Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code

Jaakko Leppänen (Corresponding Author), M. Aufiero, E. Fridman, R. Rachamin, S. Van Der Marck

Research output: Contribution to journalArticleScientificpeer-review

48 Citations (Scopus)

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 languageEnglish
Pages (from-to)272-279
JournalAnnals of Nuclear Energy
Volume65
DOIs
Publication statusPublished - 2014
MoE publication typeA1 Journal article-refereed

Fingerprint

Kinetic parameters
Research reactors
Reactor cores
Neutrons

Keywords

  • Adjoint-weighted time constants
  • Effective delayed neutron fraction
  • Effective generation time
  • Monte Carlo
  • Serpent

Cite this

Leppänen, Jaakko ; Aufiero, M. ; Fridman, E. ; Rachamin, R. ; Van Der Marck, S. / Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code. In: Annals of Nuclear Energy. 2014 ; Vol. 65. pp. 272-279.
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Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code. / Leppänen, Jaakko (Corresponding Author); Aufiero, M.; Fridman, E.; Rachamin, R.; Van Der Marck, S.

In: Annals of Nuclear Energy, Vol. 65, 2014, p. 272-279.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code

AU - Leppänen, Jaakko

AU - Aufiero, M.

AU - Fridman, E.

AU - Rachamin, R.

AU - Van Der Marck, S.

PY - 2014

Y1 - 2014

N2 - 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.

AB - 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.

KW - Adjoint-weighted time constants

KW - Effective delayed neutron fraction

KW - Effective generation time

KW - Monte Carlo

KW - Serpent

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DO - 10.1016/j.anucene.2013.10.032

M3 - Article

VL - 65

SP - 272

EP - 279

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

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