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


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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.

作者简介

S. Ignatov

National Research Center Kurchatov Institute

Email: potapov_v@mail.ru
俄罗斯联邦, Moscow, 123182

V. Potapov

National Research Center Kurchatov Institute

编辑信件的主要联系方式.
Email: potapov_v@mail.ru
俄罗斯联邦, Moscow, 123182

Iu. Simirskii

National Research Center Kurchatov Institute

Email: potapov_v@mail.ru
俄罗斯联邦, Moscow, 123182

A. Stepanov

National Research Center Kurchatov Institute

Email: potapov_v@mail.ru
俄罗斯联邦, Moscow, 123182

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