Radionuclides in Irradiated Graphite of Uranium–Graphite Reactors: Decontamination of Sleeves Using Liquid Reagents
- 作者: Volkova A.1, Zakharova E.1, Pavlyuk A.2, Shiryaev A.1
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隶属关系:
- Frumkin Institute of Physical Chemistry and Electrochemistry
- Experimental and Demonstration Center for Decommissioning of Uranium–Graphite Reactors
- 期: 卷 60, 编号 5 (2018)
- 页面: 558-562
- 栏目: Article
- URL: https://journals.rcsi.science/1066-3622/article/view/224745
- DOI: https://doi.org/10.1134/S1066362218050144
- ID: 224745
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详细
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.
作者简介
A. Volkova
Frumkin Institute of Physical Chemistry and Electrochemistry
Email: shiryaev@phyche.ac.ru
俄罗斯联邦, Leninskii pr. 31, korp. 4, Moscow, 119071
E. Zakharova
Frumkin Institute of Physical Chemistry and Electrochemistry
Email: shiryaev@phyche.ac.ru
俄罗斯联邦, Leninskii pr. 31, korp. 4, Moscow, 119071
A. Pavlyuk
Experimental and Demonstration Center for Decommissioning of Uranium–Graphite Reactors
Email: shiryaev@phyche.ac.ru
俄罗斯联邦, Seversk, Tomsk oblast, 636000
A. Shiryaev
Frumkin Institute of Physical Chemistry and Electrochemistry
编辑信件的主要联系方式.
Email: shiryaev@phyche.ac.ru
俄罗斯联邦, Leninskii pr. 31, korp. 4, Moscow, 119071