The spectral element method for static neutron transport in AN approximation. Part I
Creators
- 1. Energy Department, Politecnico di Torino, I-10129 Torino (Italy)
- 2. Service de Métrologie Nucléaire, Université Libre de Bruxelles, B-1050 Brussels (Belgium)
Description
Highlights: ► Spectral elements methods (SEMs) are extended for the neutronics of nuclear reactor cores. ► The second-order, AN formulation of neutron trasport is adopted. ► Results for classical benchmark cases in 2D are presented and compared to finite elements. ► The advantages of SEM in terms of precision and convergence rate are illustrated. ► SEM consitutes a promising approach for the solution of neutron transport problems. - Abstract: Spectral elements methods provide very accurate solutions of elliptic problems. In this paper we apply the method to the AN (i.e. SP2N−1) approximation of neutron transport. Numerical results for classical benchmark cases highlight its performance in comparison with finite element computations, in terms of accuracy per degree of freedom and convergence rate. All calculations presented in this paper refer to two-dimensional problems. The method can easily be extended to three-dimensional cases. The results illustrate promising features of the method for more complex transport problems
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2012.10.013Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2012.10.013;
- PII
- S0306-4549(12)00410-0;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 53
- Journal Issue
- Complete
- Journal Page Range
- p. 372-380
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45111082
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCURACY; APPROXIMATIONS; BENCHMARKS; COMPARATIVE EVALUATIONS; CONVERGENCE; DEGREES OF FREEDOM; FINITE ELEMENT METHOD; NEUTRON TRANSPORT; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CALCULATION METHODS; EVALUATION; MATHEMATICAL SOLUTIONS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; RADIATION TRANSPORT; REACTOR COMPONENTS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.