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


Ontology type: schema:ScholarlyArticle     


Article Info

DATE

2018-09

AUTHORS

A. G. Volkova, E. V. Zakharova, A. O. Pavlyuk, A. A. Shiryaev

ABSTRACT

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 14C and 15–19% for 36Cl. Under these treatment conditions, no structural changes occur in graphite, and 14С 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. More... »

PAGES

558-562

Journal

TITLE

Radiochemistry

ISSUE

5

VOLUME

60

Author Affiliations

Identifiers

URI

http://scigraph.springernature.com/pub.10.1134/s1066362218050144

DOI

http://dx.doi.org/10.1134/s1066362218050144

DIMENSIONS

https://app.dimensions.ai/details/publication/pub.1110131776


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