Management of Radioactive Waste Containing Graphite: Overview of Methods
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 tho...
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| Format: | Article |
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MDPI AG
2020-09-01
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| Series: | Energies |
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| Online Access: | https://www.mdpi.com/1996-1073/13/18/4638 |
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| author | Leon Fuks Irena Herdzik-Koniecko Katarzyna Kiegiel Grazyna Zakrzewska-Koltuniewicz |
| author_facet | Leon Fuks Irena Herdzik-Koniecko Katarzyna Kiegiel Grazyna Zakrzewska-Koltuniewicz |
| author_sort | Leon Fuks |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-03-10T16:31:44Z |
| format | Article |
| id | doaj.art-3b2c49ff6c204099b40486e505f3b2f4 |
| institution | Directory Open Access Journal |
| issn | 1996-1073 |
| language | English |
| last_indexed | 2024-03-10T16:31:44Z |
| publishDate | 2020-09-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Energies |
| spelling | doaj.art-3b2c49ff6c204099b40486e505f3b2f42023-11-20T12:49:10ZengMDPI AGEnergies1996-10732020-09-011318463810.3390/en13184638Management of Radioactive Waste Containing Graphite: Overview of MethodsLeon Fuks0Irena Herdzik-Koniecko1Katarzyna Kiegiel2Grazyna Zakrzewska-Koltuniewicz3Centre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, PolandCentre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, PolandCentre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, PolandCentre for Radiochemistry and Nuclear Chemistry, Institute of Nuclear Chemistry and Technology, 16 Dorodna, 03-161 Warszawa, PolandSince 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.https://www.mdpi.com/1996-1073/13/18/4638graphiteirradiated graphitegraphite processingradioactive wastewaste managementwaste disposal |
| spellingShingle | Leon Fuks Irena Herdzik-Koniecko Katarzyna Kiegiel Grazyna Zakrzewska-Koltuniewicz Management of Radioactive Waste Containing Graphite: Overview of Methods Energies graphite irradiated graphite graphite processing radioactive waste waste management waste disposal |
| title | Management of Radioactive Waste Containing Graphite: Overview of Methods |
| title_full | Management of Radioactive Waste Containing Graphite: Overview of Methods |
| title_fullStr | Management of Radioactive Waste Containing Graphite: Overview of Methods |
| title_full_unstemmed | Management of Radioactive Waste Containing Graphite: Overview of Methods |
| title_short | Management of Radioactive Waste Containing Graphite: Overview of Methods |
| title_sort | management of radioactive waste containing graphite overview of methods |
| topic | graphite irradiated graphite graphite processing radioactive waste waste management waste disposal |
| url | https://www.mdpi.com/1996-1073/13/18/4638 |
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