scholarly journals .GAMMA.-ray attenuation coefficient and dose buildup factor of various building materials.

1985 ◽  
Vol 20 (3) ◽  
pp. 241-249
Author(s):  
Yasuhiro YAMAGUCHI ◽  
Kentaro MINAMI ◽  
Satoru OHTANI
2011 ◽  
Vol 8 (2) ◽  
pp. 613-617 ◽  
Author(s):  
Baghdad Science Journal

In this study, dependence of gamma-ray absorption coefficient on the size of Pb particle size ranging from 200µm up to 2.5mm, using different weights of each particle size. The results show that gamma-ray attenuation coefficient is inversely proportional with the size of Pb particle size due to the reduction of the spaces between the lead particles.


Author(s):  
Majid Jalali

The compounds, Na2B4O7, H3BO3, CdCl2 and NaCl and their solutions, attenuate gamma rays in addition to neutron absorption. These compounds are widely used in shielding of neutron sources, reactor control and neutron converters. Mass attenuation coefficients of gamma related to saturated solutions of the above four compounds, in energies 1172 keV and 1332 keV have been measured by NaI detector and agree very well with the results obtained by Xcom code. Experiment and computation show that, H3BO3 has the highest gamma ray attenuation coefficient among the aforementioned compounds.


Materials ◽  
2021 ◽  
Vol 14 (17) ◽  
pp. 5051
Author(s):  
Mahmoud T. Alabsy ◽  
Jamila S. Alzahrani ◽  
M. I. Sayyed ◽  
Mahmoud I. Abbas ◽  
Daria I. Tishkevich ◽  
...  

Polymers are often used in medical applications, therefore, some novel polymers and their interactions with photons have been studied. The gamma-ray shielding parameters for Polymethylpentene (PMP), Polybutylene terephthalate (PBT), Polyoxymethylene (POM), Polyvinylidenefluoride (PVDF), and Polychlorotrifluoroethylene (PCTFE) polymers were determined using the Geant4 simulation and discussed in the current work. The mass attenuation coefficients (μ/ρ) were simulated at low and high energies between 0.059 and 1.408 MeV using different radionuclides. The accuracy of the Geant4 simulated results were checked with the XCOM software. The two different methods had good agreement with each other. Exposure buildup factor (EBF) was calculated and discussed in terms of polymers under study and photon energy. Effective atomic number (Zeff) and electron density (Neff) were calculated and analyzed at different energies. Additionally, the half-value layer (HVL) of the polymers was evaluated, and the results of this parameter showed that PCTFE had the highest probability of interaction with gamma photons compared to those of the other tested polymers.


2020 ◽  
Vol 400 ◽  
pp. 32-37
Author(s):  
A.S. Guimarães ◽  
I.M. Ribeiro ◽  
A.C. Azevedo ◽  
João M.P.Q. Delgado

The knowledge of moisture transfer in multi-layered building materials and components using numerical simulations is fundamental to predict the behaviour of that building materials and components when in contact with moisture and to avoid some possible future pathology guarantying a correct performance.This paper describes a comparative analysis of experimental values of Hygric Permeance (HP) obtained by water absorption curves and gamma-ray attenuation profiles, for perfect contact interface.


2017 ◽  
Vol 2017 ◽  
pp. 1-7 ◽  
Author(s):  
Sarai Lekchaum ◽  
Kitsakorn Locharoenrat

This contribution is aimed at designing the optimal thickness of lead-iron double-layer container to store a radioactive waste releasing the photon energy at 1.3325 MeV and initial radiation intensity at 100 mSv/hr using the optimization design by MATLAB software. This design consisted of three parts of calculations to achieve 1000 times the radiation attenuation of container. The first was the logarithmic interpolation for the mass attenuation coefficient. The second was the bilogarithmic interpolation for the exposure buildup factor. The third was the contour-plotting analytical technique for the optimal thickness of radiation container. The values of mass attenuation coefficient and exposure buildup factor were exactly validated as compared with the standard reference database. Furthermore, we have found that the optimal thickness was 3.2 cm for lead (1st layer) and 17.0 cm for iron (2nd layer). Container weight was 994.30 kg, whilst container cost was 167.30 USD. The benefit of our design can quickly and precisely apply for the radiation safety assessment of the occupational radiation workers who always work in the nuclear reactor area.


1973 ◽  
Vol 8 (6) ◽  
pp. 2814-2818 ◽  
Author(s):  
S. Gopal ◽  
B. Sanjeevaiah

2014 ◽  
Vol 979 ◽  
pp. 395-400
Author(s):  
Natthakridta Chanthima ◽  
Kazuhito Shimada ◽  
Jakrapong Kaewkhao

The total mass attenuation coefficient (μ/ρ, cm2g-1) of gamma-ray for building materials containing with Lead Carbonate (PbCO3) have been studied. The raw building material have cement, sand and stone in the ratio 1 : 2 : 4. The raw material was mixed with 30% of PbCO3to be used as the sample material. The mass attenuation coefficient of the raw material has been calculated by theoretical approach using WinXCom program for the photon energy band from 1 keV to 100 GeV. The composition of sample material was analyzed by energy dispersive X-ray fluorescence spectrometer (EDXRF). The variations of mass attenuation coefficient are shown graphically and compared with that of standard shielding concretes. It was found that the sample building material has higher value of mass attenuation coefficient than standard shielding concretes at energy zone above 2–7 keV, 90–800 keV and 5 MeV–100 GeV.


2020 ◽  
pp. 60-65
Author(s):  
Hiwa Mohammad Qadr

The purpose of this study was to determine the linear attenuation coefficient, the mass attenuation coefficient, Half Value Layer. Tenth Value Layer and Mean Free Path for four different shielding materials such as aluminium, iron, zirconium and tungsten. By using the gamma-radiation energies emitted from 152Eu, 22Na, 137Cs, and 60Co radioactive sources. For this purpose, the attenuation measurements were performed using NaI(TI) detector. Calculated values of all parameters of the all shielding materials were compared with each other. The results of all presented parameters show that, tungsten has the best radiation shielding compared to other shielding materials. Then, the obtained parameters were compared with the theoretical values.


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