Plutonium redistribution in fast reactor mixed oxide fuel pins

Bober, M.; Schumacher, G.; Geithoff, D.

doi:10.1016/0022-3115(73)90101-3

Cited by 30 publications

(4 citation statements)

References 7 publications

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“…The fuel pellet temperature rises to over 2300 K during irradiation because of the high linear heating power. The large temperature gradient in the radial direction causes redistribution of Pu and U, and Pu content increases to about 40% at the pellet center [2,3]. The maximum temperature of the fuel pellet during irradiation is limited within the design criterion to prevent fuel melting.…”

Section: Introductionmentioning

confidence: 99%

Solidus and liquidus temperatures in the UO2–PuO2 system

Kato

Morimoto

Sugata³

et al. 2008

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

Solidus and liquidus temperatures in the UO2–PuO2 system

Kato

Morimoto

Sugata³

et al. 2008

Journal of Nuclear Materials

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“…The redistributions of actinide elements in the MOX fuel under a steep temperature gradient have been studied by a number of researchers, and considered to be caused by the following two transport processes [5][6][7][8][9][10][11][12]: pore migration by evaporation and condensation, and thermal diffusion.…”

Section: Discussionmentioning

confidence: 99%

Radial redistribution of actinides in irradiated FR-MOX fuels

Maeda

Sasaki

Kato

et al. 2009

Journal of Nuclear Materials

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“…Plutonium migration mechanisms have been extensively investigated, and a large amount of basic information on plutonium migration mechanisms has been obtained. Bober (Bober et al, 1973) and Schumacher and Matzke (Glasser-Leme and Matzke, 1982) pointed out vapor transport and thermal diffusion as important mechanisms of plutonium migration, respectively. Vapor transport and thermal diffusion are mainly influenced by temperature, oxygen/metal ratio, and initial plutonium content (Olander, 1976).…”

Section: Plutonium Redistribution Modulementioning

confidence: 99%

Multiphysics thermo-mechanical behavior modeling for annular uranium-plutonium mixed oxide fuels in a lead-cooled fast reactor

et al. 2022

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Understanding and predicting nuclear fuel behavior is the cornerstone for fuel design and optimization, and the safe and economic operation of nuclear reactors. Due to the excellent neutronic economy and safe operational characteristics of lead/lead-bismuth-based liquid metal coolant, lead-cooled fast reactor (LFR) has received much attention and has been regarded as one of the top candidate reactors for Generation IV nuclear power plants. Mixed oxide (MOX) fuel is beneficial to improve fuel cycle utilization and consume weapons-grade plutonium, among which hollow MOX fuel has excellent heat transfer advantages, which can further improve fuel economy and safety, and has good development prospects. In this work, an annular uranium-plutonium mixed oxide (MOX) fuel operating in a liquid lead/lead-bismuth cooled fast reactor is modeled and simulated to predict its behavior under transient and steady-state operation. This model has several modules working in a fully coupled approach based on COMSOL Multiphysics, such as heat transfer, fuel burnup, oxygen redistribution, plutonium redistribution, porosity evolution, fission gas release, JOG growth, and grain size evolution. The modeling results were benchmarked with the existing codes and experimental data, and the results were in satisfactory agreement. The parameters analysis was carried out in this work. Consistent with the solid MOX fuel, the O/M ratio (or deviation from the stoichiometry of oxygen) significantly affects temperature evolution, fission gas migration and release behavior, and plutonium redistribution. Linear power also has a significant influence on fuel performance.

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Plutonium redistribution in fast reactor mixed oxide fuel pins

Cited by 30 publications

References 7 publications

Solidus and liquidus temperatures in the UO2–PuO2 system

Solidus and liquidus temperatures in the UO2–PuO2 system

Radial redistribution of actinides in irradiated FR-MOX fuels

Multiphysics thermo-mechanical behavior modeling for annular uranium-plutonium mixed oxide fuels in a lead-cooled fast reactor

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