Comparison of oxidation behaviour of nuclear graphite grades at very high temperatures

Lo, I-Hsuan; Yeh, Tsung‐Kuang; Patterson, E. A.; Tzelepi, Athanasia

doi:10.1016/j.jnucmat.2020.152054

Cited by 12 publications

(1 citation statement)

References 26 publications

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“…The thermal gasification rate of graphite in ambient air depends on the temperature. From the reported experimental results [23][24][25], the thermal gasification mechanism was dominated by air diffusing into the pores of the graphite surface at a gasification temperature lower than 1173 K. A recent study on the thermal gasification of irradiated graphite powder [16,24] has experimentally proved that controlling the gasification progress of the irradiated graphite can enrich radioactive carbon-oxygen compounds in the gaseous byproducts. It was also reported that, depending on thermal gasification circumstances such as gasification temperature, reaction duration, and ambient oxidant content, the observed ratio of radioactive carbonaceous gases to nonradioactive carbonaceous gases increase to 195.49.…”

Section: Introductionmentioning

confidence: 99%

Single-Phase Flow Model of a Screw Reactor for Decontamination of Radioactive Graphite Waste Using Surface Gasification

Yang

2022

Processes

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A screw reactor is a promising apparatus for decontaminating radioactive graphite waste by uniform gasification under ambient air. However, developing the design equation for a screw reactor is difficult due to the reactor’s fundamentally intricate gas and solid interactions. In this study, we performed three-dimensional computational fluid dynamics simulations to predict and characterize the graphite particles that flow through the screw reactor and are thermally gasified. This was done using the Eulerian single-fluid approach coupled with the experimentally established kinetic model for graphite gasification. The numerical results show that the counter-rotating flow, generated along the rotating screw of the reactor by the relative motion of the reactor wall to the rotating screw, mixes particles spatially and reduces their axial velocity. The diameter of the feed graphite particles can be reduced by as much as 28% depending on the screw rotating velocity and the temperature of the reactor shell, according to the conducted numerical calculations. These numerical simulations can be used to provide proper operating parameters for the laboratory-scale screw reactor by which to decontaminate radioactive graphite waste by gasifying the radiocarbons, together with a part of the graphite matrix, on the surface of the graphite particles.

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Section: Introductionmentioning

confidence: 99%

Single-Phase Flow Model of a Screw Reactor for Decontamination of Radioactive Graphite Waste Using Surface Gasification

Yang

2022

Processes

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Depth profile analysis of oxidized nuclear graphite microstructures using micro-focused synchrotron X-ray diffraction

Huang

et al. 2022

J Mater Sci

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Oxidation behaviors of matrix-grade graphite during water vapor ingress accidents for high temperature gas-cooled reactors

Cho

García

et al. 2021

Carbon

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Comparison of oxidation behaviour of nuclear graphite grades at very high temperatures

Cited by 12 publications

References 26 publications

Single-Phase Flow Model of a Screw Reactor for Decontamination of Radioactive Graphite Waste Using Surface Gasification

Single-Phase Flow Model of a Screw Reactor for Decontamination of Radioactive Graphite Waste Using Surface Gasification

Depth profile analysis of oxidized nuclear graphite microstructures using micro-focused synchrotron X-ray diffraction

Oxidation behaviors of matrix-grade graphite during water vapor ingress accidents for high temperature gas-cooled reactors

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