Heat-aided method for separating the graphite matrix from the nu

Details Heat-aided method for separating the graphite matrix from the nu Heat-aided method for separating the graphite matrix from the nu

1982-12-07

1985-03-26

Kyle, Deborah L.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

252639, 264 05, G21C 1942, C01G 5600

Patent

active

045072671

ABSTRACT:
Removal of the graphite structure from the nuclear fuel material of fuel elements of gas-cooled high-temperature reactors is performed by heat-treatment of the fuel elements in oxygen-containing gas at temperatures below 700.degree. C. until the carbon or graphite structure is loosened up and converted into a mechanically removable material. During heat-treatment, mechanical forces are preferably applied for continually removing the outer layers that are most heavily attacked and transport of the dust into cooler temperature zones. For this purpose, the fuel elements are agitated during heat-treatment, as by an oscillating sieve or by brushes. Pre-impregnation with a material catalyzing the combustion is useful if it is important to have the heat-treatment temperature as low as possible.

REFERENCES:
patent: 3453090 (1969-07-01), Schulter
patent: 4134941 (1979-01-01), Hrovat
patent: 4228141 (1980-10-01), Sugikawa
Inorganic Chemistry, E. Barnett, Longmans, Green and Co., London, 2nd Ed., 957, p. 410.
Nuclear Graphite, R. Nightingale, Academic Press, NY and London, 1962, p. 450.
R. Bohnert and G. Kaiser-Apr. 14, 1972, pp. 252-255 of OAEF Reactor Conf. in Hamburg, Germany.

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