Results 171 to 180 of about 2,139 (206)
In this study, the gamma photons shielding parameters of the newly produced (NG1, NG2, NG3 and NG4) and widely used (Window, PbO, Soda and Borosilicate glasses) glass samples were evaluated comparatively.
E Kavaz, N Ekinci, H O Tekin
exaly +2 more sources
Some of the next articles are maybe not open access.
Related searches:
Related searches:
Coupling the SAND-II and MCNPX codes for neutron spectrum unfolding
Journal of Instrumentation, 2018Measurement of neutron energy spectrum is very important to develop the application of neutrons in different fields of science and technology. One of the commonly used methods to measure the neutron energy spectrum is the threshold foil activation method and using an unfolding code such as SAND-II. The main limitation of such codes is that the geometry
A. Heydarzade, Y. Kasesaz, S. Mohammadi
openaire +1 more source
Secondary neutron source modelling using MCNPX and ALEPH codes
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014Monitoring the subcritical state and divergence of reactors requires the presence of neutron sources. But mainly secondary neutrons from these sources feed the ex-core detectors (SRD, Source Range Detector) whose counting rate is correlated with the level of the subcriticality of reactor.
Christos Trakas, Nordine Kerkar
openaire +1 more source
Proton Therapy of eye using MCNPX code
2018Introduction: Proton radiotherapy is the one of advanced teletherapy methods. The protons deposit their maximum energy in a position called Bragg peak. Therefore, for treatment of cancer, the tumor should be placed at the Bragg peak or SOBP. The scattered photons and neutrons is a challenge in proton radiotherapy.
Safaiean, S. +2 more
openaire +1 more source
Shielding evaluation for solar particle events using MCNPX, PHITS and OLTARIS codes
Life Sciences in Space Research, 2015Detailed analyses of Solar Particle Events (SPE) were performed to calculate primary and secondary particle spectra behind aluminum, at various thicknesses in water. The simulations were based on Monte Carlo (MC) radiation transport codes, MCNPX 2.7.0 and PHITS 2.64, and the space radiation analysis website called OLTARIS (On-Line Tool for the ...
S.K. Aghara +3 more
openaire +2 more sources
Responses of a 6LiI Bonner Sphere Spectrometer using the Monte Carlo codes PHITS and MCNPX
Applied Radiation and Isotopes, 2023The response functions (RFs) of a Bonner Sphere Spectrometer (BSS) with a 6LiI thermal neutron detector were calculated using the Monte Carlo codes PHITS (version 3.26) and MCNPX (version 2.7.0), with their own default nuclear data libraries, and physics models.
Rafael Santos Oliveira +3 more
openaire +2 more sources
Radiation shielding properties of pentaternary borate glasses using MCNPX code
Journal of Physics and Chemistry of Solids, 2018Abstract 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 investigated in the energy ranging from 31 keV to 662 keV using the MCNPX Code ...
M.I. Sayyed +4 more
openaire +1 more source
Spread‐out Bragg peak and monitor units calculation with the Monte Carlo Code MCNPX
Medical Physics, 2007The aim of this work was to study the dosimetric potential of the Monte Carlo code MCNPX applied to the protontherapy field. For series of clinical configurations a comparison between simulated and experimental data was carried out, using the proton beam line of the MEDICYC isochronous cyclotron installed in the Centre Antoine Lacassagne in Nice.
J, Hérault +3 more
openaire +2 more sources
Applied Radiation and Isotopes, 2008
This work presents a methodology for digital radiography simulation for industrial applications using the MCNPX radiography tally. In order to perform the simulation, the energy-dependent response of a BaFBr imaging plate detector was modeled and introduced in the MCNPX radiography tally input. In addition, a post-processing program was used to convert
E M, Souza +4 more
openaire +2 more sources
This work presents a methodology for digital radiography simulation for industrial applications using the MCNPX radiography tally. In order to perform the simulation, the energy-dependent response of a BaFBr imaging plate detector was modeled and introduced in the MCNPX radiography tally input. In addition, a post-processing program was used to convert
E M, Souza +4 more
openaire +2 more sources
A new application of radioactive particle tracking using MCNPX code and artificial neural network
Applied Radiation and Isotopes, 2019Stirrers and mixers are highly used in chemical, food, pharmaceutical, cosmetic, concrete industries and others. During the fabrication process, the equipment may fail to appropriately stir or mix the solution. Besides that, it is also important to determine when the right homogeneity of the mixture is attained.
Roos Sophia de F, Dam +3 more
openaire +2 more sources

