Radionuclides in Irradiated Graphite of Uranium–Graphite Reactors: Decontamination by Thermochemical Methods
| Autor: | A. O. Pavlyuk, Andrey A. Shiryaev, N. I. Rodygina, Elena V. Zakharova, A. G. Volkova |
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| Rok vydání: | 2018 |
| Předmět: |
Annealing (metallurgy)
Chemistry 020209 energy Metallurgy chemistry.chemical_element 02 engineering and technology Human decontamination Crystal structure Uranium 010403 inorganic & nuclear chemistry 01 natural sciences 0104 chemical sciences Reagent Oxidizing agent 0202 electrical engineering electronic engineering information engineering Graphite Irradiation Physical and Theoretical Chemistry |
| Zdroj: | Radiochemistry. 60:657-663 |
| ISSN: | 1608-3288 1066-3622 |
| DOI: | 10.1134/s1066362218060152 |
| Popis: | Graphite samples from blocks and sleeves are characterized by extremely heterogeneous spatial distribution of radionuclides on the scale of tens and hundreds of micrometers. The graphite decontamination occurs in three steps: Up to 25% of 14C is removed in the course of low-temperature annealing or treatment of graphite with liquid reagents (total weight loss of graphite ≤10%); up to 70–80% of 14C is removed in the course of 20-h heat treatment under oxidizing conditions; and in the final step the degree of removal of 14C exceeds 90%, with a proportional decrease in the graphite weight. Oxidation of graphite in the first steps of thermochemical treatment mainly occurs along (micro)cracks and other defects, which favors the removal of relatively weakly bound 14C, e.g., from the pore space. The removal of 14C from the crystal lattice of graphite requires its breakdown, e.g., by high-temperature heat treatment. |
| Databáze: | OpenAIRE |
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