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Development of integrated waste management options for irradiated graphite
Alan Wareing,Liam Abrahamsen-Mills,Linda Fowler,Michael Grave,Richard Jarvis,Martin Metcalfe,Simon Norris,Anthony William Banford 한국원자력학회 2017 Nuclear Engineering and Technology Vol.49 No.5
The European Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste projectsought to develop best practices in the retrieval, treatment, and disposal of irradiated graphite includingother irradiated carbonaceous waste such as structural material made of graphite, nongraphitized carbonbricks, and fuel coatings. Emphasis was given on legacy irradiated graphite, as this represents a significantinventory in respective national waste management programs. This paper provides an overview ofthe characteristics of graphite irradiated during its use, primarily as a moderator material, within nuclearreactors. It describes the potential techniques applicable to the retrieval, treatment, recycling/reuse, anddisposal of these graphite wastes. Considering the lifecycle of nuclear graphite, from manufacture to finaldisposal, a number of waste management options have been developed. These options consider thetechniques and technologies required to address each stage of the lifecycle, such as segregation, treatment,recycle, and ultimate disposal in a radioactive waste repository, providing a toolbox to aid operatorsand regulators to determine the most appropriate management strategy. It is noted that nationalwaste management programs currently have, or are in the process of developing, respective approachesto irradiated graphite management. The output of the Treatment and Disposal of Irradiated Graphite andother Carbonaceous Waste project is intended to aid these considerations, rather than dictate them.