Published 2017 | Version v1
Journal article

MCNP6 and SERPENT2 Performances with Unstructured Mesh Geometry

  • 1. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)
  • 2. VTT Technical Research Centre, P.O. Box 1000, FI-02044 VTT (Finland)

Description

Traditionally, Monte Carlo codes model a nuclear reactor by combinatorial geometry. In this model, volume primitives (e,g, spheres, cylinders, parallelepipeds...) are combined together by Boolean operations (e.g. union, intersection, and complement) and replicated by lattice definitions to build the core geometry. Recently, high performances computing platforms allowed using unstructured mesh geometry in Monte Carlo codes. When this option is chosen, any type of core geometry can be modeled since the restriction of using volume primitives is removed. In an unstructured mesh geometry, Boolean operations and lattice definitions are not used since each volume is defined by triangular surfaces (facets). This study focuses on two Monte Carlo codes: MCNP (version 6.1.1 beta) developed at Los Alamos National Laboratory since 1957 and written in FORTRAN90, C, and C++ (267,000 total source code lines), and SERPENT (version 2.1.27) developed at VTT Technical Research Centre since 2004 and written in C (195,000 total source code lines). These two codes follow different approaches for the unstructured mesh geometry modeling: MCNP uses ABAQUS format, whereas SERPENT uses the STL format. In the STL (STereoLithographic) geometry model only the surfaces of the volume are meshed; the interior part of the volumes is not meshed. In the STL geometry model, the whole geometry is defined by the sequence of SOLID and ENDSOLID sections. Each volume of the geometry must have a SOLID and ENDSOLID section. The STL file contains no information specifying the materials of the volumes. MCNP and SERPENT can model any kind of complicated geometry using unstructured meshes. MCNP and SERPENT use the ABAQUS and STL file formats, respectively. The STL file format does not have tetrahedrons and has only triangular facets on the volumes boundary. This allows SERPENT simulations to run 10 times faster than MCNP. However, if Monte Carlo results have to be coupled to thermal-hydraulics codes, the interior of the geometry volumes must be meshed, which may reduce SERPENT performances

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
116
Journal Page Range
p. 1111-1113
ISSN
0003-018X

Conference

Title
2017 Annual Meeting of the American Nuclear Society
Dates
11-15 Jun 2017
Place
San Francisco, CA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
52090718
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; CYLINDERS; GEOMETRY; MONTE CARLO METHOD; PERFORMANCE; REACTORS; SOLIDS; SURFACES; THERMAL HYDRAULICS
Descriptors DEC
CALCULATION METHODS; FLUID MECHANICS; HYDRAULICS; MATHEMATICS; MECHANICS; SIMULATION

Optional Information

Notes
7 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)