Abstract
The release of long-lived radionuclides 14C and 36Cl , which are key products for assessment of disposal variants (near-surface, buried, or deep) of irradiated graphite, was analyzed. Test material was irradiated graphite from IUGR and RBMK-1000 reactors. Unlike other types of radioactive waste (RAW), graphite has the developed pore structure and, consequently, its effective surface area in contact with the leaching medium is increased in comparison with non-porous materials. With due to regard for the graphite pore structure, the mechanism describing the leaching process is proposed and experimentally substantiated. The parameters numerically characterizing graphite RAW in terms of leaching resistance, independent of the geometric shape of individual fragments (samples) are also introduced. The proposed parameters and an algorithm for their determination are recommended by the authors for use in predictive calculations of the release of radionuclides from graphite under conditions of long-term storage/disposal.
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Funding
The activity of 14С and 36Cl radionuclides in the samples was measured on an equipment of the Center for the Collective Use of Physical Research Methods of the Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences (CCU PMI IPCE RAS). The study was supported in part by the Program no. 14P of the Presidium of the Russian Academy of Sciences.
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Translated from Radiokhimiya, No. 2, pp. 149–159, February, 2021 https://doi.org/10.31857/S0033831121020088
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Pavlyuk, A.O., Kotlyarevskii, S.G., Kan, R.I. et al. Study of the Process of Leaching of Long-Lived Radionuclides 14С and 36Сl from Irradiated Graphite. Radiochemistry 63, 187–196 (2021). https://doi.org/10.1134/S1066362221020090
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DOI: https://doi.org/10.1134/S1066362221020090