Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor
- 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, Laboratory for Reactor Physics and Systems Behaviour, PSI Villigen, 5232 (Switzerland)
Description
Highlights: • Development and verification of an SP3 solver based on OpenFOAM. • Integration into the GeN-Foam multi-physics platform. • Application of the new GeN-Foam SP3 solver to the CROCUS reactor. - Abstract: The Laboratory for Reactor Physics and Systems Behaviour at the PSI and at the EPFL has been developing since 2013 a multi-physics platform for coupled reactor analysis named GeN-Foam. The developed tool includes a solver for the eigenvalue and transient solution of multi-group neutron diffusion equations. Although frequently used in reactor analysis, the diffusion theory shows some limitations for core configurations involving strong anisotropies, which is the case for the CROCUS research reactor at the EPFL. The use of an SP3 approximation to neutron transport can often lead to visible improvements in a code predictive capabilities, especially for one-directional anisotropies, with acceptable added computational cost vs diffusion. Following some modelling issues for the CROCUS reactor, and in order to improve the GeN-Foam modelling capabilities, the GeN-Foam diffusion solver has been extended to allow for SP3 analyses. The present paper describes such extension and a preliminary verification using a mini-core PWR benchmark. The newly developed solver is then applied to the analysis of the CROCUS experimental reactor and results are compared to Monte Carlo calculations, as well as to the results of the diffusion solver.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2016.11.042Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2016.11.042;
- PII
- S0306-4549(16)30512-6;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 101
- Journal Page Range
- p. 419-428
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48085553
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BENCHMARKS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CROCUS REACTOR; EIGENVALUES; MONTE CARLO METHOD; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; PWR TYPE REACTORS; REACTOR CORES; REACTOR PHYSICS; SPHERICAL HARMONICS
- Descriptors DEC
- CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; EVALUATION; EXPERIMENTAL REACTORS; FUNCTIONS; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICS; POOL TYPE REACTORS; POWER REACTORS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZERO POWER REACTORS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.