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...

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 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 ...

Neutron response functions of a phoswich neutron detector and thin organic liquid scintillator were simulated using the multi-purpose Monte Carlo code MCNPX, incorporating functions of light outputs, energy resolutions, and uniformity of scintillation. The simulated response functions were verified by response-function measurement for high-energy neutrons produced by bombarding thin lithium tar...