Abstract
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
Original language | English |
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Title of host publication | Proceedings |
Subtitle of host publication | International Conference on the Physics of Reactors 2012: Advances in Reactor Physics, PHYSOR 2012 |
Publisher | American Nuclear Society (ANS) |
Pages | 842-853 |
Volume | 1 |
ISBN (Print) | 978-1-6227-6389-4 |
Publication status | Published - 2012 |
MoE publication type | A4 Article in a conference publication |
Event | International Conference on the Physics of Reactors, PHYSOR 2012: Advances in Reactor Physics - Knoxville, United States Duration: 15 Apr 2012 → 20 Apr 2012 |
Conference
Conference | International Conference on the Physics of Reactors, PHYSOR 2012 |
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Country/Territory | United States |
City | Knoxville |
Period | 15/04/12 → 20/04/12 |
Keywords
- 3D core analysis
- criticality spectrum
- few-group cross-section generation
- lattice physics
- Monte Carlo
- reflector cross sections
- serpent