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 ( 14 C)[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 14 C 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 14 C from exfoliated nuclear graphite, with the aim to design a practicable approach to obtain graphite for recycling or/and safety disposed as L& LLW.

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

Capone M.;Cherubini N.;Cozzella M. L.;Dodaro A.;Guarcini T.
2019

Abstract

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 ( 14 C)[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 14 C 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 14 C from exfoliated nuclear graphite, with the aim to design a practicable approach to obtain graphite for recycling or/and safety disposed as L& LLW.
14; C removal ; Exfoliation process ultrasound assisted; Nuclear waste; Recover and recycling of irradiated graphite
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/52215
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