A power cable is the most important part in a power transmission system. The cables must be total quality dedicated and certified for development, manufacturing and installation, however are exposed to a corrosive environment. The purpose of this paper is to show that the fast neutron radiography with a transportable system is a solution to find defects in the cables and reduce the cost of insp...

Neutrons are primarily produced at large international facilities using either spallation reactions or nuclear fission. There is a demand for small scale neutron production for use at hospitals and borders for a variety of applications. Isolated fission sources and sealed tube deuterium-tritium fusors are able to provide a reliable neutron flux at small scale but are impractical due to the asso...

Large quantities of radiopharmaceuticals prescribed for treatment and diagnosis are excreted through kidney. Therefore, radiation unwanted dose is created in kidney. As a result, exact calculation of prescribed radiopharmaceuticals amount is important. Monte Carlo method is used for simulation of radiation transport in body due to random nature of radiation. In this research, for the first time...

Here, the characterisation of the high-energy neutron field at TRIUMF (The Tri Universities Meson Facility, Vancouver, British Columbia) with Monte Carlo simulation software is described. The package used is MCNPX version 2.6.0, with the neutron fluence rate determined at three locations within the TRIUMF Thermal Neutron Facility (TNF), including the exit of the neutron channel where users of t...

Different types the spectrum of photons were studied; they were emitted from the flattening filter of a LINAC Varian 2100 C/D that operates at 15 MV. The simplified geometry of the LINAC head was calculated using the MCNPX code based on the studies of the materials of the flattening filter, namely, SST, W, Pb, Fe, Ta, Al, and Cu. These materials were replaced in the flattening filter to calcula...

a Department of physics, faculty of science, Takestan Branch, Islamic Azad University,Takestan, IRAN. b Engineering Department, Shahid Beheshti University, G.C., P.O. Box 1983963113, Tehran, IRAN. ________________________________________________________________________________________ Abstract: Absorption dose distribution of onion powder in electron irradiation system has been numerically inve...

The present work concerns the development of a technique for activity determination 68Ge/68Ga and 57Co disused radioactive sources. This aims to determine these sources by measuring Monte Carlo simulation using MCNPX code. Therefore, efficiency calibrations 3 x NaI(Tl) detector specific source geometries were carried out. Spectrums two types collected different measurement times. characteristic...

This study aimed to perform an extensive characterization of a 74.75TeO2–0.25V2O5–(25 − x)B2O3-xNd2O3 glass system with (x = 0, 0.5, 1.0, and 1.5 mol%) for radiation shielding properties. Linear mass attenuation coefficients were determined using Phy-X PSD software compared the simulation Monte Carlo MCNPX (version 2.7.0). Half value layer, mean free path, tenth effective atomic number, exposur...

A conventional Bonner Sphere (BS) set consisting of six polyethylene spheres was modified to enhance its response to a high-energy neutron by putting a lead shell inside a polyethylene moderator. The response matrix of an extended BS was calculated using the MCNPX code and calibrated using a 252Cf neutron source. In order to survey the unknown photon and neutron mixed field, a spherical tissue ...

Modeling the radio-induced effects in biological medium still requires accurate physics models to describe the interactions induced by all the charged particles present in the irradiated medium in detail. These interactions include inelastic as well as elastic processes. To check the accuracy of the very low energy models recently implemented into the GEANT4 toolkit for modeling the electron sl...