Nuclear Engineering and Technology

  • 제52권4호
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  • Pages.797-801
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  • 2020
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Proposal of a prototype plant based on the exfoliation process for the treatment of irradiated graphite

  • Pozzetto, Silvia (ENEA Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Nuclear Material Characterization Laboratory and Nuclear Waste Management) ;
  • Capone, Mauro (ENEA Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Nuclear Material Characterization Laboratory and Nuclear Waste Management) ;
  • Cherubini, Nadia (ENEA Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Nuclear Material Characterization Laboratory and Nuclear Waste Management) ;
  • Cozzella, Maria Letizia (ENEA Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Nuclear Material Characterization Laboratory and Nuclear Waste Management) ;
  • Dodaro, Alessandro (ENEA Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Nuclear Material Characterization Laboratory and Nuclear Waste Management) ;
  • Guidi, Giambattista (ENEA - Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Energy Technology Department and Guglielmo Marconi University)
  • 투고 : 2019.03.18
  • 심사 : 2019.09.16
  • 발행 : 2020.04.25
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초록

Most of irradiated graphite that should be disposed comes from moderators and reflectors of nuclear power plants. The quantity of irradiated graphite could be higher in the future if high-temperature reactors (HTRs) will be deployed. In this case noteworthy quantities of fuel pebbles containing semi-graphitic carbonaceous material should be added to the already existing 250,000 tons of irradiated graphite. Industry graphite is largely used in industrial applications for its high thermal and electrical conductivity and thermal and chemical resistance, making it a valuable material. Irradiated graphite constitutes a waste management challenge owing to the presence of long-lived radionuclides, such as 14C and 36Cl. In the ENEA Nuclear Material Characterization Laboratory it has been successfully designed a procedure based on the exfoliation process organic solvent assisted, with the purpose of investigate the possibility of achieving graphite significantly less toxic that could be recycled for other purpose [1]. The objective of this paper is to evaluate the possibility of the scalability from laboratory to industrial dimensions of the exfoliation process and provide the prototype of a chemical plant for the treatment of irradiated graphite.

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참고문헌

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피인용 문헌

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  2. A comprehensive review on decontamination of irradiated graphite waste vol.559, 2020, https://doi.org/10.1016/j.jnucmat.2021.153475