroscopic removal cross-section (∑R) were evaluated. The sample [55TeO2 – 25B2O3 – 10Bi2O3 – 10Li2O] possess the highest values of (μm = 1.192 ± 0.033 cm2/g, Zeff = 56.12 e/atom and ∑ R = 0.101499 cm-1) at energy 121 keV also lower values of (HVL = 0.121 cm, TVL = 0.1 cm and MFP = 0.174 cm) at photon energy 121 keV, therefore this sample considered the best gamma ray shielding material among the prepared glasses.

scholarly journals MODIFIED BORON-TITANIUM AUSTENITIC STAINLESS-STEEL ALLOYS FOR POWER REACTORS

2020 ◽  
Vol 5 (6) ◽  
pp. 87-95 ◽  
Author(s):  
Shaimaa Hafez ◽  
M.M. Eissa ◽  
S.U. El-Kameesy ◽  
R.M. Elshazly ◽  
M.K. El Fawkhry ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Cross Sections ◽  
Nuclear Reactor ◽  
Gamma Ray ◽  
Impact Testing ◽  
Austenitic Phase ◽  
Steel Alloys ◽  
Microstructure Observation ◽  
Shielding Material ◽  
Slow Neutrons

Boron, Titanium and boron – titaniumaustenitic stainless steel alloys were developed to be used as a nuclear reactor shielding material. Three grades of steel alloys with base composition of AISI316 but having either Ti or B or Ti and B (SS316Ti, SS316B and SS316TiB) were designed and produced using 30 kg pilot plant medium frequency induction furnace at the same conditions. Samples of the properly treated steels were subjected to microstructure observation, hardness, tensile and impact testing. The microstructure observation revealed an austenitic phase in all investigated steel alloys. Among the investigated steels, the lowest corrosion rate was found in the modified steel containing B. The macroscopic-cross sections for neutrons > 10 keV, slow, and total slow neutrons were carried out using 241Am-Be neutron source. The developed boron and boron-titanium stainless steel alloys were found to have higher cross sections for neutrons > 10 keV, slow, and total slow neutrons than SS316 while the modified Ti- stainless steel has lower values for slow neutrons and neutrons > 10 keV than the standard stainless steel SS316. Moreover, the associated neutron half value layer (HVL) was calculated for each sample. Additionally, gamma ray shielding properties were performed for several gamma ray energies that emitted from 232Th radioactive source.

Optimizing Gamma-Ray Shielding Material by Using Genetic Algorithm and MCNP Code

2010 ◽  
Author(s):  
Sahar Ashayer ◽  
Mansur Asgari ◽  
Hossein Afarideh
Keyword(s):  
Genetic Algorithm ◽  
Gamma Ray ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Mcnp Code ◽  
Biological Damage ◽  
Manned Spacecraft ◽  
Multi Objective Genetic Algorithm ◽  
Low Weight ◽  
Shielding Material

Radiation shielding material investigations is an important subject which relates to human safety, for those engaging in medical radiation, radiology, and facilities related with nuclear radiation, manned spacecraft and so on. Therefore necessity of finding effective shielding materials which have low weight, and cost, and have stability against radiation, with high temperature resistant, and no biological damage,… is obvious. On the other hand, because of the multi-variability of the problem, it is experimentally difficult to determine the optimum values of the concerned variables. For this reason, simulation for discovering optimized shielding material is important. Parameters such as attenuation, thickness, and cost of gamma radiation shielding materials were optimized by using genetic algorithm combined with MCNP code. Multi objective genetic algorithm (GA) is one of the scientific solutions for this problem.

scholarly journals A Novel Radiation Shielding Material for Gamma-Ray: The Development of Lutetium Lithium Borate Glasses

2018 ◽  
Vol 766 ◽  
pp. 246-251 ◽  
Author(s):  
Punsak Glumglomchit ◽  
Juniastel Rajagukguk ◽  
Jakrapong Kaewkhao ◽  
Keerati Kirdsiri
Keyword(s):  
Gamma Ray ◽  
Theoretical Data ◽  
Borate Glasses ◽  
Lithium Borate ◽  
Attenuation Coefficients ◽  
Effective Electron ◽  
Mass Attenuation Coefficients ◽  
Shielding Properties ◽  
Shielding Material ◽  
Mass Attenuation

This work, gamma-ray shielding properties of the lutetium lithium borate glasses in the system Lu2O3 - Li2O - B2O3 have been evaluated as a shielding material at 662 keV photon energy. While the experimental mass attenuation coefficients (μm) have been determined by using the narrow beam transmission method, the theoretical data were calculated using WinXCom program. The good agreements between experimental and theoretical values have been obtained. Both experimental and computational mass attenuation coefficients data were used to obtain the effective atomic number (Zeff), and the effective electron density (Nel). Based on the obtained data, the Lu-based glasses have good shielding properties, the improved glasses could be used as gamma-rays shielding material.

scholarly journals Calculation of gamma-ray attenuation parameters for locally developed shielding material: Polyboron

2016 ◽  
Vol 9 (1) ◽  
pp. 26-34 ◽  
Author(s):  
Ripan Biswas ◽  
Hossain Sahadath ◽  
Abdus Sattar Mollah ◽  
Md. Fazlul Huq
Keyword(s):  
Gamma Ray ◽  
Gamma Ray Attenuation ◽  
Shielding Material
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