Results 21 to 30 of about 5,690 (213)

Characterization of the light and flexible nonlead aprons as an alternative to Pb-PVC. [PDF]

open access: yesJ Appl Clin Med Phys
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.
Khorami MT, Salehi Z.
europepmc   +2 more sources

Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources [PDF]

open access: yesNuclear Technology and Radiation Protection, 2023
The present work concerns the development of a technique for activity determination of 68Ge/68Ga and 57Co disused radioactive sources. This technique aims to determine the activity of these sources by measuring and Monte Carlo simulation using ...
Mavrikis Dimitris   +5 more
doaj   +1 more source

Enhance simulation capability of beta-voltaic micro battery using MCNPX-SILVACO hybrid code [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2020
The accuracy of each simulating beta-voltaic battery parameter is very important, especially in micro-batteries. The aim of this study is to improve the calculation of beta-battery parameters’ accuracy. For this purpose, at first, using the Monte Carlo N-
P. Maleki, Gh.R. Etaati
doaj   +1 more source

An MCNPX accelerator beam source

open access: yesProgress in Nuclear Energy, 2009
Abstract We have developed a new source feature for MCNPX that enables the transport of particles in a field-free drift region for a beam produced by an accelerator. The beam representation is based on the formulation used in the TRANSPORT charged-particle-beam code.
Joe Durkee   +4 more
openaire   +3 more sources

Modeling the NHEJ repair of DNA damage induced by electrons calculated using the MCNPX and Geant4-DNA codes [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2022
In radiotherapy, ionizing radiation is used to damage cells. Monte Carlo simulations of radiation interactions with DNA give us good information about the type of damage and their repair process, which can be very useful in treating cancer and protecting
Sh. Farazmand, M. Mokari, M.H. Alamatsaz
doaj   +1 more source

Calculation of photoneutron contamination of varian linac in icru soft-tissue phantom using MCNPX code

open access: yesJournal of Medical Physics, 2021
Purpose: The aim of this research was to calculate the fluence, dose equivalent (DE), and kerma of thermal, epithermal and fast photoneutrons separately, within ICRU soft-tissue-equivalent phantom in the radiotherapy treatment room, using MCNPX Monte ...
Mojtaba Cheraghian   +3 more
doaj   +1 more source

Low-energy neutron propagation in MCNPX and GEANT4 [PDF]

open access: yesNuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2006
Simulations of neutron background from rock for underground experiments are presented. Neutron propagation through two types of rock, lead and hydrocarbon material is discussed. The results show a reasonably good agreement between GEANT4, MCNPX and GEANT3 in transporting low-energy neutrons.
Lemrania, R.   +5 more
openaire   +3 more sources

Diagnostic and therapeutic radioisotopes in nuclear medicine: Determination of gamma-ray transmission factors and safety competencies of high-dense and transparent glassy shields

open access: yesOpen Chemistry, 2022
We present the findings of an extensive examination on newly designed CdO-rich and transparent glass shields for nuclear medicine facilities in lieu of traditional and unfavorable materials, such as lead and concrete.
Erdemir Rabiye Uslu   +7 more
doaj   +1 more source

Americium-beryllium shield container optimization with new high alloyed stainless steel and composite material using MCNPX code [PDF]

open access: yesNuclear Technology and Radiation Protection, 2023
In this paper the goal is to optimize a shield for the americium-beryllium radioactive source, which generates a mixed neutron and gamma-ray radiation field, using two different materials designed with simultaneous moderation and absorption of ...
Hooshmand Fini Ali   +2 more
doaj   +1 more source

Cálculo, usando o código MCNPX, de doses equivalentes no tratamento 3D-CRT de câncer de próstata, com gantry operando a 45°, 135°, 225° e 315°

open access: yesBrazilian Journal of Radiation Sciences, 2020
O Instituto Nacional do Câncer José Alencar Gomes da Silva - INCA adota como protocolo padrão no tratamento de câncer de próstata, na técnica de Radioterapia Tridimensional Conformada (3D-CRT), o uso da incidência do feixe em 4 angulos, 0°, 90º , 180º e ...
Eduardo Fonseca   +5 more
doaj   +1 more source

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