Optimization of multidimensional cross-section tables for few-group core calculations
Description
Highlights: • Optimization of tabulated cross-sections libraries for multi-group diffusion codes. • Sensitivity coefficients using perturbation theory are determined. • A non-uniform grid satisfying a given target accuracy in k-effective is built. • Satisfactory results are obtained using libraries with different accuracy level. - Abstract: Multigroup diffusion codes for three dimensional LWR core analysis use as input data pre-generated homogenized few group cross sections and discontinuity factors for certain combinations of state variables, such as temperatures or densities. The simplest way of compiling those data are tabulated libraries, where a grid covering the domain of state variables is defined and the homogenized cross sections are computed at the grid points. Then, during the core calculation, an interpolation algorithm is used to compute the cross sections from the table values. Since interpolation errors depend on the distance between the grid points, a determined refinement of the mesh is required to reach a target accuracy, which could lead to large data storage volume and a large number of lattice transport calculations. In this paper, a simple and effective procedure to optimize the distribution of grid points for tabulated libraries is presented. Optimality is considered in the sense of building a non-uniform point distribution with the minimum number of grid points for each state variable satisfying a given target accuracy in k-effective. The procedure consists of determining the sensitivity coefficients of k-effective to cross sections using perturbation theory; and estimating the interpolation errors committed with different mesh steps for each state variable. These results allow evaluating the influence of interpolation errors of each cross section on k-effective for any combination of state variables, and estimating the optimal distance between grid points
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2014.02.013Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2014.02.013;
- PII
- S0306-4549(14)00083-8;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 69
- Journal Page Range
- p. 226-237
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46021992
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- ACCURACY; CROSS SECTIONS; DATA BASE MANAGEMENT; HEAVY WATER MODERATED REACTORS; INTERPOLATION; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NUCLEAR DATA COLLECTIONS; OPTIMIZATION; PERTURBATION THEORY; REACTOR CORES; SENSITIVITY; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; MANAGEMENT; MATHEMATICAL SOLUTIONS; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR COMPONENTS; REACTORS; TRANSPORT THEORY
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.