Deterministic methods to solve the differential transport equation in neutronic
Description
We present a synthesis of the methods used to solve the integro-differential form of the transport equation. This form is used above all to achieve whole core calculations in 2 and 3D. First, we discretize the equation in energy and it leads us to an one group energy equation. For each of these groups, the scope of the calculation is so big that we have to calculate our solution on homogenized cells. On this homogenized medium, we describe different angular and spatial discretizations with acceleration methods. Finally we select some promising schemes to test: - SN Linear Nodal method with a Diffusion Synthetic Acceleration method; - Variational Nodal Method. These methods could be compared with more classical ones. To say, finite element or finite difference methods. (author). 65 refs., 3 annexes
Availability note (English)
MF available from INIS under the Report Number.Files
26037716.pdf
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Additional details
Additional titles
- Original title (French)
- Methodes deterministes de resolution de l'equation integro-differentielle du transport neutronique
Publishing Information
- Imprint Pagination
- 101 p.
- Report number
- EDF--94-NJ-00061
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 26037716
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALGORITHMS; DISCRETE ORDINATE METHOD; FINITE DIFFERENCE METHOD; FINITE ELEMENT METHOD; HOMOGENIZATION METHODS; NEUTRON TRANSPORT; NODAL EXPANSION METHOD
- Descriptors DEC
- CALCULATION METHODS; ITERATIVE METHODS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; RADIATION TRANSPORT