Results 111 to 120 of about 4,292 (208)

INVESTIGATION OF WATER EQUIVALANCE AND SHIELDING PROPERTIES OF DIFFERENT SOLID PHANTOMS USING MCNPX CODE

, 2021
The purpose of the present study was to evaluate the capability of Monte Carlo N-Particle Transport Code System-eXtendend (MCNPX) Monte Carlo code on investigation the water equivalent different solid phantoms and their shielding parameters and also ...
Tekin, H. O., Karahan, M., Erguzel, T. T., Mesbahi, A., Kara, U., Kilicoglu, O., Sayyed, M.   +6 more
core  

Neutron multiplicity simulations: geant4 versus mcnpx-polimi

, 2016
[57th Annual INMM Meeting, 2016-07-24 - 2016-07-28, Atlanta, USA] 57th Annual INMM Meeting, Atlanta, USA, 24 Jul 2016 - 28 Jul ...
Kütt, Moritz, Göttsche, Malte
openaire   +2 more sources

Verification of Photonuclear Reactions in OpenMC with MCNPx and FLUKA

Conference paper presented at PHYSOR 2026 - The International Conference on Physics of Reactors. Published in Proceedings of PHYSOR 2026 International Conference. ISBN: 979-12-81583-46-7. Conference website: https://www.physor2026.org/. Session: R05. Verification and Validation of Methods and Codes. Paper ID: 509.
L. Loi, A. Missaglia, C. Introini, F. C. Giacobbo, E. Padovani, A. Cammi   +5 more
openaire   +1 more source

Personal monitor glass badge: Theoretical dosemeter response calculated with the Monte Carlo transport code MCNPX

, 2011
International audienceThis paper describes the results of the simulation of a radiophotoluminescent (RPL) dosemeter with the Monte Carlo transport code MCNPX.
Clairand, I., C. Huet, Huet, C., Hocine, N., Itié, C., I. Clairand, C. Itie, N. Hocine, Donadille, L., L. Donadille   +9 more
core   +1 more source

MCNPX 2.7.0 extensions

, 2011
Denise Pelowitz, Joe Durkee, Jay Elson, Michael Fensin, John Hendricks, Michael James, Russell Johns, Gregg Mc Kinney, Stepan Mashnik, Laurie Waters, Trevor Wilcox, Jerome Verbeke   +11 more
openaire   +2 more sources

Investigating the possibility of extending the BWR cycle length for 15 years of operation by mixing highly enriched UO₂ fuel with burnable absorbers. [PDF]

Sci Rep, 2023
Mustafa SS.
europepmc   +1 more source

Monte Carlo microdosimetry of ²¹¹at in multi-species thyroid follicle models: AlfaMC versus MCNPX and Geant4. [PDF]

EJNMMI Phys
Romiani A, Josefsson A, Chakarova R, Forssell-Aronsson E.   +3 more
europepmc   +1 more source

Effects of type and thickness of joint infill materials on gamma radiation attenuation in rock masses: experimental and numerical investigations. [PDF]

Sci Rep
Golmohammadi S, Noorian-Bidgoli M, Moghaddam-Arani AR.   +2 more
europepmc   +1 more source

Utilization of three-layers heterogeneous mammographic phantom through MCNPX code for breast and chest radiation dose levels at different diagnostic X-ray energies: A Monte Carlo simulation study. [PDF]

Front Public Health, 2023
ALMisned G, Elshami W, Kilic G, Rabaa E, Zakaly HMH, Ene A, Tekin HO.   +6 more
europepmc   +1 more source

MCNPX Simulations for Neutron Cross Section Measurements

, 2010
This thesis presents MCNPX simulations of the SCANDAL set-up used at the Theodor Svedberg Laboratory for neutron scattering cross-section measurements. The thesis describes processes and data important for the upcoming off-line data analysis. In the experiment, neutrons scattered off the target are converted to protons which are stopped in scintillator
openaire   +1 more source