A 3D industrial computed tomography (CT) manufactured based on a first generation CT systems, single-source – single-detector, was evaluated. Operation accuracy assessment of the manufactured system was achieved using simulation in comparison with experimental tests. Cs and Co were used as a gamma source. Simulations were achieved using MCNP4C code. Experimental tests of Cs were in good agreeme...

The weight window variance reduction method in the general-purpose Monte Carlo N-Particle radiation transport code MCNP has recently been rewritten. In particular, it is now possible to generate weight window importance functions on a superimposed mesh, eliminating the need to subdivide geometries for variance reduction purposes. Our assessment addresses the following questions: (1) Does the n...

In this paper MCNP4C code has been used to simulate of the photonuclear interaction induced by 10MeV electron beam is an approach for generating the high intensity neutrons. Since the results are depended on the target material, the calculations are performed for the targets made of high-z elements of Pb, Ta and W in a simple geometry.

This paper is aimed to investigate the design of an optimized neutron radiography system that utilizes the flux of a reactor. Moderation, collimation aspects are studied. A Monte Carlo code, MCNP4C, was utilized to achieve a maximum and more homogenous neutron flux in the collimator outlet next to the image plane, taking into account geometric characteristics. It was possible to obtain a normal...

In this paper we propound a non­destructive and non­invasive technique for measuring the thickness of water penetration in a homogeneous slab. The proposed device consists of a 252 Cf spontaneous fission source and a set of 3 He detectors located on the same side of a concrete slab subject to water infiltration. The effectiveness of this technique has been investigated by Monte Carlo simulation...

It is well known that Intercrystal scattering (ICS) and the parallax effect are two major resolution limiting parameters in current PET detector designs with block detectors. More recently for the purpose of resolution recovery, investigators and manufacturers have attempted to accurately model these effects into the image reconstruction task. In this study we utilized the MCNP4C Monte Carlo co...

Monte Carlo simulations are widely used for calculation of the dosimetric parameters of brachytherapy sources. MCNP4C2, MCNP5, MCNPX, EGS4, EGSnrc, PTRAN, and GEANT4 are among the most commonly used codes in this field. Each of these codes utilizes a cross-sectional library for the purpose of simulating different elements and materials with complex chemical compositions. The accuracies of the f...

High-temperature gas-cooled reactor fuels are composed of thousands of microscopic fuel particles, randomly dispersed in a graphite matrix. The modelling of such geometry is complicated, especially using continuous-energy Monte Carlo codes, which are unable to apply any deterministic corrections in the calculation. This paper presents the geometry routine developed for modelling randomly disper...