Abstract
This paper presents the methodology developed for the
Serpent 2 Monte Carlo code for the calculation of
adjoint-weighted reactor point kinetics parameters:
effective generation time and delayed neutron fractions.
The calculation routines were implemented at the
Politecnico di Milano, and they are based on the iterated
fission probability (IFP) method. The developed
methodology is mainly intended for the modeling of small
research reactor cores, and the results are validated by
comparison to experimental data and MCNP5 calculations in
31 critical configurations.
Original language | English |
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Pages (from-to) | 272-279 |
Journal | Annals of Nuclear Energy |
Volume | 65 |
DOIs | |
Publication status | Published - 2014 |
MoE publication type | A1 Journal article-refereed |
Keywords
- Adjoint-weighted time constants
- Effective delayed neutron fraction
- Effective generation time
- Monte Carlo
- Serpent