With the advent of inexpensive computing power over the past two decades, applications of Monte Carlo radiation transport techniques have proliferated dramatically. At Los Alamos, the Monte Carlo codes MCNP5 [1] and MCNPX [2] are used routinely on personal computer platforms for radiation shielding analysis and dosimetry calculations. These codes are attractive for such applications because of ...

abstractbackground: an electron beam generated x-ray spectrum consists of characteristic x-ray and continuous bermsstrahlung. the aim of this research is calculating and comparing x-ray spectra for different target filter of mammograms. materials and methods: monte carlo is a very powerful tool to simulate a series of different target-filter assembly in order to calculate the x-ray spectra. mcn...

Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal. (August 2012) Joe Justina, M.Sc., Mangalore University Co-Chairs of Advisory Committee: Dr. Craig M. Marianno Dr. Sunil S. Chirayath A large radiological accident will result in the contamination of surrounding people, animal, vegetation etc. In such a s...

BACKGROUND Obtaining high quality images in Single Photon Emission Tomography (SPECT) device  is the most important goal in nuclear medicine. Because if image quality is low, the possibility of making a mistake in diagnosing and treating the patient will rise. Studying effective factors in spatial resolution of imaging systems is thus deemed to be vital. One of the most important factors in SPE...

Interface software was developed to generate the input file to run Monte Carlo MCNP-4B code from medical image in Interfile format version 3.3. The software was tested using a spherical phantom of tomography slides with known cumulated activity distribution in Interfile format generated with IMAGAMMA medical image processing system. The 3D dose calculation obtained with Monte Carlo MCNP-4B code...

The dose distribution inside the Gamma Cobalt irradiation therapy unit at Egyptian Atomic Energy Authority (EAEA) was determined both experimentally and theoretically. MCNP computer code, based on Monte Carlo method, was used to model the unit and calculate the dose distributions in both normal and emergency situation of the unit. The dose distribution inside the unit was also measured during t...

A binary formatwith lists of particle state information, for interchanging particles between variousMonte Carlo simulation applications, is presented. Portable C code for file manipulation is made available to the scientific community, along with converters and plugins for several popular simulation packages. Program summary Program Title:MCPL Program Files doi: http://dx.doi.org/10.17632/cby92...

Pohang Neutron Facility (PNF) is a pulsed neutron facility based on the 100-MeV electron linear accelerator. It was constructed for nuclear data production in Korea, and it consists of an electron linear accelerator, a watercooled Ta target with a water moderator and a time-offlight path with an 11 m length. The 100-MeV electron linac uses a thermionic RF-gun, an alpha magnet, four quadrupole m...