### Abstract

Original language | English |
---|---|

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 |
---|---|

Country | United States |

City | Saratoga Springs |

Period | 3/05/09 → 7/05/09 |

### Fingerprint

### Keywords

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

### Cite this

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

}

*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.

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - Burnup calculation capability in the PSG2/serpent Monte Carlo reactor physics code

AU - Leppänen, Jaakko

AU - Pusa, Maria

PY - 2009

Y1 - 2009

N2 - 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.

AB - 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.

KW - serpent

KW - PSG

KW - Monte Carlo burnup calculation

KW - TTA

KW - CRAM

M3 - Conference article in proceedings

SN - 978-0-89448-069-0

SP - 1662

EP - 1673

BT - International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2009)

PB - American Nuclear Society ANS

ER -