Three-dimensional static and dynamic reactor calculations by the nodal expansion method
Description
This report reviews various method for the calculation of the neutron-flux- and power distribution in an nuclear reactor. The nodal expansion method (NEM) is especially described in much detail. The nodal expansion method solves the diffusion equation. In this method the reactor core is divided into nodes, typically 10 to 20 cm in each direction, and the average flux in each node is calculated. To obtain the coupling between the nodes the local flux inside each node is expressed by use of a polynomial expansion. The expansion is one-dimensional, so inside each node such three expansions occur. To calculate the expansion coefficients it is necessary that the polynomial expansion is a solution to the one-dimensional diffusion equation. When the one-dimensional diffusion equation is established a term with the transversal leakage occur, and this term is expanded after the same polynomials. The resulting equation system with the expansion coefficients as the unknowns is solved with weigthed residual technique. The nodal expansion method is built into a computer program (also called NEM), which is divided into two parts, one part for steady-state calculations and one part for dynamic calculations. It is possible to take advantage of symmetry properties of the reactor core. The program is very flexible with regard to the number of energy groups, the node size, the flux expansion order and the transverse leakage expansion order. The boundary of the core is described by albedos. The program and input to it are described. The program is tested on a number of examples extending from small theoretical one up to realistic reactor cores. Many calculations are done on the wellknown IAEA benchmark case. The calculations have tested the accuracy and the computing time for various node sizes and polynomial expansions. In the dynamic examples various strategies for variation of the time step-length have been tested. (author)
Availability note (English)
MF available from INIS under the Report Number; Also available from Risoe Library, DK-4000 Roskilde, Denmark.Files
17047429.pdf
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Additional details
Publishing Information
- ISBN
- 87-550-1169-1
- Imprint Pagination
- 206 p.
- Report number
- RISO-R--496
INIS
- Country of Publication
- Denmark
- Country of Input or Organization
- Denmark
- INIS RN
- 17047429
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; N CODES; NEUTRON FLUX; POLYNOMIALS; POWER DISTRIBUTION; REACTOR CORES; REACTOR KINETICS; SERIES EXPANSION; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; FUNCTIONS; KINETICS; RADIATION FLUX; REACTOR COMPONENTS; SIMULATION; SPATIAL DISTRIBUTION
Optional Information
- Notes
- 41 refs.