Solving eigenvalue response matrix equations with nonlinear techniques
Creators
- 1. Department of Mechanical and Nuclear Engineering, Kansas State University, 3002 Rathbone Hall, Manhattan, KS 66506 (United States)
- 2. Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, 77 Massachusetts Avenue, 24-107, Cambridge, MA 02139 (United States)
Description
Highlights: • High performance solvers were applied within ERMM for the first time. • Accelerated fixed-point methods were developed that reduce computational times by 2–3. • A nonlinear, Newton-based ERMM led to similar improvement and more robustness. • A 3-D, SN-based ERMM shows how ERMM can apply fine-mesh methods to full-core analysis. - Abstract: This paper presents new algorithms for use in the eigenvalue response matrix method (ERMM) for reactor eigenvalue problems. ERMM spatially decomposes a domain into independent nodes linked via boundary conditions approximated as truncated orthogonal expansions, the coefficients of which are response functions. In its simplest form, ERMM consists of a two-level eigenproblem: an outer Picard iteration updates the k-eigenvalue via balance, while the inner λ-eigenproblem imposes neutron balance between nodes. Efficient methods are developed for solving the inner λ-eigenvalue problem within the outer Picard iteration. Based on results from several diffusion and transport benchmark models, it was found that the Krylov–Schur method applied to the λ-eigenvalue problem reduces Picard solver times (excluding response generation) by a factor of 2–5. Furthermore, alternative methods, including Picard acceleration schemes, Steffensen's method, and Newton's method, are developed in this paper. These approaches often yield faster k-convergence and a need for fewer k-dependent response function evaluations, which is important because response generation is often the primary cost for problems using responses computed online (i.e., not from a precomputed database). Accelerated Picard iteration was found to reduce total computational times by 2–3 compared to the unaccelerated case for problems dominated by response generation. In addition, Newton's method was found to provide nearly the same performance with improved robustness
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2014.02.002Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2014.02.002;
- PII
- S0306-4549(14)00072-3;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 69
- Journal Page Range
- p. 97-107
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46021979
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- ALGORITHMS; BENCHMARKS; BOUNDARY CONDITIONS; CONVERGENCE; COST; EIGENVALUES; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; NEUTRONS; NONLINEAR PROBLEMS; REACTOR CORES; RESPONSE FUNCTIONS; RESPONSE MATRIX METHOD
- Descriptors DEC
- BARYONS; CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTARY PARTICLES; EQUATIONS; FERMIONS; FUNCTIONS; HADRONS; MATHEMATICAL LOGIC; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR KINETICS EQUATIONS
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.