Results 181 to 190 of about 5,690 (213)

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

MCNPX vs. DORT for sns shielding design studies

Radiation Protection Dosimetry, 2005
Radiation transport occurs through the 18 m long access way adjacent to the Spallation Neutron Source accelerator tunnel and the 2.2 m thick massive shielding door which closes the access way. A variety of typical materials for accelerator shielding, such as concrete and steel, were used for construction of the door to study radiation penetration.
openaire   +2 more sources

Photonuclear physics modeling in the MCNPX-PoliMi code

2012 IEEE Nuclear Science Symposium and Medical Imaging Conference Record (NSS/MIC), 2012
The MCNP-PoliMi code is an enhanced version of the MCNP4c code developed in 2003 to simulate the detector response from correlated neutron and gamma-ray measurements. In 2012 the -PoliMi modifications were incorporated into version 2.7.0 of the MCNPX code.
Shaun D. Clarke, Sara A. Pozzi, Enrico Padovani   +2 more
openaire   +1 more source

The role of dysprosium oxide (Dy_2O_3) on gamma and neutron radiation protection properties of lead borosilicate glasses by using Monte Carlo simulation MCNPX code and Phy-X/PSD software

Pramana (Bangalore), 2023
M. Aladailah, O. L. Tashlykov, A. Acikgoz, G. Demircan, M. Altarawneh   +4 more
semanticscholar   +1 more source

Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX.

Applied Radiation and Isotopes, 2019
A comparative study has been performed with the latest evaluated nuclear data libraries JEFF-3.3 and ENDF/B-VIII.0. The study has been conducted through the benchmark calculations for 120 criticality problems and the TRIGA Mark II research reactor with ...
Ouadie Kabach, A. Chetaine, A. Benchrif
semanticscholar   +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

Proton Therapy of eye using MCNPX code

2018
Introduction: 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., Salehi Barough, M., Shirmardi, S.P.   +2 more
openaire   +1 more source

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

Gamma ray shielding studies on 26.66 B2O3–16GeO2–4Bi2O3–(53.33–x) PbO–xPbF2 glass system using MCNPX, Geant4 and XCOM

Materials Research Express, 2018
In the present work, MCNPX and Geant4 have been used to calculate the mass attenuation coefficient of 26.66 B2O3–16GeO2–4Bi2O3–(53.33–x) PbO–xPbF2 (x = 0, 15, 30, 40 mol %) glasses at 0.122, 0.356, 0.511, 0.662, 0.84, 1.17, 1.275 and 1.33 MeV photon ...
Ajay Kumar, S. Singh, Y. Elmahroug, Ü. Kara, H. O. Tekin, M. Sayyed   +5 more
semanticscholar   +1 more source

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