Abstract
This paper discusses recent modifications to the Serpent
Monte Carlo code methodology and related to the
calculation of few-group diffusion coefficients and
reflector discontinuity factors The new methods were
assessed in the following manner. First, few-group
homogenized cross sections calculated by Serpent for a
reference PWR core were compared with those generated 1
commercial deterministic lattice transport code HELIOS-2.
Second, Serpent and HELIOS-2 fe group cross section sets
were later employed by nodal diffusion code DYN3D for the
modeling the reference PWR core. Finally, the nodal
diffusion results obtained using the both cross sectii
sets were compared with the full core Serpent Monte Carlo
solution. The test calculations shov that Serpent can
calculate the parameters required for nodal analyses
similar to conventional deterministic lattice codes.
Original language | English |
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Title of host publication | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 |
Publisher | American Nuclear Society (ANS) |
Pages | 693-703 |
ISBN (Print) | 978-0-89448-700-2 |
Publication status | Published - 2013 |
MoE publication type | A4 Article in a conference publication |
Event | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 - Sun Valley, ID, United States Duration: 5 May 2013 → 9 May 2013 |
Conference
Conference | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 |
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Abbreviated title | M&C 2013 |
Country/Territory | United States |
City | Sun Valley, ID |
Period | 5/05/13 → 9/05/13 |
Keywords
- few-group cross section generation
- HELIOS
- Monte Carlo
- PWR
- serpent