Results 171 to 180 of about 5,690 (213)

The comparison of different multilayer perceptron and General Regression Neural Networks for volume fraction prediction using MCNPX code.

Applied Radiation and Isotopes, 2020
This research presents a methodology for volume fraction predictions in water-gas-oil multiphase systems based on gamma-ray densitometry and artificial neural networks.
C. Salgado, Ross Sophia de Freitas Dam, W. L. Salgado, R. Werneck, C. Pereira, R. Schirru   +5 more
semanticscholar   +1 more source

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
In the present article, for different chemical compositions of B2O3‒Bi2O3, B2O3‒Sb2O3, B2O3‒WO3‒La2O3, B2O3‒MoO3‒ZnO, and TeO2‒MO (M = Mg, Ba, and Zn) glasses, by applying WinXCom program we calculated the mass attenuation coefficient (μ/ρ) values, and ...
M. Sayyed, M. Dong, H. O. Tekin, G. Lakshminarayana, M. Mahdi   +4 more
semanticscholar   +1 more source

An inter-comparison between accuracy of EGSnrc and MCNPX Monte Carlo codes in dosimetric characterization of intraoperative electron beam

Comput. Biol. Medicine, 2020
BACKGROUND Ionometric dosimetry in IOERT is a complicated process, due to the sophisticated beam setup and the necessity for dedicated protocols for ion chamber response correction.
S. Lashkari, H. Baghani, M. Tavakoli, S. Mahdavi   +3 more
semanticscholar   +1 more source

The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability

Nuclear Technology, 2010
Monte Carlo–linked depletion methods have gained recent interest due to the ability to model complex three-dimensional geometries using continuous-energy cross sections.
Michael L. Fensin, John S. Hendricks, Samim Anghaie   +2 more
openaire   +1 more source

Development of the MCNPX model for the portable HPGe detector

Radiation Physics and Chemistry, 2014
The portable HPGe coaxial detector Canberra Big MAC is used in LVR-15 research reactor for spectrometric measurement of spent nuclear fuel. The fuel is measured in the dedicated system located in the spent fuel pool situated near the reactor. For the purpose of the spectrometric system calibration, the detector was precisely modeled with the MCNPX code.
Michal Koleska, Ladislav Viererbl, Milan Marek   +2 more
openaire   +1 more source

Photon shielding characterizations of bismuth modified borate –silicate–tellurite glasses using MCNPX Monte Carlo code

Materials Chemistry and Physics, 2018
In this study, the radiation mass attenuation coefficients of different bismuth-borate glass samples as shielding materials are calculated at 356, 662, 1173 and 1332 keV photon energies by using general purpose Monte Carlo code MCNPX (version 2.4.0). The
Huseyin Ozan Tekin, M. Sayyed, T. Manici, E. Altunsoy   +3 more
semanticscholar   +1 more source

GEANT4 benchmark with MCNPX and PHITS for activation of concrete

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2018
Abstract The activation of concrete is a real problem from the point of view of waste management. Because of the complexity of the issue, Monte Carlo (MC) codes have become an essential tool to its study. But various codes or even nuclear models exist in MC.
Robin Tesse, Frédéric Stichelbaut, Nicolas Pauly, Alain Dubus, Jonathan Derrien   +4 more
openaire   +2 more sources

Radiation shielding properties of pentaternary borate glasses using MCNPX code

Journal of Physics and Chemistry of Solids, 2018
The mass attenuation coefficient, effective atomic number, and half value layer of (75-x) B 2 O 3 -xBi 2 O 3 -10Na 2 O-10CaO-5Al 2 O 3 glass system (x = 0, 5, 10, 15, 20 and 25mol%) with potential applications as radiation shielding materials, have been ...
M. Sayyed, B. Elbashir, H. Tekin, E. Altunsoy, D. Gaikwad   +4 more
semanticscholar   +1 more source

Analysis of red mud doped Bi2O3-B2O3-BaO glasses for application as glass solder in radiation shield repair using MCNPX simulation

Ceramics International, 2019
Glasses in the range 50Bi2O3-30B2O3-(20-x)BaO-xRedmud, x = 0.1–0.5 wt%, were synthesized and characterized for use as low melting point radiation shield glass solder using a combination of spectroscopic, thermal analysis and MCNPX simulation.
W. Marltan, P. Venkateswara Rao, H. O. Tekin, M. Sayyed, R. Klement, D. Galusek, G. Lakshminarayana, P. Syam Prasad, N. Veeraiah   +8 more
semanticscholar   +1 more source

Monte-Carlo Simulations: FLUKA vs. MCNPX

AIP Conference Proceedings, 2007
Several experiments were performed at the Phasotron and Nuclotron accelerators in JINR Dubna in which spallation reactions and neutron transport were studied. The experimental results were checked against the predictions of the Monte‐Carlo code MCNPX.
M. Oden, A. Krasa, M. Majerle, O. Svoboda, V. Wagner, Carlos Granja, Claude Leroy, Ivan Stekl   +7 more
openaire   +1 more source