A method for uncertainty and sensitivity analysis in fuel performance codes

Authors

  • Ana Carolina Bortoletto Dantas Instituto de Pesquisas energéticas e Nucleares
  • Antonio Teixeira e Silva Instituto de Pesquisas Energéticas e Nucleares

DOI:

https://doi.org/10.15392/bjrs.v9i3.1700

Keywords:

sensitivity analysis, uncertainty analysis, confidence intervals

Abstract

The present study proposes a method for the execution of uncertainty and sensitivity analysis on TRANSURANUS code, adapted for the use of stainless steel AISI-348 as the cladding material for a PWR reactor fuel rod, thus allowing to determine which input data are more relevant to the TRANSURANUS models, as well as a confidence interval for the results. The analysis was made through Monte Carlo sampling, where input values related to the geometry and composition of the fuel rod were taken from a normal distribution truncated around fabrication tolerance values. The generated samples were used as TRANSURANUS input data, and after numerous executions of the code, the results pertaining to the fuel center line temperature, fuel rod inner pressure and cladding strains were used to obtain a confidence interval and to make a variance based sensitivity analysis, showing that the models used in TRANSURANUS are additive in nature, and input interactions are not relevant to the code.

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Author Biography

  • Ana Carolina Bortoletto Dantas, Instituto de Pesquisas energéticas e Nucleares
    Mestranda do programa de Tecnologia de Reatores.

References

LOUCKS, P. et al. Water Resources Systems Planning and Management: An Introduction to Methods, Models And Applications. Published by UNESCO, Paris, 2005.

SALTELLI, A. et al. Global Sensitivity Analysis: The Primer. John Wiley & Sons, 2008.

GIOVEDI, C. et al. Fuel Performance Of Iron-Based Alloy Cladding Using Modified Transuranus Code , XXI ENFIR, Santos, 2019

BOULARÁ, STUZIK, GAUDIER. Uncertainty and sensitivity analysis of the nuclear fuel thermal behavior. Commissariat à l’Énergie Atomique (CEA), France.

GAMBLE, K. A.; SWILER, L. P.; Uncertainty quantification and Sensitivity analysis applications to fuel performance modeling. Idaho National Laboratory.

IKONEN, T.; TULKKI, V.; Importance of input interactions in the uncertainty and sensitivity analysis of nuclear fuel behavior. VTT Technichal Reasearch Centre of Finland

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Published

2021-09-20

Issue

Section

Articles

How to Cite

A method for uncertainty and sensitivity analysis in fuel performance codes. Brazilian Journal of Radiation Sciences, Rio de Janeiro, Brazil, v. 9, n. 3, 2021. DOI: 10.15392/bjrs.v9i3.1700. Disponível em: https://bjrs.org.br/revista/index.php/REVISTA/article/view/1700. Acesso em: 22 dec. 2024.

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