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Numerical solution of the Neutron Transport Equation using discontinuous nodal methods at X-Y geometry; Solucion numerica de la ecuacion de transporte de neutrones usando metodos nodales discontinuos en geometria X-Y

Abstract

The purpose of this work is to solve the neutron transport equation in discrete-ordinates and X-Y geometry by developing and using the strong discontinuous and strong modified discontinuous nodal finite element schemes. The strong discontinuous and modified strong discontinuous nodal finite element schemes go from two to ten interpolation parameters per cell. They are describing giving a set D{sub c} and polynomial space S{sub c} corresponding for each scheme BDMO, RTO, BL, BDM1, HdV, BDFM1, RT1, BQ and BDM2. The solution is obtained solving the neutron transport equation moments for each nodal scheme by developing the basis functions defined by Pascal triangle and the Legendre moments giving in the polynomial space S{sub c} and, finally, looking for the non singularity of the resulting linear system. The linear system is numerically solved using a computer program for each scheme mentioned . It uses the LU method and forward and backward substitution and makes a partition of the domain in cells. The source terms and angular flux are calculated, using the directions and weights associated to the S{sub N} approximation and solving the angular flux moments to find the effective multiplication constant. The programs are written in Fortran language, using the dynamic  More>>
Authors:
Publication Date:
Dec 31, 1996
Product Type:
Thesis/Dissertation
Report Number:
INIS-MX-046
Reference Number:
SCA: 990200; PA: AIX-29:023445; EDB-98:057201; SN: 98001957223
Resource Relation:
Other Information: TH: Thesis (M. in Sci.).; PBD: 1996
Subject:
99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; BENCHMARKS; BOUNDARY CONDITIONS; COORDINATES; DISCRETE ORDINATE METHOD; FORTRAN; GEOMETRY; LEGENDRE POLYNOMIALS; MULTIGROUP THEORY; NEUTRON TRANSPORT THEORY; NODAL EXPANSION METHOD; NUMERICAL SOLUTION
OSTI ID:
603524
Research Organizations:
Instituto Politecnico Nacional, Mexico City (Mexico). Escuela Superior de Fisica y Matematicas.
Country of Origin:
Mexico
Language:
Spanish
Other Identifying Numbers:
Other: ON: DE98620840; TRN: MX9800030023445
Availability:
INIS; OSTI as DE98620840
Submitting Site:
INIS
Size:
220 p.
Announcement Date:
Jun 09, 1998

Citation Formats

Delfin L, A. Numerical solution of the Neutron Transport Equation using discontinuous nodal methods at X-Y geometry; Solucion numerica de la ecuacion de transporte de neutrones usando metodos nodales discontinuos en geometria X-Y. Mexico: N. p., 1996. Web.
Delfin L, A. Numerical solution of the Neutron Transport Equation using discontinuous nodal methods at X-Y geometry; Solucion numerica de la ecuacion de transporte de neutrones usando metodos nodales discontinuos en geometria X-Y. Mexico.
Delfin L, A. 1996. "Numerical solution of the Neutron Transport Equation using discontinuous nodal methods at X-Y geometry; Solucion numerica de la ecuacion de transporte de neutrones usando metodos nodales discontinuos en geometria X-Y." Mexico.
@misc{etde_603524,
title = {Numerical solution of the Neutron Transport Equation using discontinuous nodal methods at X-Y geometry; Solucion numerica de la ecuacion de transporte de neutrones usando metodos nodales discontinuos en geometria X-Y}
author = {Delfin L, A}
abstractNote = {The purpose of this work is to solve the neutron transport equation in discrete-ordinates and X-Y geometry by developing and using the strong discontinuous and strong modified discontinuous nodal finite element schemes. The strong discontinuous and modified strong discontinuous nodal finite element schemes go from two to ten interpolation parameters per cell. They are describing giving a set D{sub c} and polynomial space S{sub c} corresponding for each scheme BDMO, RTO, BL, BDM1, HdV, BDFM1, RT1, BQ and BDM2. The solution is obtained solving the neutron transport equation moments for each nodal scheme by developing the basis functions defined by Pascal triangle and the Legendre moments giving in the polynomial space S{sub c} and, finally, looking for the non singularity of the resulting linear system. The linear system is numerically solved using a computer program for each scheme mentioned . It uses the LU method and forward and backward substitution and makes a partition of the domain in cells. The source terms and angular flux are calculated, using the directions and weights associated to the S{sub N} approximation and solving the angular flux moments to find the effective multiplication constant. The programs are written in Fortran language, using the dynamic allocation of memory to increase efficiently the available memory of the computing equipment. (Author).}
place = {Mexico}
year = {1996}
month = {Dec}
}