The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling

For the past 50 years, graphite has been widely used as a moderator, reflector and fuel matrix in different kinds of gas-cooled reactors. Resulting in approximately 250,000 metric tons of irradiated graphite waste. One of the most significant long-lived radioisotope from graphite reactors is carbon-...

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Main Authors: Mauro Capone, Nadia Cherubini, Maria Letizia Cozzella, Alessandro Dodaro, Tiziana Guarcini
Format: Article
Language:English
Published: Elsevier 2019-07-01
Series:Nuclear Engineering and Technology
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573318307447
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spelling doaj-e5e7efa7fdff4a2ab0999283f646941c2020-11-25T02:14:47ZengElsevierNuclear Engineering and Technology1738-57332019-07-0151410371040The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recyclingMauro Capone0Nadia Cherubini1Maria Letizia Cozzella2Alessandro Dodaro3Tiziana Guarcini4ENEA Italian National Agency for New Technologies, Energy and Sustainable Economic, Development Nuclear Material Characterization Laboratory, Nuclear Waste Management, ItalyENEA Italian National Agency for New Technologies, Energy and Sustainable Economic, Development Nuclear Material Characterization Laboratory, Nuclear Waste Management, ItalyCorresponding author.; ENEA Italian National Agency for New Technologies, Energy and Sustainable Economic, Development Nuclear Material Characterization Laboratory, Nuclear Waste Management, ItalyENEA Italian National Agency for New Technologies, Energy and Sustainable Economic, Development Nuclear Material Characterization Laboratory, Nuclear Waste Management, ItalyENEA Italian National Agency for New Technologies, Energy and Sustainable Economic, Development Nuclear Material Characterization Laboratory, Nuclear Waste Management, ItalyFor the past 50 years, graphite has been widely used as a moderator, reflector and fuel matrix in different kinds of gas-cooled reactors. Resulting in approximately 250,000 metric tons of irradiated graphite waste. 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 nuclear graphite (NG). Considering the lifecycle of NG a number of waste management options have been developed, mainly focused on the achievement the radiological requirements for disposal [2]. The existing 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 from the Nuclear Power Plant in Latina (Italy) which have been used to investigate the capability of organic and inorganic solvents in removing 14C from exfoliated nuclear graphite, with the aim to design a practicable approach to obtain graphite for recycling or/and safety disposed as L& LLW. Keywords: 14C removal, Nuclear waste, Exfoliation process ultrasound assisted, Recover and recycling of irradiated graphitehttp://www.sciencedirect.com/science/article/pii/S1738573318307447
collection DOAJ
language English
format Article
sources DOAJ
author Mauro Capone
Nadia Cherubini
Maria Letizia Cozzella
Alessandro Dodaro
Tiziana Guarcini
spellingShingle Mauro Capone
Nadia Cherubini
Maria Letizia Cozzella
Alessandro Dodaro
Tiziana Guarcini
The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling
Nuclear Engineering and Technology
author_facet Mauro Capone
Nadia Cherubini
Maria Letizia Cozzella
Alessandro Dodaro
Tiziana Guarcini
author_sort Mauro Capone
title The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling
title_short The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling
title_full The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling
title_fullStr The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling
title_full_unstemmed The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling
title_sort exfoliation of irradiated nuclear graphite by treatment with organic solvent: a proposal for its recycling
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2019-07-01
description For the past 50 years, graphite has been widely used as a moderator, reflector and fuel matrix in different kinds of gas-cooled reactors. Resulting in approximately 250,000 metric tons of irradiated graphite waste. 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 nuclear graphite (NG). Considering the lifecycle of NG a number of waste management options have been developed, mainly focused on the achievement the radiological requirements for disposal [2]. The existing 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 from the Nuclear Power Plant in Latina (Italy) which have been used to investigate the capability of organic and inorganic solvents in removing 14C from exfoliated nuclear graphite, with the aim to design a practicable approach to obtain graphite for recycling or/and safety disposed as L& LLW. Keywords: 14C removal, Nuclear waste, Exfoliation process ultrasound assisted, Recover and recycling of irradiated graphite
url http://www.sciencedirect.com/science/article/pii/S1738573318307447
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