Radionuclides in Irradiated Graphite of Uranium–Graphite Reactors: Decontamination of Sleeves Using Liquid Reagents

To examine the possibility of disposal of irradiated graphite in ground near-surface repositories, the concentration and spatial distribution of radionuclides in the volume of irradiated graphite sleeves of industrial uranium–graphite reactors was studied, and the efficiency of decontamination using...

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Bibliographic Details
Published in:Radiochemistry (New York, N.Y.) N.Y.), 2018-09, Vol.60 (5), p.558-562
Main Authors: Volkova, A. G., Zakharova, E. V., Pavlyuk, A. O., Shiryaev, A. A.
Format: Article
Language:English
Subjects:
Carbon 14
Chemistry
Chemistry and Materials Science
Chemistry/Food Science
Decontamination
Graphite
Nuclear Chemistry
Radioisotopes
Reactors
Reagents
Repositories
Sleeves
Spatial distribution
Uranium
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Summary:To examine the possibility of disposal of irradiated graphite in ground near-surface repositories, the concentration and spatial distribution of radionuclides in the volume of irradiated graphite sleeves of industrial uranium–graphite reactors was studied, and the efficiency of decontamination using liquid reagent treatment methods was evaluated. The radionuclide distribution in the graphite volume is extremely heterogeneous on the 10–100 μm scale. The degree of decontamination using solutions with high acid concentrations and fluoride ions added does not exceed 16–25% for 14 C and 15–19% for 36 Cl. Under these treatment conditions, no structural changes occur in graphite, and 14 С bound with the graphite surface via sorption is removed. Significant differences in the efficiency of the reagent decontamination of irradiated graphite from various producers were revealed.
ISSN:1066-3622
1608-3288
DOI:10.1134/S1066362218050144