A Radiometric Method for Measuring the 14С Activity in Irradiated Graphite

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.