Nuclear Engineering and Technology

  • 제48권1호
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  • Pages.182-188
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  • 2016
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Study on the Recycling of Nuclear Graphite after Micro-Oxidation

  • Liu, Juan (State Key Laboratory of New Ceramic and Fine Processing, Tsinghua University) ;
  • Wang, Chen (Beijing Key Laboratory of Fine Ceramics, Institute of Nuclear and New Energy Technology, Tsinghua University) ;
  • Dong, Limin (Beijing Key Laboratory of Fine Ceramics, Institute of Nuclear and New Energy Technology, Tsinghua University) ;
  • Liang, Tongxiang (State Key Laboratory of New Ceramic and Fine Processing, Tsinghua University)
  • 투고 : 2015.03.08
  • 심사 : 2015.08.16
  • 발행 : 2016.02.25
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초록

In this paper, a feasible strategy for the recycling of nuclear graphite is reported, based on the formation mechanism and the removal of carbon-14 by micro-oxidation. We investigated whether ground micro-oxidation graphite could be used as a filler to make new recycled graphite and which graphite/pitch coke ratio will give the recycled graphite outstanding properties (e.g., apparent density, flexural strength, compressive strength, and tensile strength). According to the existing properties of nuclear graphite, the ratio of graphite to pitch coke should not exceed 3. The recycled reactor graphite has been proven superior in density, strength, and thermal conductivity. The micro-oxidation process enhances the strength of the recycled graphite because there are more pores and unsmooth surfaces on the oxidized graphite particles, which is beneficial for the access of the pitch binder and leads to efficient joint adhesion among the graphite particles.

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참고문헌

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  3. Management of Radioactive Waste Containing Graphite: Overview of Methods vol.13, pp.18, 2016, https://doi.org/10.3390/en13184638
  4. Comparison of ultrafine-grain isotropic graphite prepared from microcrystalline graphite and pitch coke vol.290, pp.None, 2016, https://doi.org/10.1016/j.fuel.2020.120055
  5. A comprehensive review on decontamination of irradiated graphite waste vol.559, pp.None, 2016, https://doi.org/10.1016/j.jnucmat.2021.153475