Abstract—
A radiometric method for measuring the 14C activity in irradiated graphite samples has been developed. The samples of graphite blocks used in the experiments have been taken from graphite stacks of uranium−graphite reactors that are being prepared for decommissioning and subsequent dismantling. The 14C radionuclide, which poses a radioecological hazard, is produced in reactor graphite during neutron irradiation and has a half-life of 5730 years. Therefore, the 14C content of radioactive waste produced upon dismantling of graphite stacks and elements of technological constructions must be monitored during decommissioning of uranium−graphite reactors. Taking the total volume of graphite in uranium−graphite reactors into account, it is desirable that a method for prompt monitoring of the 14C concentration in graphite be available. The radiometric method whose implementation is described here may be suitable for this purpose.
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ACKNOWLEDGMENTS
We are very grateful to D.A. Kuleshov for providing the samples of irradiated graphite from the Leningrad NPP. We are also grateful to the management of the Pilot and Demonstration Center for Decommissioning of Uranium-Graphite Nuclear Reactors for the scientific and technical cooperation on the problem of irradiated graphite of industrial reactors.
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Translated by N. Goryacheva
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Ignatov, S.M., Potapov, V.N., Simirskii, I.N. et al. A Radiometric Method for Measuring the 14С Activity in Irradiated Graphite. Instrum Exp Tech 62, 393–400 (2019). https://doi.org/10.1134/S0020441219020192
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DOI: https://doi.org/10.1134/S0020441219020192