Monte Carlo Simulation of Neutrons Scattering in the Reactor

Authors

  • Mohana Faroug Saeed Attia
  • Afraa Ibraheim Mohmmed Abdalateif

DOI:

https://doi.org/10.31695/IJASRE.2018.32757

Keywords:

Monte Carlo, Neutron Scattering, Neutron Flux, Energy Spectrum, Diluted, Shield Reactor

Abstract

The significance of Monte Carlo simulation to engineer and scientist is now broadly stated and maximum undergraduates have a few training within the use of computers and feature get right of entry to a laptop for the solution of their issues. Monte Carlo method became used to sample the probability laws that describe the behavior of the neutrons in the reactor Shielding. In this study the principles of Monte Carlo simulation were applied to describe the behavior of the high energy neutrons in two different shielding materials; lead and water, the method used is based on the postulate that the scattering is isotropic. Monte Carlo Simulation used to calculate neutron flux and neutron scattering in the reactor. This study had shown that the shield material of water is the one regarding that is best of energy and collision. The findings will be of interest to agree with theoretical results, showed that Monte Carlo method is a method that is efficient reasonable accuracy. Also, the neutron flux was calculated according to the mixture components, radial, energy spectrum in the reactor system for the selected fluids, library and structural
material. Three-dimensional nucleonic calculations were performed using the Monte Carlo method. The analysis of Monte Carlo undertaken here, to the knowledge of the neutrons attenuation calculation, which is performed for two different materials in terms of their atomic mass numbers, show that the best diluted are those having an atomic mass comparable to the neutron’s mass. Also, other average neutron flux distribution was investigated according to the neutron energy spectrum [0-20 MeV] in the system.

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How to Cite

Mohana Faroug Saeed Attia, & Afraa Ibraheim Mohmmed Abdalateif. (2018). Monte Carlo Simulation of Neutrons Scattering in the Reactor. International Journal of Advances in Scientific Research and Engineering (IJASRE), ISSN:2454-8006, DOI: 10.31695/IJASRE, 4(6`), 51–57. https://doi.org/10.31695/IJASRE.2018.32757