Abstract
Presented here is a new numerical nodal method for the simulation of the axial power distribution within nuclear reactors using the one-dimensional one speed kinetics diffusion model with one group of delayed neutron precursors. Our method is based on a spectral analysis of the nodal kinetics equations. These equations are obtained by integrating the original kinetics equations separately over a time step and over a spatial node, and then considering flat approximations for the forward difference terms. These flat approximations are the only approximations that are considered in the method. As a result, the spectral nodal method for space - time reactor kinetics generates numerical solutions for space independent problems or for time independent problems that are completely free from truncation errors. We show numerical results to illustrate the method`s accuracy for coarse mesh calculations. (author).
Citation Formats
Barros, R.C. de.
Numerical nodal simulation of the axial power distribution within nuclear reactors using a kinetics diffusion model. I; Simulacao numerica nodal da distribuicao axial de potencia em reatores nucleares usando um modelo cinetico de difusao.I.
Brazil: N. p.,
1992.
Web.
Barros, R.C. de.
Numerical nodal simulation of the axial power distribution within nuclear reactors using a kinetics diffusion model. I; Simulacao numerica nodal da distribuicao axial de potencia em reatores nucleares usando um modelo cinetico de difusao.I.
Brazil.
Barros, R.C. de.
1992.
"Numerical nodal simulation of the axial power distribution within nuclear reactors using a kinetics diffusion model. I; Simulacao numerica nodal da distribuicao axial de potencia em reatores nucleares usando um modelo cinetico de difusao.I."
Brazil.
@misc{etde_10108815,
title = {Numerical nodal simulation of the axial power distribution within nuclear reactors using a kinetics diffusion model. I; Simulacao numerica nodal da distribuicao axial de potencia em reatores nucleares usando um modelo cinetico de difusao.I}
author = {Barros, R.C. de}
abstractNote = {Presented here is a new numerical nodal method for the simulation of the axial power distribution within nuclear reactors using the one-dimensional one speed kinetics diffusion model with one group of delayed neutron precursors. Our method is based on a spectral analysis of the nodal kinetics equations. These equations are obtained by integrating the original kinetics equations separately over a time step and over a spatial node, and then considering flat approximations for the forward difference terms. These flat approximations are the only approximations that are considered in the method. As a result, the spectral nodal method for space - time reactor kinetics generates numerical solutions for space independent problems or for time independent problems that are completely free from truncation errors. We show numerical results to illustrate the method`s accuracy for coarse mesh calculations. (author).}
place = {Brazil}
year = {1992}
month = {May}
}
title = {Numerical nodal simulation of the axial power distribution within nuclear reactors using a kinetics diffusion model. I; Simulacao numerica nodal da distribuicao axial de potencia em reatores nucleares usando um modelo cinetico de difusao.I}
author = {Barros, R.C. de}
abstractNote = {Presented here is a new numerical nodal method for the simulation of the axial power distribution within nuclear reactors using the one-dimensional one speed kinetics diffusion model with one group of delayed neutron precursors. Our method is based on a spectral analysis of the nodal kinetics equations. These equations are obtained by integrating the original kinetics equations separately over a time step and over a spatial node, and then considering flat approximations for the forward difference terms. These flat approximations are the only approximations that are considered in the method. As a result, the spectral nodal method for space - time reactor kinetics generates numerical solutions for space independent problems or for time independent problems that are completely free from truncation errors. We show numerical results to illustrate the method`s accuracy for coarse mesh calculations. (author).}
place = {Brazil}
year = {1992}
month = {May}
}