Results 151 to 160 of about 1,181 (179)

Comparison of GEANT4 and MCNPX-PoliMi fission models

2012 IEEE Nuclear Science Symposium and Medical Imaging Conference Record (NSS/MIC), 2012
The detection and characterization of special nuclear material (SNM) is of significant importance for nonproliferation applications. For neutron energies
Syed F. Naeem, Shaun D. Clarke, Sara A. Pozzi   +2 more
openaire   +1 more source

Prediction of 67Ga production using the Monte Carlo code MCNPX

Applied Radiation and Isotopes, 2013
The widely used Monte Carlo simulation code Monte Carlo N-Particle System (MCNPX) has been utilized to simulate the production of (67)Gallium via multiple nuclear reaction channels. Based on the MCNPX-generated, energy-dependent proton flux within a Zn target during irradiation, the (67)Ga production yield was determined.
M, Sadeghi, N, Jokar, T, Kakavand, H, Ghafoori Fard, C, Tenreiro   +4 more
openaire   +2 more sources

Computed radiography simulation using the Monte Carlo code MCNPX

Applied Radiation and Isotopes, 2010
Simulating X-ray images has been of great interest in recent years as it makes possible an analysis of how X-ray images are affected owing to relevant operating parameters. In this paper, a procedure for simulating computed radiographic images using the Monte Carlo code MCNPX is proposed.
S C A, Correa, E M, Souza, A X, Silva, D H, Cassiano, R T, Lopes   +4 more
openaire   +2 more sources

SOFT-RT: Software for IMRT simulations based on MCNPx code

Applied Radiation and Isotopes, 2016
Intensity Modulated Radiation Therapy (IMRT) is an advanced treatment technique, widely used in external radiotherapy. This paper presents the SOFT-RT which allows the simulation of an entire IMRT treatment protocol. The SOFT-RT performs a full three-dimensional renderization of a set of patient images, including the definitions of region of interest ...
Telma Cristina Ferreira, Fonseca, Tarcisio Passos Ribeiro, Campos   +1 more
openaire   +2 more sources

Quantitative comparison between PGNAA measurements and MCNPX simulations

Journal of Radioanalytical and Nuclear Chemistry, 2015
A MCNPX model of a neutron activation facility for radioactive waste characterization was built to support experimental studies. To validate this model, small samples of different elemental composition were irradiated and experimental data are compared to simulation results obtained using different neutron capture prompt gamma ray databases.
Nicol, T., Carasco, C., Perot, B., Ma, J. L., Payan, E., Mauerhofer, E., Havenith, A., Collot, J.   +7 more
openaire   +2 more sources

Particles Transportation and Nuclear Heating in a Tokamak by MCNPX and GEANT4

Journal of Fusion Energy, 2015
In this work as a first goal, GEANT4 Monte Carlo tool has been evaluated by means of comparison with MCNPX as alternate Monte Carlo tool in the field of tokamaks nuclear analysis. For this respect, the ITER-like geometry was studied as a candidate tokamak.
openaire   +1 more source

Gamma photon-neutron attenuation parameters of marble concrete by MCNPX code

Radiation Effects and Defects in Solids, 2021
İskender Akkurt, Roya Boodaghi Malidarre   +1 more
exaly  

Comparison of MCNPX and FLUKA Monte Carlo codes in the simulating a nuclear gauge

Applied Radiation and Isotopes, 2021
Mojtaba Tajik
exaly  

Photon attenuation coefficients of different rock samples using MCNPX, Geant4 simulation codes and experimental results: a comparison study

Radiation Effects and Defects in Solids, 2018
Shamsan Obaid, Huseyin Ozan Tekin, M I Sayyed   +2 more
exaly  

MPI configuration of MCNPX for PCs

2014
openaire   +1 more source