Solução da equação de cinética de difusão de nêutrons em geometria cilíndrica tridimensional

Content Provider	Semantic Scholar
Author	Oliveira, Fernando Rodrígues De
Copyright Year	2017
Abstract	The present work solves the problem of spatial neutron diffusion kinetics in cylindrical geometry analytically. The solution is analytical in the sense that no approximation is made in its derivation. For this, we approach the study of the problem of spatial kinetics in three ways, firstly, we consider the technique of separation of variables to solve the monoenergetic problem, with that we determine the appropriate spatial eigenfunctions and analyze the entire spectrum according to the boundary conditions. In addition, considering the same monoenergetic model, we determined a solution for a heterogeneous medium considering two adjacent homogeneous cylindrical cells. The heterogeneity of the problem is due to the fact that each cylindrical section has a set of different nuclear parameters. Subsequently, we study the problem of spatial kinetics considering a multigroup model with G energy groups and with I groups of delayed neutron precursors. The basic idea of the solution is to assume that scalar fluxes and concentrations of delayed neutron precursors can be expressed as the product of spatial functions by time functions and, with that, we were able to determine the solution of the decoupled kinetic problem, solving an PDE for the spatial functions and solving the system of ODEs for the temporal functions. We present some numerical simulations to validate the theoretical study done in the development of this research.
File Format	PDF HTM / HTML
Alternate Webpage(s)	https://www.lume.ufrgs.br/bitstream/handle/10183/163946/001025964.pdf?isAllowed=y&sequence=1
Language	English
Access Restriction	Open
Content Type	Text
Resource Type	Article