A method of obtaining a rough enriched uranium

 

(57) Abstract:

The invention relates to metallurgy, and in particular to methods for the recovery of uranium tetrafluoride calcium thermal method. The invention allows to obtain ingots draft enriched uranium without local inclusions of slag, increase the output of enriched uranium in a rough wedge and to create conditions for metallurgical processing chip enriched uranium. According to the claimed method melting is carried out in heated is not less than 200oC graphite reactor is enclosed in the insulating casing. Heating of the reactor and placing it in heat-insulating casing allow you to retain heat, making the reaction products are in the liquid state during the time for which there is the most complete separation of uranium and slag, as well as eliminate complex technology swarf recycling of uranium. 2 C.p. f-crystals, 1 Il.

The invention relates to metallurgy, and in particular to methods for the recovery of uranium tetrafluoride calcium thermal method.

A method of obtaining uranium recovery of uranium tetrafluoride with calcium (Y. N. Sikorski, J. M. sterling "Uranium and its alloys", M., Atomizdat, 1971, page 33) on the plant the Bush in France, on htoi washed with pure argon, stir the reaction of the electric fuse, and the ingot is cooled in an argon atmosphere.

The disadvantage of this method is the impossibility of receiving the draft enriched uranium.

The closest solution chosen for the prototype is the way calcium thermal recovery of uranium tetrafluoride, described in the monograph "fundamentals of metallurgy" so 5, Moscow, 1968, metallurgy, page 72. The method includes the mixture of uranium tetrafluoride with metallic calcium, filling the crucible with argon and initiation of melting by electric blasting.

The disadvantage of this method is the impossibility of obtaining draft enriched uranium.

The task of the invention is to produce ingots draft enriched uranium without local inclusions of slag, increasing the yield of enriched uranium in a rough wedge and creating conditions for metallurgical processing chip enriched uranium.

The problem is solved due to the fact that melting is carried out in pre-heated to a temperature of at least 200oC graphite reactor is enclosed in insulation jacket.

This set of features of the method is new and involves an inventive step, since heating of d are in the liquid state with the passage of time, for which there is the most complete separation of uranium and slag, as well as eliminate complex technology swarf recycling of uranium.

Getting rough metal enriched uranium by calcium thermal recovery of uranium tetrafluoride is carried out in small weight quantities.

Limiting the weight of the loaded charge materials results in a process of recovering uranium tetrafluoride to a significant deviation from the normal adiabatic process. This is due to large thermal losses, which reduces the yield of metal and contamination of uranium metal ingots slag and non-metallic inclusions. For this reason, it is impossible to melt the metal shavings enriched uranium produced after mechanical processing of ingots. In the chips is directed to chemical processing and only after completing a full expensive technological cycle is returned in the form of uranium tetrafluoride by reductive smelting.

The method is as follows.

Example 1.

The reactor graphite ARV type, consisting of a mold 1, the spacers 2 and case 3 cover technological exchange rate is not 4, close the annular heat-insulating casing 5 and is filled with argon.

Then fall asleep 6 kg of uranium tetrafluoride, mixed with 1900 g of metallic calcium.

Poured on top 20-30 grams of titanium metal powder and initiate melting of the electric blasting.

Time to solidification of the ingot is 3-5 hours, which is sufficient for complete separation of uranium and slag.

Snap-apart and separate the metal from the slag.

Get 4-4,5 kg of metal with a mass fraction of uranium 95%.

Example 2.

The reactor graphite ARV type, consisting of a mold 1, the spacers 2 and case 3 are coating technology coating, is heated in a resistance furnace to a temperature of at least 200oC, collected on the insulating pallet 4, close the annular heat-insulating casing 5 and is filled with argon.

On a cardboard disk, is placed on the mold in layers fall asleep 0.75-1.0 kg of uranium metal shavings, 3 kg of uranium tetrafluoride, mixed with metallic calcium, 0.75 to 1.0 kg of uranium metal shavings, 3 kg of uranium tetrafluoride, mixed with metallic calcium.

Initiate melting powder of titanium metal using electric blasting.

1. A method of obtaining a rough enriched uranium containing the mixture of uranium tetrafluoride with metallic calcium, initiation of melting by electric blasting, melting the mixture in an argon atmosphere, wherein the melting is carried out in a pre-heated reactor, placed in a heat-insulating casing.

2. The method according to p. 1, characterized in that the reactor is heated to a temperature not less than 200oC.

3. The method according to p. 1, characterized in that the charge injected shavings of metal enriched uranium.

 

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FIELD: production of pure niobium.

SUBSTANCE: method includes reducing fusion of niobium pentoxide with aluminum and calcium to provide crude ingots followed by heat treatment and multiple electron beam refining. As an additional raw material in step of reducing fusion sublimates (preferably in non-oxidized form) from second and subsequent electron beam refining are used. Such sublimates are obtained by subsequent cooling of furnace smelting chamber under residual pressure of 10-2-10-4 mmHg for 1.0-3.0 h, letting-to-helium under 1-3 mmHg for 1.0-3.0 h, and letting-to-air for 20-40 min. Sublimates are added in amount of 4.5 % based to feeding niobium pentoxide. Claimed method affords the ability to increase niobium pentoxide consumption by 73 kg in respect to 1000 kg of pure niobium in crude ingots.

EFFECT: production of pure niobium with increased effectiveness without deterioration of refined niobium quality.

2 cl, 1 tbl

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