Results 191 to 200 of about 2,139 (206)

Radiation shielding study of tellurite tungsten glasses with different antimony oxide as transparent shielding materials using MCNPX code

Journal of Non-Crystalline Solids, 2018
M I Sayyed, H O Tekin, Shamsan S Obaid
exaly  

Investigation of photon shielding performances of some selected alloys by experimental data, theoretical and MCNPX code in the energy range of 81 keV–1333 keV

Journal of Alloys and Compounds, 2019
F Akman, M I Sayyed, M R Kaçal
exaly  

Proposition of a practical protocol for obtaining a valid radiology image using radiography tally of MCNPX Monte Carlo Code

Applied Radiation and Isotopes, 2019
Alireza Kamali-Asl, Sanaz Hariri Tabrizi   +1 more
exaly  

Comparative investigations of gamma and neutron radiation shielding parameters for different borate and tellurite glass systems using WinXCom program and MCNPX code

Materials Chemistry and Physics, 2018
M I Sayyed, M G Dong, H O Tekin
exaly  

Radiation shielding and mechanical properties of Al2O3-Na2O-B2O3-Bi2O3 glasses using MCNPX Monte Carlo code

Materials Chemistry and Physics, 2019
Shams A M Issa, H O Tekin, Reda Elsaman   +2 more
exaly  

A new approach for solution of time dependent neutron transport equation based on nodal discretization using MCNPX code with feedback

Annals of Nuclear Energy, 2019
Naser Vosoughi
exaly  

Verification and validation of the MCNPX-PoliMi code for simulations of neutron multiplicity counting systems

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2013
S D Clarke, Marek Flaska, S A Pozzi
exaly  

Gamma radiation shielding properties of the hematite-serpentine concrete blended with WO3 and Bi2O3 micro and nano particles using MCNPX code

Radiation Physics and Chemistry, 2018
H O Tekin, M I Sayyed, Shams A M Issa
exaly  

Effects of micro-sized and nano-sized WO 3 on mass attenauation coefficients of concrete by using MCNPX code

Applied Radiation and Isotopes, 2017
H O Tekin, Vishwanath P Singh
exaly  

Neutronic analysis and validation of boiling water reactor core designed by MCNPX code

Annals of Nuclear Energy, 2015
A Abdelghafar Galahom
exaly