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- 저자 : Cozzella, (검색결과 2 건)
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Mauro Capone,Nadia Cherubini,Maria Letizia Cozzella,Alessandro Dodaro,Tiziana Guarcini 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.4
For the past 50 years, graphite has been widely used as a moderator, reflector and fuel matrix in differentkinds of gas-cooled reactors. Resulting in approximately 250,000 metric tons of irradiated graphitewaste. One of the most significant long-lived radioisotope from graphite reactors is carbon-14 (14C) [1]with a half-life of 5730 years, this makes it a huge concern for deep geologic disposal of nucleargraphite (NG). Considering the lifecycle of NG a number of waste management options have beendeveloped, mainly focused on the achievement the radiological requirements for disposal [2]. Theexisting approaches for recycling depend on the cost to be economically viable. In this new study, an affordable process to remove 14C has been proposed using samples taken fromthe Nuclear Power Plant in Latina (Italy) which have been used to investigate the capability of organicand inorganic solvents in removing 14C from exfoliated nuclear graphite, with the aim to design apracticable approach to obtain graphite for recycling or/and safety disposed as L& LLW.
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Pozzetto, Silvia,Capone, Mauro,Cherubini, Nadia,Cozzella, Maria Letizia,Dodaro, Alessandro,Guidi, Giambattista Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.4
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 <sup>14</sup>C and <sup>36</sup>Cl. 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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