Results 61 to 70 of about 4,949 (201)
In a cyclotron-based proton therapy facility, the energy changes are performed by means of a degrader of variable thickness. The interaction of the proton beam with the degrader creates energy tails and increases the beam emittance.
Adelmann, A. +5 more
core +1 more source
Fuel burnup analysis for Thai research reactor by using MCNPX computer code [PDF]
This paper presents the fuel burnup analysis of the Thai research reactor (TRR-1/M1), TRIGA Mark-III, operated by Thailand Institute of Nuclear Technology (TINT) in Bangkok, Thailand. The modelling software used in this analysis is MCNPX (MCNP eXtended) version 2.6.0, a Fortran90 Monte Carlo radiation transport computer code.
S Sangkaew, T Angwongtrakool, B Srimok
openaire +1 more source
Characterization of the light and flexible nonlead aprons as an alternative to Pb–PVC
Abstract Background Radiation shielding is crucial for protecting healthcare professionals from scatter radiation during x‐ray procedures. Conventional lead aprons, although effective, are limited by their high weight, low flexibility, and potential toxicity.
Mansour Tayebi khorami, Zaker Salehi
wiley +1 more source
The study of neutron spectra in water bath from Pb target irradiated by 250MeV/u protons
The spallation neutrons were produced by the irradiation of Pb with 250 MeV protons. The Pb target was surrounded by water which was used to slow down the emitted neutrons.
Bin Zhou +15 more
core +1 more source
Monte Carlo Particle Lists: MCPL [PDF]
A binary format with lists of particle state information, for interchanging particles between various Monte Carlo simulation applications, is presented.
Cai, Xiao Xiao +5 more
core +2 more sources
The melt quench method has been used to prepare the xBi2O3-(30-x)MoO3-40B2O3-20SiO2-9Na2O-1Fe2O3 glass system, where x = 15, 17.5, 20, 25 and 30 mol. %.
Shams A.M. Issa +4 more
doaj +1 more source
Simulation of surface flux received through breast tumor radiation therapy with MCNPX code
In radiation therapy, investigating of the effects of the surface flux reaching on the tissue is important in planning the treatment and this requires a precise evaluation of the absorbed dose distribution throughout the irradiated tissue. Therefore, by Monte Carlo simulation with MCNP code, a point source with the size of E with a spectrum width of 0 ...
Afshin, Parsa +2 more
openaire +2 more sources
Abstract Background The choice of nuclear interaction models in Monte Carlo simulations affects the dose calculation accuracy for light ion beam therapy. Purpose This study aimed to evaluate the dose calculation accuracy and simulation time of three GATE‐RTiON/Geant4 physics lists for therapeutic carbon ion beams, assessing their suitability for ...
Yihan Jia +6 more
wiley +1 more source
Radiation protection considerations on radon and building materials radioactivity in Near Zero Energy Buildings [PDF]
Recent updates of the E.U. Basic Safety Standards, stated in the Council Directive 2013/59/EURATOM, are focusing on risks related to radon gas concentration inside dwellings and working places, as well as radioactivity of building materials.
Franci, Daniele +4 more
core +1 more source
Abstract Background Radiobiological data suggests variations in relative biological effectiveness (RBE) between clinically used photon‐based sources. A microdosimetric formalism using Monte Carlo (MC) methods can mechanistically describe the photon RBE.
Mirta Dumančić +6 more
wiley +1 more source

