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Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I; Comparacion entre un modelo de diferencias finitas (PUMA) y uno de elementos finitos (DELFIN) para la simulacion del reactor de la CNA-I (central nuclear Atucha-I)

Abstract

The reactor code PUMA, developed in CNEA, simulates nuclear reactors discretizing space in finite difference elements. Core representation is performed by means a cylindrical mesh, but the reactor channels are arranged in an hexagonal lattice. That is why a mapping using volume intersections must be used. This spatial treatment is the reason of an overestimation of the control rod reactivity values, which must be adjusted modifying the incremental cross sections. Also, a not very good treatment of the continuity conditions between core and reflector leads to an overestimation of channel power of the peripherical fuel elements between 5 to 8 per cent. Another code, DELFIN, developed also in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and current among elements and a more realistic representation of the hexagonal lattice of the reactor. A comparison between results obtained using both methods in done in this paper. (author). 4 refs., 3 figs.
Authors:
Grant, C R [1] 
  1. Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares
Publication Date:
Dec 31, 1996
Product Type:
Miscellaneous
Report Number:
INIS-AR-121; CONF-961181-
Reference Number:
SCA: 210400; 990200; PA: AIX-28:076121; EDB-97:143854; SN: 97001880527
Resource Relation:
Conference: International conference on nuclear power competitiveness in the next two decades, Buenos Aires (Argentina), 18-21 Nov 1996; Other Information: PBD: 1996; Related Information: Is Part Of Proceedings of the international conference on nuclear power competitiveness in the next two decades; PB: 335 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; ATUCHA REACTOR; COMPARATIVE EVALUATIONS; D CODES; H CODES; CONTROL ELEMENTS; EVALUATED DATA; FINITE DIFFERENCE METHOD; FINITE ELEMENT METHOD; MODERATELY ENRICHED URANIUM; NATURAL URANIUM; REACTOR CELLS; REACTOR SIMULATORS; T CODES
OSTI ID:
545951
Research Organizations:
Asociacion Argentina de Tecnologia Nuclear, Buenos Aires (Argentina); Comision Nacional de Energia Atomica, Buenos Aires (Argentina)
Country of Origin:
Argentina
Language:
Spanish
Other Identifying Numbers:
Other: ON: DE98603571; TRN: AR9700027076121
Availability:
INIS; OSTI as DE98603571
Submitting Site:
INIS
Size:
pp. 57-63
Announcement Date:

Citation Formats

Grant, C R. Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I; Comparacion entre un modelo de diferencias finitas (PUMA) y uno de elementos finitos (DELFIN) para la simulacion del reactor de la CNA-I (central nuclear Atucha-I). Argentina: N. p., 1996. Web.
Grant, C R. Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I; Comparacion entre un modelo de diferencias finitas (PUMA) y uno de elementos finitos (DELFIN) para la simulacion del reactor de la CNA-I (central nuclear Atucha-I). Argentina.
Grant, C R. 1996. "Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I; Comparacion entre un modelo de diferencias finitas (PUMA) y uno de elementos finitos (DELFIN) para la simulacion del reactor de la CNA-I (central nuclear Atucha-I)." Argentina.
@misc{etde_545951,
title = {Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I; Comparacion entre un modelo de diferencias finitas (PUMA) y uno de elementos finitos (DELFIN) para la simulacion del reactor de la CNA-I (central nuclear Atucha-I)}
author = {Grant, C R}
abstractNote = {The reactor code PUMA, developed in CNEA, simulates nuclear reactors discretizing space in finite difference elements. Core representation is performed by means a cylindrical mesh, but the reactor channels are arranged in an hexagonal lattice. That is why a mapping using volume intersections must be used. This spatial treatment is the reason of an overestimation of the control rod reactivity values, which must be adjusted modifying the incremental cross sections. Also, a not very good treatment of the continuity conditions between core and reflector leads to an overestimation of channel power of the peripherical fuel elements between 5 to 8 per cent. Another code, DELFIN, developed also in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and current among elements and a more realistic representation of the hexagonal lattice of the reactor. A comparison between results obtained using both methods in done in this paper. (author). 4 refs., 3 figs.}
place = {Argentina}
year = {1996}
month = {Dec}
}