dc.creatorDANTAS, A.C.
dc.creatorSILVA, A.T.
dc.date2021
dc.date2022-03-14T12:08:05Z
dc.date2022-03-14T12:08:05Z
dc.date.accessioned2023-09-28T14:21:20Z
dc.date.available2023-09-28T14:21:20Z
dc.identifier2319-0612
dc.identifierhttp://repositorio.ipen.br/handle/123456789/32785
dc.identifier3
dc.identifier9
dc.identifier10.15392/bjrs.v9i3.1700
dc.identifierSem Percentil
dc.identifierSem Percentil CiteScore
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/9003004
dc.descriptionThe 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.
dc.format1-18
dc.relationBrazilian Journal of Radiation Sciences
dc.rightsopenAccess
dc.subjectcladding
dc.subjectdata covariances
dc.subjectfuel rods
dc.subjectmonte carlo method
dc.subjectnuclear fuels
dc.subjectperformance
dc.subjectpwr type reactors
dc.subjectsensitivity analysis
dc.subjectstainless steel-348
dc.subjectt codes
dc.titleA method for uncertainty and sensitivity analysis in fuel performance codes
dc.typeArtigo de peri??dico
dc.coverageN


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