Management of Radioactive Waste Containing Graphite: Overview of Methods

被引:18
作者
Fuks, Leon [1 ]
Herdzik-Koniecko, Irena [1 ]
Kiegiel, Katarzyna [1 ]
Zakrzewska-Koltuniewicz, Grazyna [1 ]
机构
[1] Inst Nucl Chem & Technol, Ctr Radiochem & Nucl Chem, 16 Dorodna, PL-03161 Warsaw, Poland
关键词
graphite; irradiated graphite; graphite processing; radioactive waste; waste management; waste disposal; spent TRISO fuel; IRRADIATED GRAPHITE; NUCLEAR GRAPHITE; FUEL-ELEMENT; DISINTEGRATION; DISPOSAL; MATRIX;
D O I
10.3390/en13184638
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
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.
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页数:19
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