Published 1983 | Version v1
Book

The use of a finite-difference scheme to improve the accuracy of the Modal Expansion Method

  • 1. Atomic Energy of Canada, Ltd., CANDU-Operations, Sheridan Park Res. Community, Mississauga, Ontario L5K 1B2

Description

The limitation of the Modal Expansion Method for solving the static neutron diffusion equation is demonstrated for cases where the perturbation consists of reactivity device movement. A modification, based on the finite-difference method is applied in regions which contain the reactivity devices. The results show that the error in the calculated reactivity is reduced by a factor between 4 and 10. The error in the maximum bundle and channel power is reduced by a factor of between 1.2 and 6. The computation cost per solution is less than $2.00 on the CDC 6600. The method is useful for analyses that require a relatively large number of approximate solutions to the static neutron diffusion equation

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
LaGrange Park, IL (USA)
ISBN
0-919784-02-X
Imprint Title
Proceedings of the international conference on numerical methods in nuclear engineering. Volume 1
Journal Page Range
p. 673-689.

Conference

Title
International conference on numerical methods in nuclear engineering.
Dates
6-9 Sep 1983.
Place
Montreal (Canada).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17051529
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; COST; DISTURBANCES; ERRORS; FINITE DIFFERENCE METHOD; FUEL ELEMENT CLUSTERS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION; REACTIVITY; REACTOR CORES
Descriptors DEC
FUEL ASSEMBLIES; ITERATIVE METHODS; REACTOR COMPONENTS; TRANSPORT THEORY