Nuclear fuel safety threshold determined by logistic regression plus uncertainty
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World Academy of Science, Engineering and Technology
Resumo
Analysis of the uncertainty quantification related to
nuclear safety margins applied to the nuclear reactor is an important
concept to prevent future radioactive accidents. The nuclear fuel
performance code may involve the tolerance level determined by
traditional deterministic models producing acceptable results at burn
cycles under 62 GWd/MTU. The behavior of nuclear fuel can
simulate applying a series of material properties under irradiation and
physics models to calculate the safety limits. In this study, theoretical
predictions of nuclear fuel failure under transient conditions
investigate extended radiation cycles at 75 GWd/MTU, considering
the behavior of fuel rods in light-water reactors under reactivity
accident conditions. The fuel pellet can melt due to the quick increase
of reactivity during a transient. Large power excursions in the reactor
are the subject of interest bringing to a treatment that is known as the
Fuchs-Hansen model. The point kinetic neutron equations show
similar characteristics of non-linear differential equations. In this
investigation, the multivariate logistic regression is employed to a
probabilistic forecast of fuel failure. A comparison of computational
simulation and experimental results was acceptable. The experiments
carried out use the pre-irradiated fuels rods subjected to a rapid
energy pulse which exhibits the same behavior during a nuclear
accident. The propagation of uncertainty utilizes the Wilk's
formulation. The variables chosen as essential to failure prediction
were the fuel burnup, the applied peak power, the pulse width, the
oxidation layer thickness, and the cladding type.
Como referenciar
GOMES, D.S.; SILVA, A.T. Nuclear fuel safety threshold determined by logistic regression plus uncertainty. World Academy of Science, Engineering and Technology, v. 11, n. 3, p. 622-628, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28904. Acesso em: 30 Dec 2025.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.