This paper describes the methods used in the Serpent 2 Monte Carlo code for producing homogenized group constants for nodal diffusion and other deterministic reactor simulator calculations. The methodology covers few-group reaction cross sections, scattering matrices, diffusion coefficients and poison cross sections condensed in infinite and B1leakage-corrected critical spectra, as well as the calculation of discontinuity factors, pin-power form factors, delayed neutron parameters and total and partial albedos. Also included is a description of an automated burnup sequence, which was recently implemented for the handling of restart calculations with branch variations. This capability enables covering the full range of local operating conditions required for the parameterization of group constants within a single run. The purpose of this paper is to bring the methodological description provided in earlier publications up to date, and provide insight into the developed methods and capabilities, including their limitations and known flaws.
- automated burnup sequence
- group constants
- Monte Carlo
- spatial homogenization
Leppänen, J., Pusa, M., & Fridman, E. (2016). Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code. Annals of Nuclear Energy, 96, 126-136. https://doi.org/10.1016/j.anucene.2016.06.007