A reduced order accelerator for time-dependent segregated neutronic solvers
- 1. École Polytechnique Fédérale de Lausanne, Laboratory for Reactor Physics and Systems Behaviour, 1015 Lausanne (Switzerland)
- 2. Paul Scherrer Institut, Nuclear Energy and Safety Department, PSI Villigen, 5232 (Switzerland)
Description
Highlights: • Development of an acceleration technique for segregated neutronic problems and application to multi-group diffusion. • Use of reduced order modelling for faster iterations. • Comparable performances with respect to some commonly used techniques. • Flexible implementation and room for extension and improvements. - Abstract: The deterministic solution of the neutron transport problem entails the coupled solution of several partial differential equations, one for each energy group, direction and/or spherical harmonic. Several techniques have been devised for accelerating the solution of this set of equations, both for time dependent and eigenvalue calculations. This paper describes an acceleration technique based on reduced order models and applicable to the segregated solution of time dependent solutions. In this work the technique is applied to the simple case of multi-group diffusion and tested on two cases of practical interest. It shows performances that are comparable to some commonly employed acceleration techniques. Some potential advantages have been observed for transients with significant flux deformations. In addition, possibly interesting features of the proposed technique are: a relatively easy implementation in general PDE solvers and numerical libraries; its potential applicability to any kind of problem requiring the iterative solution of a system of equations; a flexible implementation with a wide margin for possible modifications.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2018.07.032Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2018.07.032;
- PII
- S0306454918303815;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 121
- Journal Page Range
- p. 177-185
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50079510
- Subject category
- S43: PARTICLE ACCELERATORS;
- Descriptors DEI
- ACCELERATION; ACCELERATORS; IMPLEMENTATION; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; SIMULATION; TIME DEPENDENCE
- Descriptors DEC
- CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION TRANSPORT
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.