Results 21 to 30 of about 6,588 (195)

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

Sensitivity analysis of Monte Carlo model of a gantry-mounted passively scattered proton system [PDF]

open access: yes, 2020
PURPOSE: This study aimed to present guidance on the correlation between treatment nozzle and proton source parameters, and dose distribution of a passive double scattering compact proton therapy unit, known as Mevion S250.
Baradaran-Ghahfarokhi, Milad   +4 more
core   +2 more sources

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

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

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

Evaluation of fast fission factor in a typical pool type research reactor [PDF]

open access: yesJournal of Nuclear Research and Applications, 2022
One of the important factors of a nuclear reactor core is the fast fission factor.  This paper calculates this parameter based on space and energy-dependent method using the PTRAC card of MCNPX code. Tehran research reactor (TRR) is taken as a case study,
M. Arkani, S. Khakshournia
doaj   +1 more source

Validation of MCNPX-PoliMi fission models [PDF]

open access: yes2012 IEEE Nuclear Science Symposium and Medical Imaging Conference Record (NSS/MIC), 2012
We present new results on the measurement of correlated, outgoing neutrons from spontaneous fission events in a Cf-252 source. 16 EJ-309 liquid scintillation detectors are used to measure neutron-neutron correlations for various detector angles. Anisotropy in neutron emission is observed.
Sara A. Pozzi   +12 more
openaire   +1 more source

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