HTGR Knowledge Base

Conference Article: On applicability of gas-fluoride technology to regeneration of spent HTGR fuel elements

Prusakov, V.N.; Trotsenko, N.M

Abstract

Alongside with the well known water extraction method of reprocessing the irradiated uranium-graphite fuel elements quite as interesting is an alternate method based on fluorination of irradiated nuclear fuel by elemental fluorine. The HTGR fuel elements can be fluorinated without preliminary removal of the graphite shells. In order to reduce the fluorine consumption the graphite can be removed prior to fluorination.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment Moscow (Russian Federation) 18-21 Oct 1983
International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria); State Committee on the Utilisation of Atomic Energy of the USSR, Moscow (Russian Federation)
IWGGCR--8, pp:383-387