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A comparison of Nodal methods in neutron diffusion calculations

Abstract

The nuclear engineering department at IEC uses in the reactor analysis three neutron diffusion codes based on nodal methods. The codes, GNOMERl, ADMARC2 and NOXER3 solve the neutron diffusion equation to obtain flux and power distributions in the core. The resulting flux distributions are used for the furl cycle analysis and for fuel reload optimization. This work presents a comparison of the various nodal methods employed in the above codes. Nodal methods (also called Coarse-mesh methods) have been designed to solve problems that contain relatively coarse areas of homogeneous composition. In the nodal method parts of the equation that present the state in the homogeneous area are solved analytically while, according to various assumptions and continuity requirements, a general solution is sought out. Thus efficiency of the method for this kind of problems, is very high compared with the finite element and finite difference methods. On the other hand, using this method one can get only approximate information about the node vicinity (or coarse-mesh area, usually a feel assembly of a 20 cm size). These characteristics of the nodal method make it suitable for feel cycle analysis and reload optimization. This analysis requires many subsequent calculations of the flux and  More>>
Authors:
Tavron, Barak [1] 
  1. Israel Electric Company, Haifa (Israel) Nuclear Engineering Dept. Research and Development Div.
Publication Date:
Dec 01, 1996
Product Type:
Conference
Report Number:
INIS-mf-15507; CONF-961252-
Reference Number:
SCA: 220100; PA: AIX-28:023669; EDB-97:072408; SN: 97001788817
Resource Relation:
Conference: 19. conference of the Israel Nuclear Societies, Herzliya (Israel), 9-10 Dec 1996; Other Information: PBD: Dec 1996; Related Information: Is Part Of Program and book of abstracts; PB: 149 p.
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; REACTOR PHYSICS; NODAL EXPANSION METHOD; COMPUTER CODES; COMPUTERIZED SIMULATION; FINITE DIFFERENCE METHOD; GREEN FUNCTION; REACTOR LATTICES
OSTI ID:
475942
Research Organizations:
Israel Nuclear Society, Yavne (Israel)
Country of Origin:
Israel
Language:
English
Other Identifying Numbers:
Other: ON: DE97616259; TRN: IL9606170023669
Availability:
INIS; OSTI as DE97616259
Submitting Site:
INIS
Size:
pp. 1-5
Announcement Date:

Citation Formats

Tavron, Barak. A comparison of Nodal methods in neutron diffusion calculations. Israel: N. p., 1996. Web.
Tavron, Barak. A comparison of Nodal methods in neutron diffusion calculations. Israel.
Tavron, Barak. 1996. "A comparison of Nodal methods in neutron diffusion calculations." Israel.
@misc{etde_475942,
title = {A comparison of Nodal methods in neutron diffusion calculations}
author = {Tavron, Barak}
abstractNote = {The nuclear engineering department at IEC uses in the reactor analysis three neutron diffusion codes based on nodal methods. The codes, GNOMERl, ADMARC2 and NOXER3 solve the neutron diffusion equation to obtain flux and power distributions in the core. The resulting flux distributions are used for the furl cycle analysis and for fuel reload optimization. This work presents a comparison of the various nodal methods employed in the above codes. Nodal methods (also called Coarse-mesh methods) have been designed to solve problems that contain relatively coarse areas of homogeneous composition. In the nodal method parts of the equation that present the state in the homogeneous area are solved analytically while, according to various assumptions and continuity requirements, a general solution is sought out. Thus efficiency of the method for this kind of problems, is very high compared with the finite element and finite difference methods. On the other hand, using this method one can get only approximate information about the node vicinity (or coarse-mesh area, usually a feel assembly of a 20 cm size). These characteristics of the nodal method make it suitable for feel cycle analysis and reload optimization. This analysis requires many subsequent calculations of the flux and power distributions for the feel assemblies while there is no need for detailed distribution within the assembly. For obtaining detailed distribution within the assembly methods of power reconstruction may be applied. However homogenization of feel assembly properties, required for the nodal method, may cause difficulties when applied to fuel assemblies with many absorber rods, due to exciting strong neutron properties heterogeneity within the assembly. (author).}
place = {Israel}
year = {1996}
month = {Dec}
}