نتایج جستجو برای: mcnp x

تعداد نتایج: 623959  

Journal: :journal of paramedical sciences 0
rouhollah adeli central iran research complex (yazd), nuclear science and technology research institute (nstri), iran. seyed pezhman shirmardi central iran research complex (yazd), nuclear science and technology research institute (nstri), iran. jamal amiri department of radiotherapy, faculty of paramedical sciences, kurdistan university of medical sciences, sanandaj, iran v.p. singh department of physics, karnataka university, dharwad 580003, india. m.e. medhat experimental nuclear physics departments, nuclear research centre, p.o.13759, cairo, egypt

monte carlo method is a very accurate method to optimize medical diagnostic radiology spectra and simulation of radiation transportation. using mcnp code, radiology and mammography attenuated x-rayspectraweresimulated.the ipem report number 78 was used as a reference to compare with the geant4 and mcnp simulations because of its popularity and wide availability. the results of geant4 in 40kev s...

2010
A. Mehranian M. R. Ay H. Zaidi

We introduce a fast and well-structured package for constructing voxel-based computational phantoms as MCNP(X) input file based on CT DICOM images. Our program which has been implemented under a graphic user inter-face provides several basic image processing tools for manipulating images. The MCNP materials are interpreted from the CT numbers of DICOM images. Two modes of phantom creation have ...

2005
R. Jeraj

MCNP is widely used Monte Carlo program in reactor and nuclear physics. However, an option of simulating electrons was added into the code a few years ago. With this extension MCNP became a code, potentially applicable for applications in medical physics. In 1997, a new version of the code, named MCNP4B was released, which contains several improvements in electron transport modelling. To test s...

2000
PJ Collins FW Schultz

INTRODUCTION Monte Carlo (MC) methods have become the "gold standard" for assessing dose distribution, organ doses and effective dose associated with the exposure, both external and internal, of humans to ionizing radiation. Powerful and sophisticated tools for simulation of radiation transport (for example, MCNP, EGS4) are now widely available. However, these codes are designed for general-pur...

Journal: :Environmental pollution 2009
A A Koelmans B Nowack M R Wiesner

In this paper, we show that concentrations of manufactured carbon-based nanoparticles (MCNPs) in aquatic sediments will be negligible compared to levels of black carbon nanoparticles (BCNPs). This is concluded from model calculations accounting for MCNP sedimentation fluxes, removal rates due to aggregation or degradation, and MCNP burial in deeper sediment layers. The resultant steady state MC...

2011
M. Giglioli

A great challenge in simulations in the area of radiotherapy is to character the source, since the equipment’s manufacturers don’t provide specifics information about this. This work presents an empiric method for characterization of the ray-X beams of 6,0 MV and 10 MV originating from a linear accelerator of the mark Varian model 2100C. The experimental values of the percentage of deep dose (P...

ژورنال: سنجش و ایمنی پرتو 2020

Radiation protection and the selection of suitable materials to reduce radiation effects is one of the important branches of medical science and radiation. In this paper, the mass attenuation coefficients, half value layer thicknesses and thicknesses of 0/5 mm lead of polyvinyl chloride (PVC) composites containing Nano and micro-particles of copper oxide are calculated using experimental method...

A. Bozkurt, G. Kemikler, H. Acun,

Background: This study aims to calculate the air-kerma strength (SK), the dose rate constant (∧) and the dose rate profiles of a Gammamed 12i Ir-192 source by using the Monte Carlo technique and to compare the dose rate values with those calculated by the Abacus HDR treatment planning system (TPS). Materials and Methods: Air-kerma strength (in units of U; 1 U= μGy m2 h-1) and the dose ra...

2012
Matthew R. Halstead Sangjin Lee James Petrosky Abigail Bickley Paul Sokol

The energy spectrum of the Neutron Radiation Effects Program (NREP) beam line, Target-ModeratorReflector-1 (TMR-1), at Indiana University has not been previously characterized. The facility has a unique proton source with variable pulse length (15-600 s) and energy (13 MeV). Thus, it can produce a unique and tailored neutron beam when incident on a beryllium target. Through a combination of MCN...

 ABSTRACTBackground: Monte Carlo simulation has been used by many researchers to calculate organ and effective dose of patients arising from conventional X-ray examinations. In this study the radiation transport code, MCNP-4C, has been used to perform Monte Carlo simulations to estimate radiation dose delivered to different organs in conventional X-ray examinations.Material and Methods: In this...

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