### 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 language | English |
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Title of host publication | International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009) |

Publisher | American Nuclear Society ANS |

Pages | 1662-1673 |

Edition | cd-rom |

ISBN (Print) | 978-0-89448-069-0 |

Publication status | Published - 2009 |

MoE publication type | A4 Article in a conference publication |

Event | International Conference on Mathematics, Computational Methods & Reactor Physics, M&C 2009 - Saratoga Springs, United States Duration: 3 May 2009 → 7 May 2009 |

### Conference

Conference | International Conference on Mathematics, Computational Methods & Reactor Physics, M&C 2009 |
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Country | United States |

City | Saratoga Springs |

Period | 3/05/09 → 7/05/09 |

### Keywords

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

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## 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. https://www.vtt.fi/inf/julkaisut/muut/2009/MC2009.pdf