A method for uncertainty and sensitivity analysis in fuel performance codes
DOI:
https://doi.org/10.15392/bjrs.v9i3.1700Palabras clave:
sensitivity analysis, uncertainty analysis, confidence intervalsResumen
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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Referencias
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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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Derechos de autor 2021 Brazilian Journal of Radiation Sciences (BJRS)
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