Revised methods for few-group cross sections generation in the Serpent Monte Carlo code

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22105631

Fridman, E. ^[1]; Leppaenen, J. ^[2]

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1. Reactor Safety Div., Helmholz-Zentrum Dresden-Rossendorf, POB 51 01 19, Dresden, 01314 (Germany)
2. VTT Technical Research Centre of Finland, POB 1000, FI-02044 VTT (Finland)

This paper presents new calculation methods, recently implemented in the Serpent Monte Carlo code, and related to the production of homogenized few-group constants for deterministic 3D core analysis. The new methods fall under three topics: 1) Improved treatment of neutron-multiplying scattering reactions, 2) Group constant generation in reflectors and other non-fissile regions and 3) Homogenization in leakage-corrected criticality spectrum. The methodology is demonstrated by a numerical example, comparing a deterministic nodal diffusion calculation using Serpent-generated cross sections to a reference full-core Monte Carlo simulation. It is concluded that the new methodology improves the results of the deterministic calculation, and paves the way for Monte Carlo based group constant generation. (authors)

• Research Organization: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
• OSTI ID: 22105631
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
COMPUTER GRAPHICS
COMPUTERIZED SIMULATION
CRITICALITY
DIFFUSION
FISSION
GROUP CONSTANTS
MONTE CARLO METHOD
NEUTRONS
SCATTERING
SPECTRA
THREE-DIMENSIONAL CALCULATIONS