Paper Profile


A Mesh-Free Method for Approximate Solution of Neutron Transport Equation


Documents: Full paper available in Conference Proceedings.
 
Date: Tuesday October 20
Time:10:20 - 10:45
 
Session:2A3: Reactor Physics II
 
Authors: Dimitar Altiparmakov (Canadian Nuclear Laboratories (Retired))
Abstract:

This paper presents a new method for approximate solution of the multigroup neutron transport equation. The R-function theory is applied to describe the geometric shape of material regions analytically. Resulting formulae form a basis for a mesh-free approximation of the spatial neutron flux distribution. The method of moments is applied to transform the integral transport equation into a system of linear algebraic equations. Calculations of characteristic twodimensional CANDU lattice problems show that the method is capable of accurate modeling of the neutron transport with a significant reduction of the number of unknowns compared to standard mesh-based approximations.

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