Burnup calculation capability in the PSG2/serpent Monte Carlo reactor physics code

Jaakko Leppänen, Maria Pusa

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

16 Citations (Scopus)

Abstract

Serpent is the new version of the PSG continuous-energyMonte Carlo reactor physics code, developed at VTT Technical Research Centre of Finland since 2004. The code is mainly intended for lattice physics calculations, such as group constant generation for coupled few-group nodal diffusion codes. The capabilities of Serpent have recently been extended to fuel cycle studies and the modeling of irradiated fuels by introducing built-in burnup calculation routines. This paper presents the methodology used for burnup calculation. The code has two fundamentally different options for solving the depletion equations: 1) the Transmutation Trajectory Analysis method (TTA), based on the analytical solution of linearized depletion chains and 2) the Chebyshev Rational Approximation Method (CRAM), an advanced matrix exponential solution developed at VTT. The results are compared to deterministic CASMO-4E calculations. The lack of computing power is still today a major factor limiting the practical use of the Monte Carlo method for burnup calculation. The Serpent code uses special techniques for reducing the overall calculation time enough for the method to become a viable alternative to deterministic assembly burnup codes.
Original languageEnglish
Title of host publicationInternational Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009)
PublisherAmerican Nuclear Society ANS
Pages1662-1673
Editioncd-rom
ISBN (Print)978-0-89448-069-0
Publication statusPublished - 2009
MoE publication typeA4 Article in a conference publication
EventInternational Conference on Mathematics, Computational Methods & Reactor Physics, M&C 2009 - Saratoga Springs, United States
Duration: 3 May 20097 May 2009

Conference

ConferenceInternational Conference on Mathematics, Computational Methods & Reactor Physics, M&C 2009
CountryUnited States
CitySaratoga Springs
Period3/05/097/05/09

Fingerprint

Physics
Monte Carlo methods
Trajectories

Keywords

  • serpent
  • PSG
  • Monte Carlo burnup calculation
  • TTA
  • CRAM

Cite this

Leppänen, J., & Pusa, M. (2009). Burnup calculation capability in the PSG2/serpent Monte Carlo reactor physics code. In International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009) (cd-rom ed., pp. 1662-1673). American Nuclear Society ANS.
Leppänen, Jaakko ; Pusa, Maria. / Burnup calculation capability in the PSG2/serpent Monte Carlo reactor physics code. International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009). cd-rom. ed. American Nuclear Society ANS, 2009. pp. 1662-1673
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Leppänen, J & Pusa, M 2009, Burnup calculation capability in the PSG2/serpent Monte Carlo reactor physics code. in International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009). cd-rom edn, American Nuclear Society ANS, pp. 1662-1673, International Conference on Mathematics, Computational Methods & Reactor Physics, M&C 2009, Saratoga Springs, United States, 3/05/09.

Burnup calculation capability in the PSG2/serpent Monte Carlo reactor physics code. / Leppänen, Jaakko; Pusa, Maria.

International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009). cd-rom. ed. American Nuclear Society ANS, 2009. p. 1662-1673.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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Leppänen J, Pusa M. Burnup calculation capability in the PSG2/serpent Monte Carlo reactor physics code. In International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009). cd-rom ed. American Nuclear Society ANS. 2009. p. 1662-1673