Results 31 to 40 of about 1,181 (179)

Simulating Proton Radiation Tolerance of Perovskite Solar Cells for Space Applications

open access: yesAdvanced Energy and Sustainability Research, Volume 4, Issue 12, December 2023., 2023
Dang‐Thuan and co‐authors suggest a novel approach for predicting proton‐radiated degradation in perovskite solar cells. They combine ion scattering and optoelectronic simulations to overcome experimental constraints. FAMAPbI3‐based (lighter materials) cells show higher radiation tolerance than CsPbI2Br (heavier materials).
Dang-Thuan Nguyen   +4 more
wiley   +1 more source

Determination of gamma-ray transmission factors of WO3–TeO2–B2O3 glasses using MCNPX Monte Carlo code for shielding and protection purposes

open access: yesApplied Rheology, 2022
The aim of this study is to assess the individual gamma-ray transmission factors (TFs) and some fundamental gamma-ray attenuation properties of several types of glasses based on WO3–TeO2–B2O3 glasses system.
ALMisned Ghada   +6 more
doaj   +1 more source

Neutronic Evaluation of MSBR System Using MCNP Code

open access: yesBrazilian Journal of Radiation Sciences, 2021
The concept of Molten Salt Reactor use Th to breed fissile 233U, where an initial source of fissile material needs to be provided. However, there is no available 233U and so; the fissile fuel supply is one of the unresolved problems.
Clarysson Alberto Mello da Silva   +3 more
doaj   +1 more source

Evaluating the induced photon contamination by different breast IOERT shields using Monte Carlo simulation

open access: yesJournal of Applied Clinical Medical Physics, Volume 24, Issue 11, November 2023., 2023
Abstract Background and Objective Avoiding the underlying healthy tissue over‐exposure during breast intraoperative electron radiotherapy (IOERT) is owing to the use of some dedicated radioprotection disks during patient irradiation. The originated contaminant photons from some widely used double‐layered shielding disks including PMMA+Cu, PTFE+steel ...
Hamid Reza Baghani, Mostafa Robatjazi
wiley   +1 more source

Validation and study of different parameters in the simulation of diagnostic X-ray spectra using the MCNPX code

open access: yesBrazilian Journal of Radiation Sciences, 2023
In radiology, knowing the X-ray spectrum characteristics makes it possible to estimate the absorbed dose in the patient and to improve image quality. In this study, an X-ray generator was proposed using the MCNPX code and to validate it, the simulated ...
K.C.W. Consatti   +3 more
doaj   +1 more source

Beta-backscattering Thickness-meter Design and Evaluation with Fuzzy TOPSIS Method

open access: yesNukleonika, 2014
An industrial gauge for measuring thickness of a gold coating layer deposited on a steel base through detection of the backscattered beta particles has been described.
Arjhangmehr Afshin   +3 more
doaj   +1 more source

The comparison of five neutron sources via 7Li(p,n) reaction for the design of a facility based on prompt gamma ray neutron activation analysis (PGNAA) in vivo detections of boron [PDF]

open access: yesActa Periodica Technologica, 2020
Prompt Gamma Ray Neutron Activation Analysis (PGNAA) is a useful nondestructive method with numerous applications. In this study neutron yield from 7Li(p,n) reaction with proton energies of 2.5, 3, 4, 4.5 and 5 MeV was used in order to provide ...
Fantidis J.G., Nicolaou G.E.
doaj   +1 more source

Monte Carlo analysis of energy deposition and X-ray fluence in cylindrical anode systems. [PDF]

open access: yesJ Appl Clin Med Phys
Abstract Background Cylindrical anode X‐ray systems are increasingly used in multisource imaging; however, electron beam interactions with the curved anodes cause geometric distortions that alter energy deposition and X‐ray emission. Understanding these effects is key to optimizing system performance.
Alharbi MKM   +4 more
europepmc   +2 more sources

Monitoring internal contamination from OEW of an 18F-FDG production plant: WBC or head counting setup?

open access: yesBrazilian Journal of Radiation Sciences, 2019
The production 18F-FDG for positron emission tomography (PET) has consistently increased over the past two decades. The risk of internal contamination at 18F-FDG production facilities exists.
Bruno Melo Mendes   +3 more
doaj   +1 more source

Estudo do fluxo neutrônico no reator IPR-R1 com o MCNPX

open access: yesBrazilian Journal of Radiation Sciences, 2016
Neste trabalho utilizou-se o código computacional MCNPX, uma das versões mais recentes do código de transporte MCNP, com o objetivo de estudar a distribuição do fluxo e sua fluência neutrônica em função da energia em dois dispositivos de irradiação do ...
Júlio Ângelo de Souza Melo   +2 more
doaj   +1 more source

Home - About - Disclaimer - Privacy