Results 171 to 180 of about 4,949 (201)

Secondary neutron source modelling using MCNPX and ALEPH codes

SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014
Monitoring 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

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

Shielding evaluation for solar particle events using MCNPX, PHITS and OLTARIS codes

Life Sciences in Space Research, 2015
Detailed 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, S.I. Sriprisan, R.C. Singleterry, T. Sato   +3 more
openaire   +2 more sources

Coupling the SAND-II and MCNPX codes for neutron spectrum unfolding

Journal of Instrumentation, 2018
Measurement 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

Radioactive particle tracking methodology to evaluate concrete mixer using MCNPX code

Radiation Physics and Chemistry, 2019
Abstract In Brazil, concrete and cement are highly used in construction, therefore mixers are widely used in this industry. During the fabrication process of concrete/cement, the equipment may fail and compromise the appropriate mixing procedure. Besides that, it is also important to determine the right point of homogeneity of the mixture.
Roos Sophia Dam, Caroline M. Barbosa, José M. Lopes, Jardel L. Thalhofer, Leandro B. Silva, César M. Salgado, Ademir X. da Silva   +6 more
openaire   +1 more source

Prediction of palladium-103 production using the Monte Carlo code MCNPX

Annals of Nuclear Energy, 2013
Abstract The radionuclide 103 Pd ( T 1/2  = 16.991 d; decays almost exclusively by EC to 103m Rh, T 1/2  = 56.114 min) has been of great interest in prostate and eye cancer therapy due to its suitable half-life and decay characteristics. 103 Pd has been produced by proton irradiation of a 103 Rh target through the 103 Rh(p,n) 103 Pd reaction.
Mahmodi, M., Sadeghi, M., Tenreiro, C.
openaire   +1 more source

Spread‐out Bragg peak and monitor units calculation with the Monte Carlo Code MCNPX

Medical Physics, 2007
The 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, N, Iborra, B, Serrano, P, Chauvel   +3 more
openaire   +2 more sources

Methodology for digital radiography simulation using the Monte Carlo code MCNPX for industrial applications

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, S C A, Correa, A X, Silva, R T, Lopes, D F, Oliveira   +4 more
openaire   +2 more sources

Fuel burnup analysis for IRIS reactor using MCNPX and WIMS-D5 codes

Radiation Physics and Chemistry, 2017
Abstract International Reactor Innovative and Secure (IRIS) reactor is a compact power reactor designed with especial features. It contains Integral Fuel Burnable Absorber (IFBA). The core is heterogeneous both axially and radially. This work provides the full core burn up analysis for IRIS reactor using MCNPX and WIMDS-D5 codes.
E.A. Amin, I.I. Bashter, Nabil M. Hassan, S.S. Mustafa   +3 more
openaire   +1 more source

A new application of radioactive particle tracking using MCNPX code and artificial neural network

Applied Radiation and Isotopes, 2019
Stirrers 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, Tâmara P, Teixeira, William L, Salgado, César M, Salgado   +3 more
openaire   +2 more sources