DEVELOPMENT OF TECHNOLOGY OF ELECTROCHEMICAL SEPARATION OF FUEL ELEMENT OF HTGR

High-temperature gas-cooled reactor (HTGR) by two-thirds consists of graphite. Graphite is a moderator and reflector of neutrons, as well as the main structural material of the active zone, which allows operating the reactor at high temperatures Graphite is moderator and neutron reflector, and the main structural material of the core, allowing the reactor to operate at high temperatures. Nuclear fuel is a spherical microfuel, which are compressed into a graphite compact, from which fuel assemblies are then assembled. The Institute of Nuclear Physics of the Republic of Kazakhstan is working on the qualification of irradiated fuel HTGR. To study the properties of the irradiated fuel HTGR, it is necessary to extract microfuel from the graphite matrix. The paper presents the results of experiments on the electrochemical separation of graphite and unirradiated fuel HTGR.

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