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 |
|---|---|
| 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 |
|---|---|
| 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