METHOD FOR RECOVERING REACTOR GRAPHITE WASTE Russian patent published in 2004 - IPC

Abstract RU 2242814 C1

FIELD: recovery of high-activity wastes.

SUBSTANCE: proposed method includes crushing of reactor graphite waste and its separation into several fractions, that is fine fraction having particle size of 50 μm and below and coarse fraction with particles measuring 50 to 100 μm. Then fine and coarse fractions of crushed reactor graphite waste are mixed up, mass proportion of fine and coarse fractions being 95 : 5 to 10 : 90. Introduced in mixture of crushed reactor graphite waste are rutile concentrate as oxide of carbide-forming element, powdered aluminum as energy carrier, and modifier, proportion of ingredients being as follows, mass percent: graphite waste, 7 - 11; powdered aluminum, 23 - 30; rutile concentrate, 53 - 64; modifier, 2 - 15. Then mixture prepared in this way is charged in container and igniter composition layer is placed on top. Mixture is given heat treatment under self-spreading high-temperature fusion conditions to form carbide oxide material including radionuclides. Prior to charging mixture inner surfaces of container walls and its bottom are covered with asbestos sheets. End product formed within container is allowed to cool down under natural conditions.

EFFECT: prevented escape of radionuclides into environment; enhanced strength of end product obtained.

4 cl, 1 dwg, 4 tbl, 3 ex

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RU 2 242 814 C1

Authors

Dmitriev S.A.

Karlina O.K.

Klimov V.L.

Pavlova G.Ju.

Jurchenko A.Ju.

Dates

2004-12-20Published

2003-04-01Filed