Mesh Adaptive Search Optimization in SERPENT2 Stereolithography Geometry
- Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)
- VTT Technical Research Centre, P.O. Box 1000, FI-02044 VTT (Finland)
SERPENT2 Monte Carlo program has the capability to model reactor cores by stereolithography (STL) geometry. In this geometry, volumes are defined by the union of triangulated surfaces. Using the STL geometry offers unique benefits, including: 1) the model can be printed on 3D printers; 2) the possibility to use directly geometrical models from Computer-Aided Design (CAD); 3) the capability to perform multi-physics simulations coupling neutronics, thermal-hydraulics, and material science computations. In this work the STL geometry has been created by the CUBIT software, which is designed for finite elements mesh generation. The materials in the STL geometry have been assigned by a simple C program using the colors of the volumes in the CUBIT model. The goal of this work is to minimize the SERPENT2 computing time using mesh adaptive search algorithms. The basic idea is to split the geometry of the core into two zones: one zone containing the fuel elements (including the moderator and the coolant) and the other containing the reflector (and the target zone of the core, if it is driven by an external neutron source). By performing this splitting, two separate meshes are used, which results in a considerable computing time saving. (authors)
- OSTI ID:
- 23042792
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 115; Conference: 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, NV (United States), 6-10 Nov 2016; Other Information: Country of input: France; 6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US); ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
3D PRINTING
ALGORITHMS
COMPUTER-AIDED DESIGN
COMPUTERIZED SIMULATION
COOLANTS
COUPLING
FUEL ELEMENTS
GEOMETRY
MATERIALS
MESH GENERATION
MODERATORS
MONTE CARLO METHOD
NEUTRON SOURCES
OPTIMIZATION
REACTOR CORES
THERMAL HYDRAULICS