A Criticality and depletion analysis of the European Lead-Cooled Training Reactor (ELECTRA)
In this article, a criticality and depletion analysis of the European Lead-Cooled Training Reactor (ELECTRA), a low-power, compact, fast lead-cooled reactor, was performed. The active core model and simulations were made by using the MCNPX code.
Ana Luiza Pereira Oliveira +1 more
doaj +1 more source
Background Calculations for the High Energy Beam Transport Region of the European Spallation Source [PDF]
Expected backgrounds in the final accelerator-to-target region of the European Spallation Source, to be built in Lund, Sweden, have been calculated using the MCNPX program.
Barlow, Roger, Toader, Adina
core +3 more sources
Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources [PDF]
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
Evolution of dose distribution for a <sup>125</sup>I eye plaque using MCNPX and Plaque Simulator software. [PDF]
Abstract Objective Eye plaque radiation therapy is the treatment of choice for small‐ and medium‐sized choroidal melanomas. This study investigated the dose distribution around eye plaques containing 125I seeds to treat ocular melanoma using Monte Carlo N‐Particle eXtended (MCNPX) and Plaque Simulator (PS) software.
Poorbaygi H +6 more
europepmc +2 more sources
Enhance simulation capability of beta-voltaic micro battery using MCNPX-SILVACO hybrid code [PDF]
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
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]
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
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
Utilizing patient data: A tutorial on predicting second cancer with machine learning models. [PDF]
Abstract Background The article explores the potential risk of secondary cancer (SC) due to radiation therapy (RT) and highlights the necessity for new modeling techniques to mitigate this risk. Methods By employing machine learning (ML) models, specifically decision trees, in the research process, a practical framework is established for forecasting ...
Sadeghi H +4 more
europepmc +2 more sources
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

