Calculation of angle-dependent extrapolation lengths at the control channel edge of absorber assemblies
Creators
- 1. VE Kombinat Kernkraftwerke, Greifswald (German Democratic Republic)
- 2. Zentralinstitut fuer Kernforschung, Rossendorf (German Democratic Republic)
- 3. Energiekombinat, Berlin (German Democratic Republic)
Description
Based on a model formulated within the framework of two-group diffusion equation for the absorber section of WWER-440 type control elements and the Fourier series expansion of the corresponding solution of the modified one-group diffusion approximation, the extrapolation length on the control channel edge is investigated as a function of angle for an absorber eccentrically positioned in a homogeneous cylindrical reactor core. The angle-depending extrapolation length is shown to be calculable in a sufficient approximation from absorber-specific parameters and a flux distribution resulting from the assumption of a constant extrapolation length. The method of calculating angle-dependent extrapolation lengths is transferred onto the coarse-mesh difference schema method of the one-group diffusion equation and is also appropriate for a more exact consideration of heterogeneous core configurations. (author)
Additional details
Additional titles
- Original title (German)
- Berechnung winkelabhaengiger Extrapolationslaengen auf dem Steuerkanalrand von Absorberkassetten
Publishing Information
- Journal Title
- Kernenergie
- Journal Volume
- 32
- Journal Issue
- 4
- Series
- Kernenergie.
- Journal Page Range
- 135-140
- ISSN
- 0023-0642
- CODEN
- KERNA
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- German Democratic Republic
- INIS RN
- 20037671
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ANALYTICAL SOLUTION; CONTROL ELEMENTS; DISTRIBUTION; EXTRAPOLATION LENGTH; FINITE DIFFERENCE METHOD; MATHEMATICAL MODELS; NEUTRON ABSORBERS; NEUTRON FLUX; ONE-GROUP THEORY; WWER-3 REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; ITERATIVE METHODS; NUMERICAL SOLUTION; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS