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


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Аннотация

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.

Авторлар туралы

S. Ignatov

National Research Center Kurchatov Institute

Email: potapov_v@mail.ru
Ресей, Moscow, 123182

V. Potapov

National Research Center Kurchatov Institute

Хат алмасуға жауапты Автор.
Email: potapov_v@mail.ru
Ресей, Moscow, 123182

Iu. Simirskii

National Research Center Kurchatov Institute

Email: potapov_v@mail.ru
Ресей, Moscow, 123182

A. Stepanov

National Research Center Kurchatov Institute

Email: potapov_v@mail.ru
Ресей, Moscow, 123182

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