Elastic and viscoplastic pellets fragmentation modeling using an axisymmetrical 1D finite element code

Guicheret-Retel, Violaine; Trivaudey, Frédérique; Boubakar, M. Lamine; Thevenin, Ph.

doi:10.1016/j.nucengdes.2004.07.003

Cited by 7 publications

(1 citation statement)

References 14 publications

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“…Modelling of the fission gas behaviour could possibly benefit from advanced constitutive models for the fuel pellet material, by which the local stress state may be calculated with consideration of relevant deformation mechanisms, including cracking of the fuel material. Such constitutive models usually employ a smeared (continuum) representation of cracks in the material [141][142][143][144], since explicit (discrete) modelling of fuel pellet cracks is computationally demanding and still at the research front [145,146]. However, these state-of-the-art constitutive models tend to give very different results for the calculated stress distribution in the fuel pellet, even under stationary operating conditions, and it is therefore questionable if they would provide reliable boundary conditions for fission gas models.…”

Section: Summary Of Main Findingsmentioning

confidence: 99%

Modelling of fine fragmentation and fission gas release of UO₂ fuel in accident conditions

Jernkvist

2019

EPJ Nuclear Sci. Technol.

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In reactor accidents that involve rapid overheating of oxide fuel, overpressurization of gas-filled bubbles and pores may lead to rupture of these cavities, fine fragmentation of the fuel material, and burst-type release of the cavity gas. Analytical rupture criteria for various types of cavities exist, but application of these criteria requires that microstructural characteristics of the fuel, such as cavity size, shape and number density, are known together with the gas content of the cavities. In this paper, we integrate rupture criteria for two kinds of cavities with models that calculate the aforementioned parameters in UO2 LWR fuel for a given operating history. The models are intended for implementation in engineering type computer programs for thermal-mechanical analyses of LWR fuel rods. Here, they have been implemented in the FRAPCON and FRAPTRAN programs and validated against experiments that simulate LOCA and RIA conditions. The capabilities and shortcomings of the proposed models are discussed in light of selected results from this validation. Calculated results suggest that the extent of fuel fragmentation and transient fission gas release depends strongly on the pre-accident fuel microstructure and fission gas distribution, but also on rapid changes in the external pressure exerted on the fuel pellets during the accident.

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Section: Summary Of Main Findingsmentioning

confidence: 99%

Modelling of fine fragmentation and fission gas release of UO₂ fuel in accident conditions

Jernkvist

2019

EPJ Nuclear Sci. Technol.

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Finite element simulation of Pellet-Cladding Interaction (PCI) in nuclear fuel rods

Marchal

Campos

Garnier

2009

Computational Materials Science

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Influence of the U3O7 domain structure on cracking during the oxidation of UO2

Desgranges

Palancher

Gamaléri

et al. 2010

Journal of Nuclear Materials

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a b s t r a c tCracking is observed when a UO 2 single crystal is oxidised in air. Previous studies led to the hypothesis that cracking occurs once a critical depth of U 3 O 7 oxidised layer is reached. We present some l-Laue Xray diffraction results, which evidence that the U 3 O 7 layer, grown by topotaxy on UO 2 , is made of domains with different crystalline orientations. This observation was used to perform a modelling of oxidation coupling chemical and mechanical parameters, which showed that the domain patterning induces stress localisation. This result is discussed in comparison with stress localisation observed in thin layer deposited on a substrate and used to propose an interpretation of UO 2 oxidation and cracking.

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Elastic and viscoplastic pellets fragmentation modeling using an axisymmetrical 1D finite element code

Cited by 7 publications

References 14 publications

Modelling of fine fragmentation and fission gas release of UO₂ fuel in accident conditions

Modelling of fine fragmentation and fission gas release of UO₂ fuel in accident conditions

Finite element simulation of Pellet-Cladding Interaction (PCI) in nuclear fuel rods

Influence of the U3O7 domain structure on cracking during the oxidation of UO2

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Elastic and viscoplastic pellets fragmentation modeling using an axisymmetrical 1D finite element code

Cited by 7 publications

References 14 publications

Modelling of fine fragmentation and fission gas release of UO2 fuel in accident conditions

Modelling of fine fragmentation and fission gas release of UO2 fuel in accident conditions

Finite element simulation of Pellet-Cladding Interaction (PCI) in nuclear fuel rods

Influence of the U3O7 domain structure on cracking during the oxidation of UO2

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Modelling of fine fragmentation and fission gas release of UO₂ fuel in accident conditions

Modelling of fine fragmentation and fission gas release of UO₂ fuel in accident conditions