Published 1983
| Version v1
Book
The use of a finite-difference scheme to improve the accuracy of the Modal Expansion Method
Creators
- 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