Published December 1991
| Version v1
Journal article
Deterministic approximations for the neutron transport equation
Description
Three deterministic numerical methods were developed at the CEA/DAM to solve the bi-dimensional axisymmetric multigroup transport equation for neutrons. On an orthogonal zoning, we use the finite volume method which is the cheapest one for a given accuracy. To solve the problem on general zonings, which are commonly made of quadrilaterals, we built two finite element methods: a discontinuous one, which can be applied to the transport equation, and a continuous one, which is bound to the even party flux formulation. (author). 17 refs., 5 figs., 1 inset
Additional details
Additional titles
- Original title (French)
- Les approximations deterministes de l'equation du transport des neutrons
Publishing Information
- Journal Title
- Chocs
- Journal Issue
- no.3
- Journal Page Range
- p. 37-44.
- ISSN
- 1157-741X
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 24009120
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; DIFFUSION; FINITE DIFFERENCE METHOD; FINITE ELEMENT METHOD; MESH GENERATION; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; NUMERICAL ANALYSIS; T CODES; Z CODES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ITERATIVE METHODS; MATHEMATICS; NUMERICAL SOLUTION; SIMULATION; TRANSPORT THEORY