### Abstract

Original language | English |
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Title of host publication | Proceedings of the international conference on physics of reactors |

Subtitle of host publication | PHYSOR2014 |

Number of pages | 12 |

Volume | JAEA-Conf 2014-003 |

DOIs | |

Publication status | Published - 2015 |

MoE publication type | A4 Article in a conference publication |

Event | International Conference on the Physics of Reactors, PHYSOR 2014: The Role of Reactor Physics toward Sustainable Future - Kyoto, Japan Duration: 28 Sep 2014 → 3 Oct 2014 |

### Conference

Conference | International Conference on the Physics of Reactors, PHYSOR 2014 |
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Abbreviated title | PHYSOR2014 |

Country | Japan |

City | Kyoto |

Period | 28/09/14 → 3/10/14 |

### Fingerprint

### Cite this

*Proceedings of the international conference on physics of reactors: PHYSOR2014*(Vol. JAEA-Conf 2014-003). [1106024] https://doi.org/10.11484/jaea-conf-2014-003

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*Proceedings of the international conference on physics of reactors: PHYSOR2014.*vol. JAEA-Conf 2014-003, 1106024, International Conference on the Physics of Reactors, PHYSOR 2014, Kyoto, Japan, 28/09/14. https://doi.org/10.11484/jaea-conf-2014-003

**Adjoint-based sensitivity and uncertainty analysis of lattice physics calculations with CASMO-4.** / Pusa, Maria.

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

TY - GEN

T1 - Adjoint-based sensitivity and uncertainty analysis of lattice physics calculations with CASMO-4

AU - Pusa, Maria

N1 - Papers are in the zip file

PY - 2015

Y1 - 2015

N2 - The topic of this paper is the development of sensitivity and uncertainty analysis capability to the reactor physics code CASMO-4 in the UAM (Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of LWRs) benchmark. The developed calculation system enables the uncertainty analysis of homogenized multi-group cross-sections, diffusion coefficients and pin powers with respect to nuclear data. The uncertainty analysis methodology is deterministic, meaning that the sensitivity profiles of the responses are computed first, after which uncertainty is propagated by combining the sensitivity profiles with the covariance matrices of the uncertain nuclear data. The sensitivity analysis is based on perturbation theory which enables computing the sensitivity profiles efficiently by solving one generalized adjoint system for each response. The mathematical background of this work is reviewed and the main conclusions related to the implementation are summarized. Special emphasis is placed on the sensitivity analysis of two-group homogenized diffusion coefficients which require some modifications to the standard equations of generalized perturbation theory. Numerical results are presented and analyzed for a PWR fuel assembly with control rods out and inserted. The computational efficiency of the calculations is discussed.

AB - The topic of this paper is the development of sensitivity and uncertainty analysis capability to the reactor physics code CASMO-4 in the UAM (Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of LWRs) benchmark. The developed calculation system enables the uncertainty analysis of homogenized multi-group cross-sections, diffusion coefficients and pin powers with respect to nuclear data. The uncertainty analysis methodology is deterministic, meaning that the sensitivity profiles of the responses are computed first, after which uncertainty is propagated by combining the sensitivity profiles with the covariance matrices of the uncertain nuclear data. The sensitivity analysis is based on perturbation theory which enables computing the sensitivity profiles efficiently by solving one generalized adjoint system for each response. The mathematical background of this work is reviewed and the main conclusions related to the implementation are summarized. Special emphasis is placed on the sensitivity analysis of two-group homogenized diffusion coefficients which require some modifications to the standard equations of generalized perturbation theory. Numerical results are presented and analyzed for a PWR fuel assembly with control rods out and inserted. The computational efficiency of the calculations is discussed.

U2 - 10.11484/jaea-conf-2014-003

DO - 10.11484/jaea-conf-2014-003

M3 - Conference article in proceedings

VL - JAEA-Conf 2014-003

BT - Proceedings of the international conference on physics of reactors

ER -