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Institution

Nuclear Power Corporation of India

About: Nuclear Power Corporation of India is a based out in . It is known for research contribution in the topics: Electromagnetic shielding & Photon energy. The organization has 68 authors who have published 61 publications receiving 927 citations.

Papers published on a yearly basis

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Journal ArticleDOI
TL;DR: Gamma-ray shielding competence of silicate and borate heavy metal oxide glasses has been investigated using linear attenuation coefficients, effective atomic numbers and exposure buildup factors (EBF) as mentioned in this paper.
Abstract: Gamma-ray shielding competence of silicate and borate heavy metal oxide glasses has been investigated using linear attenuation coefficients, effective atomic numbers and exposure buildup factors (EBF). The gamma-ray EBF were computed using the Geometric Progression (G-P) fitting method for photon energies from 0.015 to 15 MeV, and for penetration depths up to 40 mean free paths (mfps). The macroscopic effective removal cross-section for fast neutron has been calculated for energy range from 2 to 12 MeV. It is found that bismuth silicate glass has superior shielding properties and is suitable for replacement of lead glasses. The present investigation is very useful for gamma-ray and neutron shielding and design for lead-free shielding glass in radiological engineering.

202 citations

Journal ArticleDOI
TL;DR: In this paper, the gamma-ray exposure buildup factor (EBF) values and neutron shielding effectiveness of bismuth borosilicate (BBS) glass systems in composition (50− x )SiO 2 :15B 2 O 3 :2Al 2 O3 :10CaO:23Na 2 O: x Bi 2 O 4 (where x = 0, 5, 10, 15 and 20 ǫ%) were calculated.

157 citations

Journal ArticleDOI
TL;DR: In this article, the mass attenuation coefficients, mu/rho and effective atomic numbers, Z(eff) of some carbon steel and stainless steel alloys have been calculated by using Geant4, MCNP simulation codes for different gamma ray energies.

96 citations

Journal ArticleDOI
TL;DR: In this article, the gamma ray exposure buildup factor (EBF) and neutron shielding efficiency of borate glass systems in composition (100 − x − y) Na2B4O7−xPbO−yNiO (where x and y = 0, 2, 4, 6, 8 and 10 weight percentage) were investigated.
Abstract: Gamma ray exposure buildup factor (EBF) and neutron shielding efficiency of borate glass systems in composition (100 − x − y) Na2B4O7−xPbO−yNiO (where x and y = 0, 2, 4, 6, 8 and 10 weight percentage) were investigated in the present study. Gamma ray EBF values were computed using Geometric Progression (G-P) method for photon energy 0.015 to 15 MeV up to penetration depths of 40 mfp (mean free path). The macroscopic effective removal cross-sections (Σ R ) for fast neutron (2 to 12 MeV) were calculated. At low- and high-energy region, the EBF values were found minimum whereas maximum in the intermediate-energy regions with a sharp peak below 100 keV for oxide containing glass samples. The investigation was carried out for potential applications of borate glasses for radiation shielding.

86 citations

Journal ArticleDOI
TL;DR: In this paper, the mass attenuation coefficients, linear attenuation coefficient and tenth value layer of seven types of concretes having density (2.3-5.11 cm−3) have been simulated by Monte Carlo simulation techniques at photon energies 1.5, 2, 3, 4, 5 and 6.

51 citations


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Performance
Metrics
No. of papers from the Institution in previous years
YearPapers
20214
20204
20185
20174
20163
20158