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http://dx.doi.org/10.1016/j.net.2019.09.006

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)
Publication Information
Nuclear Engineering and Technology / v.52, no.4, 2020 , pp. 797-801 More about this Journal
Abstract
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.
Keywords
Irradiated graphite; $^{14}C$; Prototype plant; Solvent recycling; Graphite reuse; Exfoliation process;
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Times Cited By KSCI : 5  (Citation Analysis)
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1 M.L. Dunzik-Gougar, T.E. Smith, Removal of carbon-14 from irradiated graphite, J. Nucl. Mater. 451 (2014) 328-335.   DOI
2 W. Von Lensa, D. Vulpius, H.J. Steinmetz, Treatment and disposal of irradiated graphite and other carbonaceous waste, ATW Int. Z. fuer Kernenergie 57 (4-5) (2011) 263-269.
3 F. Kang, Y.P. Zheng, H.N. Wang, Y. Nishi, M. Inagaki, Effect of preparation conditions on the characteristics of exfoliated graphite, Carbon 40 (2002) 1575-1581.   DOI
4 H. Feng, Y. Wu, J. Li, Direct exfoliation of graphite to graphene by a facile chemical approach, Small 10 (issue 11) (2004) 2233-2238.   DOI
5 M.P. Lavin Lopez, Solventebased exfoliation via sonication of graphitic materials for graphene manufacture, Ind. Eng. Chem. Res. 55 (2016) 845-855.   DOI
6 Y. Hernandez V. Nicolosi, M. Lotya, F. Blighe, Z. Sun, S. De, I.T. McGovern, B. Holland, M. Byrne, Y. Gunko, J. Boland, P. Niraj, G. Duesberg, S. Krishnamurti, R. Goodhue, J. Hutchison, V. Scardaci, A.C. Ferrari, J.N. Coleman, High yield production of graphene by liquid phase exfoliation of graphite, Nat. Nanotechnol. 3 (2008) 563-568.   DOI
7 Y. Nomura, Y. Morita, S. Deguchi, S. Mukai, Anomalously stable dispersions of graphite in water/acetone mixtures, J. Colloid Interface Sci. 346 (2010) 96-99.   DOI
8 S. Fujii, M. Shirakawa, T. Murakami, Study on Efficient Methods for Removal and Treatment of Graphite Blocks in a Gas Cooled Reactor. Technologies for Gas Cooled Reactor Decommissioning, Fuel Storage and Waste Disposal, 8-10 September 1997. IAEA-TECDOC-1043 Julich, Germany.
9 A. Sesis, M. Hodnett, G. Memoli, A.J. Wain, I. Jurewicz, A.B. Dalton, J.D. Carey, G. Hinds, Influence of acoustic cavitation on the controlled ultrasonic dispersion of carbon nanotubes, J. Phys. Chem. B 117 (2013) 15141-15150.   DOI
10 T. Meek, Q. Han, Ultrasonic Processing of Materials, Final Technical Report, U.S. Department of Energy, Industrial Materials for the future, June 2006. ORNL/TM-2005/125.
11 J. Liu, C. Wang, L. Dong, T. Liang, Study on the recycling of nuclear graphite after micro-oxidation, Nucl. Eng. Technol. 48 (2016) 182-188.   DOI
12 A. Wareing, L. Abrahamsen-Mills, L. Fowler, M. Grave, R. Jarvis, M. Metcalfe, S. Norris, A.W. Banford, Development of integrated waste management options for irradiated graphite, Nucl. Eng. Technol. 49 (2017) 1010-1018.   DOI
13 G.I. Eskin, Ultrasonic Treatment of Light Alloy Melts, Gordon and Breach, Amsterdam, 1998, ISBN 905699042X.
14 M. Capone M, N. Cherubini, M.L. Cozzella, A. Dodaro, T. Guarcini, The exfoliation of irradiated nuclear graphite by treatment with organic solvent: a proposal for its recycling, Nucl. Eng. Technol. 51 (2019) 1037-1040.   DOI
15 IAEA, Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal - Results of a Coordinated Research Project, International Atomic Energy Agency, 2016. IAEA-TECDOC-1790.
16 IAEA, Characterization, Treatment and Conditioning of Radioactive Graphite from Decommissioning of Nuclear Reactors, International Atomic Energy Agency, 2006. IAEA-TECDOC-1521.
17 IAEA, Progress in Radioactive Graphite Waste Management, International Atomic Energy Agency, 2010. IAEA-TECDOC-1647.
18 J. Fachinger, W. von Lensa, T. Podruhzina, Decontamination of nuclear graphite, Nucl. Eng. Des. 238 (2008) 3086-3091.   DOI
19 J. Li, M.L. Dunzik-Gouga, J. Wang, Recent advances in the treatment of irradiated graphite: a review, Ann. Nucl. Energy 110 (2017) 140-147.   DOI
20 T.E. Smith, S. Mc Crory, M.L. Dunzik-Gougar, Limited oxidation of irradiated graphite waste to remove surface carbon 14, Nucl. Eng. Technol. 45 (2013) 211-218.   DOI