Results 71 to 80 of about 6,588 (195)

7-Li(p,n) Nuclear Data Library for Incident Proton Energies to 150 MeV [PDF]

open access: yes, 2000
We describe evaluation methods that make use of experimental data, and nuclear model calculations, to develop an ENDF-formatted data library for the reaction p + Li7 for incident protons with energies up to 150 MeV.
Chadwick, M. B.   +6 more
core   +2 more sources

Optimizing the Nuclear Concentration Measuring System of the Cutter Suction Dredger Using MCNPX Monte Carlo Code [PDF]

open access: yesمجله مدل سازی در مهندسی
Using a dredger to remove mud and garbage accumulated in the river or sea docks is a common and important process. In order to monitor the condition of sediments on the sea bed, it is necessary to use an online measurement system for the concentration of
Mojtaba Askari   +2 more
doaj   +1 more source

The role of Ag2O incorporation in nuclear radiation shielding behaviors of the Li2O–Pb3O4–SiO2 glass system: A multi-step characterization study

open access: yesOpen Chemistry, 2023
We report the gamma-ray shielding properties of five different lithium silicate glasses based on the (40 − x) Li2O–10Pb3O4–50SiO2 nominal composition. Transmission factor values and some basic shielding parameters such as linear (µ) and mass attenuation ...
ALMisned Ghada   +8 more
doaj   +1 more source

Improved modelling of helium and tritium production for spallation targets [PDF]

open access: yes, 2009
Reliable predictions of light charged particle production in spallation reactions are important to correctly assess gas production in spallation targets.
A. Boudard   +31 more
core   +1 more source

OEDIPE: A Personalized Dosimetric Tool Associating Voxel-Based Models with MCNPX [PDF]

open access: yesCancer Biotherapy and Radiopharmaceuticals, 2005
A new tool, named OEDIPE (a French acronym that stands for "Tool for Personalized Internal Dose Assessment") was developed to carry out personalized internal dosimetry calculations for nuclear medicine (for both therapeutic and diagnostic procedures) and for radiation safety (in the case of internal contamination).
Sophie, Chiavassa   +6 more
openaire   +2 more sources

Experimental validation of Geant4 nuclear interaction models in dose calculations of therapeutic carbon ion beams

open access: yesMedical Physics, Volume 52, Issue 7, July 2025.
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

Sample dose calculation for flexural strength test in Tehran research reactor reflector [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2019
Safety is one of the most critical issues in any test. The flexural test is a significant one to obtain material specifications. In this paper, a standard sample dose rate was calculated for the graphite flexural test in Tehran research reactor.
M.A Amirkhani   +3 more
doaj   +1 more source

Facility for fast neutron irradiation tests of electronics at the ISIS spallation neutron source [PDF]

open access: yes, 2008
The VESUVIO beam line at the ISIS spallation neutron source was set up for neutron irradiation tests in the neutron energy range above 10 MeV. The neutron flux and energy spectrum were shown, in benchmark activation measurements, to provide a neutron ...
A. Paccagnella   +10 more
core   +2 more sources

Microdosimetry calculations in situ for clinically relevant photon sources and their correlation with the early DNA damage response

open access: yesMedical Physics, Volume 52, Issue 7, July 2025.
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

Determinação da Distribuição de Dose Absorvida na Água para o Aplicador Oftálmico COC de 106Ru/106Rh Utilizando o Código de Monte Carlo-MCNPX

open access: yesBrazilian Journal of Radiation Sciences, 2015
Os aplicadores oftálmicos COC com fonte emissoras beta de 106Ru/106Rh são utilizados no tratamento de tumores intraoculares próximos ao nervo óptico. Neste tipo de tratamento é muito importante conhecer as distribuições de dose, de modo a proporcionar a ...
nilseia aparecida barbosa
doaj   +1 more source

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