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)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 . 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.
|Titolo:||The exfoliation of irradiated nuclear graphite by treatment with organic solvent: A proposal for its recycling|
|Data di pubblicazione:||2019|
|Appare nelle tipologie:||1.1 Articolo in rivista|