Abstract
A computer program has been developed which uses a technique of synthetic acceleration by diffusion by analytical schemes. Both in the diffusion equation as in that of transport, analytical schemes were used which allowed a substantial time saving in the number of iterations required by source iteration method to obtain the K{sub e}ff. The program developed ASD (Synthetic Diffusion Acceleration) by diffusion was written in FORTRAN and can be executed on a personal computer with a hard disc and mathematical O-processor. The program is unlimited as to the number of regions and energy groups. The results obtained by the ASD program for K{sub e}ff is nearly completely concordant with those of obtained utilizing the ANISN-PC code for different analytical type problems in this work. The ASD program allowed obtention of an approximate solution of the neutron transport equation with a relatively low number of internal reiterations with good precision. One of its applications would be in the direct determinations of axial distribution neutronic flow in a fuel assembly as well as in the obtention of the effective multiplication factor. (Author).
Citation Formats
Alonso-Vargas, G.
Numerical solution of the equation of neutrons transport on plane geometry by analytical schemes using acceleration by synthetic diffusion; Solucion numerica de la ecuacion de transporte de neutrones en geometria plana mediante esquemas analiticos empleando aceleracion por difusion sintetica.
Mexico: N. p.,
1991.
Web.
Alonso-Vargas, G.
Numerical solution of the equation of neutrons transport on plane geometry by analytical schemes using acceleration by synthetic diffusion; Solucion numerica de la ecuacion de transporte de neutrones en geometria plana mediante esquemas analiticos empleando aceleracion por difusion sintetica.
Mexico.
Alonso-Vargas, G.
1991.
"Numerical solution of the equation of neutrons transport on plane geometry by analytical schemes using acceleration by synthetic diffusion; Solucion numerica de la ecuacion de transporte de neutrones en geometria plana mediante esquemas analiticos empleando aceleracion por difusion sintetica."
Mexico.
@misc{etde_10128027,
title = {Numerical solution of the equation of neutrons transport on plane geometry by analytical schemes using acceleration by synthetic diffusion; Solucion numerica de la ecuacion de transporte de neutrones en geometria plana mediante esquemas analiticos empleando aceleracion por difusion sintetica}
author = {Alonso-Vargas, G}
abstractNote = {A computer program has been developed which uses a technique of synthetic acceleration by diffusion by analytical schemes. Both in the diffusion equation as in that of transport, analytical schemes were used which allowed a substantial time saving in the number of iterations required by source iteration method to obtain the K{sub e}ff. The program developed ASD (Synthetic Diffusion Acceleration) by diffusion was written in FORTRAN and can be executed on a personal computer with a hard disc and mathematical O-processor. The program is unlimited as to the number of regions and energy groups. The results obtained by the ASD program for K{sub e}ff is nearly completely concordant with those of obtained utilizing the ANISN-PC code for different analytical type problems in this work. The ASD program allowed obtention of an approximate solution of the neutron transport equation with a relatively low number of internal reiterations with good precision. One of its applications would be in the direct determinations of axial distribution neutronic flow in a fuel assembly as well as in the obtention of the effective multiplication factor. (Author).}
place = {Mexico}
year = {1991}
month = {Dec}
}
title = {Numerical solution of the equation of neutrons transport on plane geometry by analytical schemes using acceleration by synthetic diffusion; Solucion numerica de la ecuacion de transporte de neutrones en geometria plana mediante esquemas analiticos empleando aceleracion por difusion sintetica}
author = {Alonso-Vargas, G}
abstractNote = {A computer program has been developed which uses a technique of synthetic acceleration by diffusion by analytical schemes. Both in the diffusion equation as in that of transport, analytical schemes were used which allowed a substantial time saving in the number of iterations required by source iteration method to obtain the K{sub e}ff. The program developed ASD (Synthetic Diffusion Acceleration) by diffusion was written in FORTRAN and can be executed on a personal computer with a hard disc and mathematical O-processor. The program is unlimited as to the number of regions and energy groups. The results obtained by the ASD program for K{sub e}ff is nearly completely concordant with those of obtained utilizing the ANISN-PC code for different analytical type problems in this work. The ASD program allowed obtention of an approximate solution of the neutron transport equation with a relatively low number of internal reiterations with good precision. One of its applications would be in the direct determinations of axial distribution neutronic flow in a fuel assembly as well as in the obtention of the effective multiplication factor. (Author).}
place = {Mexico}
year = {1991}
month = {Dec}
}