Grand Challenges in Nuclear Engineering

Dudarev, S. L.

doi:10.3389/fnuen.2022.945270

Cited by 2 publications

(1 citation statement)

References 45 publications

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“…In the nuclear industry, these diffusion properties are of paramount interest since they directly impact the in-pile performances of the fuel and hence the safety of the reactor. For instance, uranium-plutonium U 1−y Pu y O 2 mixed oxides (MOX), with various compositions, are used for decades for nuclear power all over the world (Olander, 2009;Baron et al, 2020;Kato et al, 2020;Dudarev, 2022;Kato and Machida, 2022). During their lifetime, MOX fuel pellets undergo the harshest temperature, atmosphere, and irradiation conditions.…”

Section: Introductionmentioning

confidence: 99%

Cation interdiffusion in uranium–plutonium mixed oxide fuels: Where are we now?

Vauchy

Hirooka²,

Matsumoto³

et al. 2022

Front. Nucl. Eng.

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The diffusion phenomena in uranium–plutonium mixed oxides U1−yPuyO2 dictate the physicochemical properties of mixed oxides (MOX) nuclear fuel throughout manufacturing, irradiation, and storage. More precisely, it is paramount to estimate the cation interdiffusion insofar as it dovetails with the actinide redistribution during sintering and under irradiation. This paper draws a critical review of the existing experimental data of U and Pu interdiffusion coefficients in MOX fuel.

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Section: Introductionmentioning

confidence: 99%

Cation interdiffusion in uranium–plutonium mixed oxide fuels: Where are we now?

Vauchy

Hirooka²,

Matsumoto³

et al. 2022

Front. Nucl. Eng.

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Recovery of neutron-irradiated VVER-440 RPV base metal and weld exposed to isothermal annealing at 343°C up to 2,000 h

Altstadt,

Bergner,

Brandenburg

et al. 2024

Front. Nucl. Eng.

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Neutron irradiation causes embrittlement of reactor pressure vessel (RPV) steels. Post-irradiation annealing is capable of partly or fully restoring the unembrittled condition. While annealing at high temperatures (e.g., 475°C) was successfully applied to extend the lifetime of operating VVER-440 reactors, the benefit of annealing at lower temperatures (e.g., 343°C–the maximum to which the primary cooling water can be heated) is a matter of debate. In this study, neutron-irradiated VVER-440 RPV base metal and weld were exposed to isothermal annealing at 343°C up to 2,000 h. Given the limited amount of material, the degree of recovery was estimated in terms of Vickers hardness, the ductile-brittle transition temperature derived from small punch tests, and the master curve reference temperature derived from fracture mechanics tests of mini samples. For the base metal, small-angle neutron scattering was applied to underpin the findings at the nm-scale. We have found significant partial recovery in both materials after annealing for 300 h or longer. The variations of the degree of recovery are critically discussed and put into the context of wet annealing.

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Grand Challenges in Nuclear Engineering

Cited by 2 publications

References 45 publications

Cation interdiffusion in uranium–plutonium mixed oxide fuels: Where are we now?

Cation interdiffusion in uranium–plutonium mixed oxide fuels: Where are we now?

Recovery of neutron-irradiated VVER-440 RPV base metal and weld exposed to isothermal annealing at 343°C up to 2,000 h

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