scholarly journals Assessment of a polymeric composite as a radiation attenuator and a restoration mortar for cracking in biological shields

2020 ◽  
Vol 21 (4) ◽  
pp. 361-368
Author(s):  
A.T. Gheith ◽  
◽  
M.A. El-Sarraf ◽  
I.E. Hasan ◽  
N.L. Helal ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Cross Sections ◽  
Gamma Ray ◽  
Detection System ◽  
Polymeric Composite ◽  
Pulse Shape Discrimination ◽  
Attenuation Relations ◽  
Attenuation Coefficients ◽  
Effective Removal ◽  
Collimated Beam

This work is dedicated to figuring out robust epoxy/magnetite/boron carbide (EP/Mag/B4C) composite for radiation attenuation at multiple applications related to nuclear installations, as well as restoration mortar for cracking developed in concrete biological shields. The mechanical properties (flexural, compressive, and impact strengths) and the physical properties (water absorption, porosity, and dry bulk density), each, have been performed to label the composite integrity for practical application. In practice, attenuation properties have been performed by using a collimated beam emitted from spontaneous fission 252Cf (100 μg) neutron source and neutron gamma spectrometer with stilbene scintillator. The pulse shape discrimination technique which would come of the zero cross over method was used to measure the fast neutron and gamma-ray spectra. Thermal neutron fluxes have been measured by using the thermal neutron detection system and the BF-3 detector. The attenuation parameters: precisely, macroscopic effective removal cross-sections ΣR (cm-1), macroscopic cross-sections Σ (cm-1), and total attenuation coefficients μ (cm-1) of fast and thermal neutrons and total gamma-rays respectively were evaluated using the attenuation relations. Also, the MCNP5 code and MERCSF-N program have been used to compute the parameters theoretically. When applicable, measured and calculated results were compared, and it tells us a comprehensive agreement.

scholarly journals Investigation on radiation shielding parameters of ordinary, heavy and super heavy concretes

2014 ◽  
Vol 29 (2) ◽  
pp. 149-156 ◽  
Author(s):  
Vishwaanath Singh ◽  
Nagappa Badiger
Keyword(s):  
Cross Sections ◽  
Gamma Ray ◽  
Weight Fraction ◽  
High Energy ◽  
Radiation Shielding ◽  
Normal Operation ◽  
Attenuation Coefficients ◽  
Effective Removal ◽  
Energy Gamma ◽  
Shielding Design

Shielding of a reactor is required for protection of people and environment during normal operation and accidental situations. In the present paper we investigated the shielding parameters viz. mass attenuation coefficients, linear attenuation coefficients, tenth-value layer, effective atomic numbers, kerma relative to air and exposure buildup factors for gamma-ray for ordinary, heavy, and super heavy concretes. Macroscopic effective removal cross-sections for fast neutron had also been calculated. Ordinary concrete is economically suitable for mixture high energy gamma-ray and neutron as it has large weight fraction of low-Z as compared with super heavy concretes to slow down the neutron. Super heavy concretes are superior shielding for both reactor operation and accident situations. The study is useful for optimizing for shielding design and radiation protection in the reactors.

scholarly journals Characterization and Monte Carlo simulations for a CLYC detector

2018 ◽  
Vol 48 ◽  
pp. 1860115
Author(s):  
Alessandro Borella ◽  
Eric Boogers ◽  
Riccardo Rossa ◽  
Peter Schillebeeckx
Keyword(s):  
Monte Carlo ◽  
Gamma Ray ◽  
Detection System ◽  
Nuclear Material ◽  
Point Sources ◽  
Pulse Shape Discrimination ◽  
Monte Carlo Code ◽  
Nuclear Security ◽  
Collaborative Agreement ◽  
Personal Dosimetry

The CLYC (Cs[Formula: see text]LiYCl[Formula: see text]:Ce) detector is a scintillator detector sensitive to both neutron and gamma radiation and capable of separating the two types of radiation by pulse-shape discrimination. This feature is interesting as pertains to the development of non-destructive assays for the safeguard of nuclear material, nuclear security, and fast-neutron personal dosimetry. A [Formula: see text] CLYC detector highly enriched with [Formula: see text]Li was purchased and tested with analog and digital electronics. In this work, we report on the characterization of the detector in terms of linearity, energy resolution, and full-energy efficiency for gamma rays. This characterization was achieved by measurements with calibrated gamma-ray point-sources with an analog measuring chain, in a well-defined, reproducible geometry. The experimental data were also used to validate a model of the detection system that was developed with the Monte Carlo code MCNP-CP. This work is part of a collaborative agreement between SCK•CEN and JRC-Geel.

scholarly journals Investigation of Gamma and Neutron Shielding Parameters for Borate Glasses Containing NiO and PbO

2014 ◽  
Vol 2014 ◽  
pp. 1-7 ◽  
Author(s):  
Vishwanath P. Singh ◽  
N. M. Badiger
Keyword(s):  
Photon Energy ◽  
Cross Sections ◽  
Borate Glass ◽  
Gamma Ray ◽  
Radiation Shielding ◽  
Interaction Parameters ◽  
Neutron Shielding ◽  
Attenuation Coefficients ◽  
Effective Electron ◽  
Weight Percentage

The mass attenuation coefficients, μ/ρ, half-value layer, HVL, tenth-value layer, TVL, effective atomic numbers, ZPIeff, and effective electron densities, Ne,eff, of borate glass sample systems of (100-x-y) Na2B4O7 : xPbO : yNiO (where x and y=0, 2, 4, 6, 8, and 10 weight percentage) containing PbO and NiO, with potential gamma ray and neutron shielding applications, have been investigated. The gamma ray interaction parameters, μ/ρ, HVL, TVL, ZPIeff, and Ne,eff, were computed for photon energy range 1 keV–100 GeV. The macroscopic fast neutron removal cross-sections (ΣR) have also been calculated. Appreciable variations were noted for all the interaction parameters by varying the photon energy and the chemical composition of the glass samples. The better shielding properties of borate glass samples containing PbO were found. These results indicated that borate glass samples are a good radiation shielding material.

scholarly journals Interaction studies and gamma-ray properties of some low-Z materials

2016 ◽  
Vol 31 (2) ◽  
pp. 135-141 ◽  
Author(s):  
Rameshwar Bhosale ◽  
Dhammajyot Gaikwad ◽  
Pravina Pawar ◽  
Madhav Rode
Keyword(s):  
Cross Sections ◽  
Building Materials ◽  
Gamma Ray ◽  
Low Cost ◽  
Electron Densities ◽  
Attenuation Coefficients ◽  
Effective Electron ◽  
Plastic Industry ◽  
Effective Atomic Numbers ◽  
Set Up

In present work we use NaI(Tl) detector in narrow-beam good geometry set-up for the gamma ray attenuation studies of some low-Z materials. The parameters such as mass attenuation coefficients, effective atomic numbers and effective electron densities, atomic cross-sections, electronic cross-sections of materials for graphitic powder, polycarbonate, polyvinyl chloride, plaster of Paris, gypsum, and limestone were determined using gamma ray sources 57Co, 133Ba, 137Bs, 60Co, and 22Na at energies of 122, 356, 511, 662, 840, 1170, 1275, and 1330 keV. It was observed that the effective atomic numbers and effective electron densities initially decrease and tend to be almost constant as a function of gamma-ray energy. An attempt was done to check the availability of these low-Z materials at large scales and obtainable at low cost as gamma ray shielding materials. The investigated data are useful in electronic industry, plastic industry, building materials, and agriculture fields.

Lower energy photon cross sections near atomic shell edges

1990 ◽  
Vol 68 (2) ◽  
pp. 244-248
Author(s):  
Manjusree Ghosh ◽  
S. K. Ghose ◽  
S. C. Das ◽  
N. Bhattacharyya ◽  
P. Chowdhuri ◽  
...  
Keyword(s):  
Cross Sections ◽  
Gamma Ray ◽  
Theoretical Models ◽  
Binding Energies ◽  
Radioactive Isotopes ◽  
Atomic Shell ◽  
Energy Photon ◽  
Attenuation Coefficients ◽  
Transmission Technique ◽  
Photon Attenuation

Photon attenuation cross sections have been measured from time to time using radioactive isotopes as photon sources in various geometries. There are, however, inconsistencies between the measured values and the available tabulated values of attenuation coefficients based on different theoretical models. The measured values are particularly deficient for photon energies in the neighbourhood of the K-shell binding energies of attenuator elements. With the objective of filling such gaps in the experimental data as well as improving the data of earlier measurements, we have undertaken the present measurements in the energy region 43–1330 KeV. The measurements are made with the transmission technique using a NaI detector in the "good geometry," in which no gamma-ray photon scattered from the absorber at an angle greater than 0.3° can reach the detector. Results covering the elements from Z = 6–92 are presented and compared with the tabulated values of Hubbell et al. and Schaupp et al.

Solar Flare Energetic Neutral Emission Measurements in the Project Coronas-I

1994 ◽  
Vol 144 ◽  
pp. 635-639
Author(s):  
J. Baláž ◽  
A. V. Dmitriev ◽  
M. A. Kovalevskaya ◽  
K. Kudela ◽  
S. N. Kuznetsov ◽  
...  
Keyword(s):  
Solar Flare ◽  
Energy Range ◽  
Gamma Rays ◽  
Pulse Shape ◽  
Gamma Ray ◽  
Pulse Shape Discrimination ◽  
Shape Discrimination ◽  
Solar Neutron ◽  
Low Altitude

AbstractThe experiment SONG (SOlar Neutron and Gamma rays) for the low altitude satellite CORONAS-I is described. The instrument is capable to provide gamma-ray line and continuum detection in the energy range 0.1 – 100 MeV as well as detection of neutrons with energies above 30 MeV. As a by-product, the electrons in the range 11 – 108 MeV will be measured too. The pulse shape discrimination technique (PSD) is used.

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