Published November 1988
| Version v1
Journal article
Mixed and mixed-hybrid elements for the diffusion equation
Creators
- 1. Centre d'Etudes Nucleaires de Saclay, Dept. des Etudes Mecaniques et Thermiques, Service d'Etudes des Reacteurs et de Mathematiques Appliquees, Gif-sur-Yvette (France)
Description
Among the classical methods used for solving the neutron diffusion equation, the Lagrange finite element method can be efficiently implemented to provide a fast numerical treatment. Mixed elements are used because they allow simultaneous approximations for the flux and its gradient of the same order. Although the linear systems produced are not positive definite, a solution ca be achieved after eliminating some of the unknowns. Numerical results include core calculations of two types of reactors
Additional details
Publishing Information
- Journal Title
- Nuclear Science and Engineering
- Journal Volume
- 100
- Journal Issue
- 3
- Series
- Nucl. Sci. Eng.
- Journal Page Range
- 218-225
- ISSN
- 0029-5639
- CODEN
- NSENA
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20057129
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALGORITHMS; DIFFUSION; EQUATIONS; FINITE ELEMENT METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; NUMERICAL SOLUTION; REACTOR CORES
- Descriptors DEC
- NEUTRAL-PARTICLE TRANSPORT; RADIATION FLUX; RADIATION TRANSPORT; REACTOR COMPONENTS