Current status of the PSG Monte Carlo neutron transport code

Conference · Sat Jul 01 00:00:00 EDT 2006

OSTI ID:22039612

Leppaenen, J ^[1]

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1. VTT Technical Research Centre of Finland, Laempoemiehenkuja 3, Espoo, FI-02044 VTT (Finland)

PSG is a new Monte Carlo neutron transport code, developed at the Technical Research Centre of Finland (VTT). The code is mainly intended for fuel assembly-level reactor physics calculations, such as group constant generation for deterministic reactor simulator codes. This paper presents the current status of the project and the essential capabilities of the code. Although the main application of PSG is in lattice calculations, the geometry is not restricted in two dimensions. This paper presents the validation of PSG against the experimental results of the three-dimensional MOX fuelled VENUS-2 reactor dosimetry benchmark. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22039612
• Resource Relation: Conference: PHYSOR-2006: American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, Vancouver, BC (Canada), 10-14 Sep 2006; Other Information: Country of input: France; 16 refs.
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
97 MATHEMATICAL METHODS AND COMPUTING
BENCHMARKS
DOSIMETRY
FUEL ASSEMBLIES
GROUP CONSTANTS
MIXED OXIDE FUELS
MONTE CARLO METHOD
NEUTRON TRANSPORT
P CODES
REACTOR LATTICE PARAMETERS
THREE-DIMENSIONAL CALCULATIONS
VALIDATION
VENUS REACTOR