Fuel performance of hollow pellets for fast breeder reactors

Ishimi, Akihiro; Katsuyama, Kozo; Kihara, Yoshiyuki; Furuya, Hirotaka

doi:10.1080/00223131.2015.1085337

Cited by 5 publications

(4 citation statements)

References 2 publications

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“…Regarding the behavior under irradiation of Gd 2 O 3 , based on the reference [11] and thermodynamic calculation, it is estimated that Gd 2 O 3 remains stable in the central region of MOX fuel even under irradiation.…”

Section: Resultsmentioning

confidence: 99%

Conceptual Study on Recriticality Prevention Core Having Duplex Pellets with Neutron Absorber in Outer Core in a Fast Reactor

Wakabayashi

Takahashi

Takaki

et al. 2019

Science and Technology of Nuclear Installations

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In a fast reactor, we evaluated a new core concept that prevents severe recriticality after whole-scale molten formation in a severe accident. A core concept in which Duplex pellets including neutron absorber are loaded in the outer core has been proposed. Analysis by the continuous energy model Monte Carlo code MVP using the JENDL-4.0 nuclear data library revealed that this fast reactor core has large negative reactivity due to fuel melting at the time of a severe accident, so that the core prevents recriticality. Regarding the core nuclear and thermal characteristics, the loading of Duplex pellets including neutron absorber in the outer core caused no significant differences from the normal core without Duplex pellets.

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Section: Resultsmentioning

confidence: 99%

Conceptual Study on Recriticality Prevention Core Having Duplex Pellets with Neutron Absorber in Outer Core in a Fast Reactor

Wakabayashi

Takahashi

Takaki

et al. 2019

Science and Technology of Nuclear Installations

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“…However, the difference in temperature increases with deepening burnup. As shown in Figure 9, the difference in thermal conductivity between the inner and outer surfaces of Microstructures of fuel region around the hollow fuel pellets at different burnups (Ishimi et al, 2016).…”

Section: Frontiers In Energy Researchmentioning

confidence: 95%

“…The pores formed by the void migration and growth of fission gas bubbles moved to the hollow edge part and became coarsened (Ishimi et al, 2016). Compared with the porosities for different deviations from the stoichiometry of oxygen, the porosity of the pellet inner surface increases when the deviation from the stoichiometry of oxygen increases, which is caused by the rise in temperature and the swelling of fission gas.…”

Section: Frontiers In Energy Researchmentioning

confidence: 99%

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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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A review of microstructural features in fast reactor mixed oxide fuels

Parrish

Aitkaliyeva

2018

Journal of Nuclear Materials

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Fuel performance of hollow pellets for fast breeder reactors

Cited by 5 publications

References 2 publications

Conceptual Study on Recriticality Prevention Core Having Duplex Pellets with Neutron Absorber in Outer Core in a Fast Reactor

Conceptual Study on Recriticality Prevention Core Having Duplex Pellets with Neutron Absorber in Outer Core in a Fast Reactor

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

A review of microstructural features in fast reactor mixed oxide fuels

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