Management of Radioactive Waste Containing Graphite: Overview of Methods

Leon Fuks, Irena Herdzik-Koniecko, Katarzyna Kiegiel and Grazyna Zakrzewska-Koltuniewicz
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Leon Fuks: Centre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, Poland
Irena Herdzik-Koniecko: Centre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, Poland
Katarzyna Kiegiel: Centre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, Poland
Grazyna Zakrzewska-Koltuniewicz: Centre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, Poland

Energies, 2020, vol. 13, issue 18, 1-19

Abstract: Since the beginning of the nuclear industry, graphite has been widely used as a moderator and reflector of neutrons in nuclear power reactors. Some reactors are relatively old and have already been shut down. As a result, a large amount of irradiated graphite has been generated. Although several thousand papers in the International Nuclear Information Service (INIS) database have discussed the management of radioactive waste containing graphite, knowledge of this problem is not common. The aim of the paper is to present the current status of the methods used in different countries to manage graphite-containing radioactive waste. Attention has been paid to the methods of handling spent TRISO fuel after its discharge from high-temperature gas-cooled reactors (HTGR) reactors.

Keywords: graphite; irradiated graphite; graphite processing; radioactive waste; waste management; waste disposal; spent TRISO fuel (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2020
References: View complete reference list from CitEc
Citations: View citations in EconPapers (2)

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