JP2008297627A - Apparatus for continuous electrorefining of metal uranium - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide an apparatus for continuous electrorefining of metal uranium, which requires no scraping and enables continuous, efficient recovery of highly pure metal uranium deposits and transition metals produced during electrolysis without interrupting the electrolysis. <P>SOLUTION: The apparatus for continuous electrorefining comprises: a cathode part 20 which is fixed below a radiator plate 10 and has several graphite cathodes 22 mounted thereon; an anode part 30 which faces and surrounds the cathode part 20, is rotatably fixed below the radiator plate 10 and receives nuclear spent fuel; an electrolytic cell 40 filled with an electrolyte in which the cathode part 20 and the anode part 30 are soaked; a metal uranium recovering part 50 which collects metal uranium and takes it out of the apparatus; and a transition metal recovering part 60 which is connected to the bottom of the electrolytic cell 40 to take out a transition metal sludge which derives from the anode part 30 and is deposited onto and collected at the bottom of the electrolytic cell 40. In the metal uranium recovering part 50, the metal uranium is electrodeposited onto the graphite cathodes 22 at the bottom of the cathode 20 and subsequently is desorbed. <P>COPYRIGHT: (C)2009,JPO&INPIT

Description

  The present invention relates to an apparatus for electrolytic refining of metal uranium. More specifically, the present invention relates to a continuous electrolytic refining apparatus for metal uranium capable of continuously recovering transition metal without interrupting the electrolysis process when recovering uranium deposits and transition metal generated in the electrolysis process. .

  As is well known, an electrorefining apparatus for metal uranium used as a conventional nuclear fuel is composed of an anode basket that receives a piece of spent metal nuclear fuel in a molten salt of about 500 ° C. in which uranium trichloride is melted, It is composed of an iron-based cathode on which uranium is electrodeposited.

When refining metal uranium using the conventional metal uranium electrolytic refining apparatus, when current is applied, uranium trichloride in the molten salt is reduced and electrodeposited on the cathode. The chlorine ions separated by the electrolytic reaction selectively dissolve metal uranium electrically at the anode. Pure metal uranium can be separated by repeating the process of electrolytic refining of metal uranium.
However, the process of electrolytic smelting of metal uranium using the conventional metal uranium electrolytic smelting apparatus has to interrupt the electrolytic reaction in order to periodically recover the metal uranium electrodeposited on the cathode. There is a problem in that a large amount of electrodeposits cannot be collected in a short time because it takes a long time and effort to collect the kimono and continuous operation is impossible.

Various electrorefining apparatuses that solve such problems and attempt to separate pure metal uranium at high speed have been reported.
According to the disclosed technique of US Pat. No. 5,650,053 (1997.7.22), a section of spent metal nuclear fuel was placed in an anode basket of a perforated plate in a molten salt at about 500 ° C. When several anode baskets are positioned inside and outside of a cathode in the form of a tube and a power source is applied while rotating the anode basket, metal uranium in the anode basket is eluted and electrodeposited on the cathode. The refining apparatus of US Pat. No. 5,650,053 is provided at the bottom of the anode basket by scraping metal uranium electrodeposited on the cathode with a ceramic plate attached to the outside of the anode basket. Collect in the collection department.

However, in the refining apparatus, only a part of the metal uranium electrodeposited on the cathode is desorbed, and the remaining electrodeposit remains attached to the surface of the cathode and changes to a dense structure that makes desorption more difficult.
Therefore, depending on the ceramic plate provided on the anode, it is impossible to scrape down the electrodeposits with a dense structure. Therefore, after a certain period of time, the electrolytic refining operation is stopped, and the current is applied in the reverse direction. After stripping the electrodeposit by reverse electrodeposition for returning the deposit to the anode, the cathode surface is cleaned, and then the operation of each electrodeposition step is performed again from the beginning.
However, such a reverse electrodeposition operation consumes a large amount of electric power, and the electrodeposition performance is very inefficient. Further, there is a problem that the apparatus becomes complicated. In addition, in order to recover the electrodeposit from the collector provided at the lower part of the anode basket, the electrolytic reaction process must be interrupted and the entire electrode module must be lifted.
In addition, since the recovery tank for the metal uranium electrodeposit is located at the lower part of the anode basket, there is a limit to obtaining a high-purity uranium electrodeposit by unavoidably mixing undissolved transition element particles generated from the anode into the uranium. There's a problem.

Japanese Patent Application Publication No. 10-332880 (1998. 12.18) also discloses a mechanical scraping method in which a metal nuclear fuel component is dissolved in cadmium at 500 ° C. and electrodeposited onto an iron-based cathode. Disclosed a refining apparatus that recovers uranium electrodeposits by a process and then transfers the collected uranium electrodeposits to a separate uranium-salt separation tank to separate the salts contained in the electrodeposits. Yes.
Therefore, the refining apparatus can perform a continuous operation without interrupting the electrolytic reaction process in order to recover the uranium electrodeposit, and can increase the processing speed.

However, since this refining apparatus also uses an iron-based cathode, there is a problem that a mechanical scraping process is required.
In addition, a pump will be used to transfer the electrodeposit, but since the electrodeposit is simultaneously transferred in a state where a large amount of salt and cadmium are mixed, in order to recover the metal uranium electrodeposit from this mixture There is a problem that an additional distillation step is required.

  On the other hand, Japanese Patent Application Laid-Open No. 10-53889 uses a drum-type cathode partly immersed in molten salt for easy recovery of uranium electrodeposited on the cathode, and rotates this. A refining apparatus is disclosed in which uranium electrodeposits are separated by a scraper, and argon gas is sprayed onto the uranium surface deposited on the surface of the cathode drum to remove residual salt.

  However, since this refining apparatus also requires continuous supply of argon and also requires a mechanical scraping process, it does not fundamentally solve the problems of conventional apparatuses.

US Pat. No. 5,650,053 Japanese Patent Application Publication No. 10-332880 Japanese Patent Application Publication No. 10-53889

  The object of the present invention to solve the above problems is to continuously collect high-purity uranium deposits and transition metals generated during the electrolysis process without the need for a scraping process and without interrupting the electrolysis process. It is to provide a continuous electrolytic refining apparatus for metal uranium that can be used.

  In order to achieve the above technical problem, a continuous electrolytic refining apparatus for metal uranium according to the present invention comprises a cathode part fixed to a lower part of a heat sink and mounted with a number of graphite cathodes, and facing the cathode part. Then, an anode part for receiving spent nuclear fuel fixed to the lower part of the heat sink so as to be rotatable while surrounding the periphery thereof, the cathode part and the anode part are received, and the cathode part and the anode part are An electrolytic cell filled with an electrolyte so that it can be immersed, and a metal uranium that is detached after being electrodeposited on the multiple graphite cathodes is collected in the lower part of the cathode part inside the electrolytic cell, and the electrolysis A metal uranium recovery unit that is led out to the outside of the tank, and a transition metal recovery unit that is connected to the lower part of the electrolytic cell and derives sludge of the transition metal that is led out from the anode part and precipitated and collected in the lower part of the electrolytic cell. Including.

The cathode part further includes a screw type stirrer disposed on a central axis of the large number of graphite cathodes.
The anode part is a cylindrical basket that is formed in a cylindrical shape surrounding the cathode part and receives spent nuclear fuel between an outer peripheral plate and an inner peripheral plate.

A plurality of discharge holes are formed in the outer peripheral plate and the inner peripheral plate of the cylindrical basket, and the discharge holes extend along the longitudinal direction of the cylindrical basket and are arranged in parallel at regular intervals along the circumference. Is done.
The discharge hole is inclined with respect to a circular center line (L) of the horizontal cross section of the cylindrical basket, and the inclination angle of the cylindrical basket is 45 degrees with respect to the circular center line (L). It is preferable to form so that it may have.

The inner peripheral plate of the cylindrical basket is preferably formed in a filter shape and has a mesh in the range of 100 to 325 mesh.
The cylindrical basket is formed by a combination of a plurality of arcuate baskets that are individually separated along the circumference of the anode frame.

The uranium recovery unit is connected to the recovery tank through the uranium recovery tank disposed under the cathode part inside the electrolytic cell, and the lower part of the electrolytic cell, and collected in the recovery tank. A first flexible screw conveyor for deriving metallic uranium is included.
A cadmium pool having a preset level is formed in the transfer tank and the transfer pipe of the first flexible screw conveyor.
In addition, a first level sensor for sensing and measuring the level of the cadmium pool is installed inside the transfer pipe of the first flexible screw conveyor.
The transition metal recovery unit includes a second flexible screw conveyor that is connected to a lower portion of the electrolytic cell and guides the collected transition metal.
A cadmium pool having a preset level is formed inside the transfer pipe of the electrolytic cell and the second flexible screw conveyor.
In addition, a second level sensor for detecting and measuring the level of the cadmium pool is installed inside the transfer pipe of the second flexible screw conveyor.

The present invention provides an electrolytic refining apparatus capable of continuously recovering metal uranium without using a conventional mechanical scraping process in an electrolytic refining process by using a graphite cathode and a rotating cylindrical anode. To do.
Further, according to the electric field refining apparatus of the present invention, each flexible screw conveyor separates and collects a metal uranium electrodeposit that is desorbed from the graphite cathode by its own weight and a cylindrical anode that is rotatably mounted. Can be continuously recovered.
Furthermore, by removing the residual molten salt present in the uranium electrodeposit by using the cadmium pool, it is possible to prevent the contamination of the ultra-uranium element and to collect high-purity uranium.

Hereinafter, a continuous uranium metal electrolysis apparatus of the present invention will be described in detail with reference to the accompanying drawings. However, since various modifications can be made within the scope described in the claims of the present invention, the technical scope of the present invention is not limited to this embodiment.
1 is a schematic cross-sectional view illustrating a continuous electrolytic refining apparatus for metal uranium according to one embodiment of the present invention, and FIG. 2 is a partially cut perspective view illustrating FIG. 1 in three dimensions.
First, a description will be given with reference to FIGS. The continuous metal uranium electrolytic refining apparatus of the present embodiment receives a cathode part (20) fixed to the lower part of the heat radiating plate (10) and the spent nuclear fuel (35) and surrounds the periphery of the cathode part (20). The anode part (30) fixed to the lower part of the heat sink (10) so as to rotate while receiving the cathode part (20) and the anode part (30), and receiving the cathode part (20) and the anode part (30). ) And an electrolytic cell (40) filled with an electrolyte so that the metal uranium can be immersed in the lower part of the cathode (20), and then the metal uranium that is detached is collected to the outside of the electrolytic cell (40). And a transition metal recovery part (60) for extracting sludge-like transition metal collected in the lower part of the electrolytic cell (40).

FIG. 3 is a perspective view showing the cathode part (20) of FIG. 2 separated and enlarged in detail.
The cathode part (20) is connected / coupled to a lower part of the fixed plate (21) and a disk-shaped fixed plate (21) separated and fixed to the lower part of the heat radiating plate (10) by a connecting member (24). A plurality of rod-shaped graphite cathodes (22) and a screw type agitator (23) which is positioned at the center of the graphite cathode (22) and is fixed so as to rotate around the center of the fixed plate (21). The
Each of the graphite cathodes (22) is made of an electrolyte so that the metal uranium electrodeposited on the cathode group side by an electrolytic reaction of uranium from the molten salt in which the spent nuclear fuel is melted is easily removed by its own weight.
Further, the graphite cathode (22) is arranged at equal intervals along the circumferential edge of the fixed plate (21) so as to increase the facing area with the anode part (30) formed surrounding the periphery thereof. It is preferable.
The screw type stirrer (23) is a screw type formed so as to stir the molten salt inside the electrolytic cell (40) by driving a first motor (26) mounted on the upper side of the radiator plate (10). Yes, the shaft is rotated at the center of the graphite cathode (22), and the molten salt filled in the electrolytic cell (40) is stirred up while flowing upward and flowing.
At this time, the screw-type stirrer (23) is preferably configured in conjunction with an anode part (30) described later so that turbulent flow does not occur when the molten salt is stirred.

FIG. 4 is an exploded perspective view showing the anode part (30) of FIG. 2 separately.
The anode part (30) includes an anode frame (31) fixed so as to be rotatable at a lower portion of the heat radiating plate (10), and a cylindrical basket (32) fixed to the anode frame (31). .
The anode frame (31) is disposed at a lower portion of the heat radiating plate (10) so as to rotate around the cathode portion (20) by driving a second motor (36) disposed above the heat radiating plate (10). Fixed.
The cylindrical basket (32) has a cylindrical shape surrounding the cathode portion (20) and facing the graphite cathode (22).
In addition, the cylindrical basket (32) has an outer peripheral plate (separated and arranged at a certain interval so that a receiving space for receiving the spent nuclear fuel (35) is formed therein. 32a) and an inner peripheral plate (32b).
Furthermore, the cylindrical basket (32) is preferably formed by being divided into a plurality of arcuate baskets (33) arranged along the circumferential direction of the anode frame (31). Therefore, the cylindrical basket (32) in the present embodiment is exemplified by a combination of quadrant arcuate baskets (33) (see FIGS. 3 and 4).
Therefore, each arcuate basket (33) can be easily replaced by engaging the anode frame (31) with the anode frame (31) without a separate fastening member.
That is, as described above, among each of the quadrant arc baskets (33), only the arc basket (33) in which the received spent nuclear fuel (35) is completely dissolved by the electrolyte is individually provided. Can be exchanged. Therefore, the electrolytic refining process can be carried out continuously without drawing the entire anode part (30) outside the electrolytic cell.
In the following description, the cylindrical basket (32) is commonly referred to as including a plurality of arcuate baskets (33) constituting the cylindrical basket (32).
The cylindrical basket (32) is formed with a plurality of discharge holes (32c) that are long in the longitudinal direction of the outer peripheral plate (32a) and the inner peripheral plate (32b) and are arranged in parallel in the circumferential direction. .

FIG. 5 is a partial cross-sectional view of the shape of the discharge hole (32c) provided in the cylindrical basket (32) of FIG. 4 as viewed from above.
The discharge holes (32c) are formed in the outer peripheral plate (32a) and the inner peripheral plate (32b) of the cylindrical basket (32) at the same interval. The discharge hole (32c) is formed so that the molten salt flows from the inside to the outside of the anode part (30) when the anode part (30) rotates.
For this purpose, the discharge hole (32c) is formed so as to be inclined with respect to the cross-sectional center line (L) of each cylindrical basket (32) (the chain line in FIG. 5). In the present embodiment, as shown in FIG. 5, an inclination angle of 45 degrees is formed with reference to the center line (L) of the cylindrical basket (32). That is, the flow path of the molten salt is formed with an inclination angle in the direction opposite to the rotation direction of the anode part (30).
Therefore, in the electrolytic reaction process of the spent nuclear fuel, the sludge containing the transition metal having a predetermined size or less remaining in the cylindrical basket (32) that is not yet dissolved by the electrolyte is caused by the outer peripheral plate ( It is discharged through the discharge hole (32c) of 32a).
Here, the inner peripheral plate (32b) of the cylindrical basket (32) is configured by a filter having a predetermined mesh or less in order to prevent the transition metal sludge from flowing back into the anode part (30). At this time, the inner peripheral plate (32b) is preferably formed of a stainless steel mesh of about 100 to 325 mesh.

6 is a partially cut perspective view showing the flow of the molten / fluid substance in the continuous uranium metal electrolytic smelting apparatus of FIG.
The molten salt inside the electrolytic cell (40) of FIG. 6 is stirred while flowing in a state where no turbulent flow is generated by the anode part (30) and the screw-type stirrer (23) interlocked therewith.
The anode part (30) makes the spent nuclear fuel (35) received in the cylindrical basket (32) easier by allowing the molten salt on the cathode part (20) side inside to flow outside while rotating. And the sludge containing the transition metal remaining in an undissolved state is discharged to the outside through the discharge hole (32c).
At this time, the discharged transition metal sludge is precipitated and collected in the lower part of the electrolytic cell (40) due to the specific gravity difference from the molten salt.
The screw-type stirrer (23) rotates a screw at the lower part of the graphite cathode (22), and flows the molten salt flowing toward the upper part, so that a large amount of metal uranium dissolved in the molten salt is more easily produced. It functions to be electrodeposited on the graphite cathode (22).

FIG. 7 is a partially cut perspective view illustrating the level of a cadmium pool in the continuous electrolytic refining apparatus for metal uranium of FIG.
The metal uranium recovery part (50) in FIG. 7 includes a recovery tank (51) disposed in the lower part of the cathode part (20), and an electrolytic tank (40) for collecting the metal uranium collected in the lower part of the recovery tank (51). A first flexible screw conveyor (52) leading out to the outside.

The collection tank (51) is formed in a funnel shape below the cathode part (20). In this collection tank (51), metal uranium electrodeposits that are electrodeposited on the graphite cathode (22) and then desorbed by their own weight are collected.
The first flexible screw conveyor (52) continuously draws the metal uranium electrodeposits collected in the lower part of the recovery tank (51) by the operation of the screw conveyor.

7 includes a second flexible screw conveyor (61) connected to the lowermost part of the electrolytic cell (40). The second flexible screw conveyor (61) continuously draws out the transition metal sludge precipitated and collected in the lower part of the electrolytic cell (40) by the operation of the screw conveyor.
Furthermore, the second flexible screw conveyor (61) can be used not only for recovering the transition metal sludge but also as a transfer means for exchanging the molten salt.

However, the metal uranium electrodeposit and the transition metal sludge derived by the first flexible screw conveyor (52) and the second flexible screw conveyor (61) contain about 20% to 30% residual molten salt. ing.
In this residual molten salt, uranium trichloride and transuranium chloride are mixed, but superuranium chloride generally has a lower vapor pressure than uranium trichloride.
Therefore, in the distillation stage of the residual molten salt, the concentration of super uranium chloride is higher than that of uranium trichloride, so that it reacts with the metal uranium electrodeposit at high temperature to form a super uranium metal phase and recover the recovered uranium. Increases the radioactive level. This has been pointed out as a major problem when intermediate storage of uranium or low-level waste.

For this reason, a level H1 cadmium pool (54) set to a predetermined level is formed inside the recovery tank (51) of the metal uranium recovery part (50) and the transfer pipe of the first flexible screw conveyor (52). To do.
Cadmium forming the cadmium pool (54) has a density of 7 g / cm ³ at a lower than 19 g / cm ³ uranium, solubility in the liquid cadmium uranium metal is 2.3 wt% at 500 ° C.. Therefore, the metal uranium electrodeposit desorbed from the graphite cathode (22) is deposited at the bottom of the cadmium pool (54). Further, the density of LiCl-KCl eutectic salt at 500 ° C., was 1.6 g / cm ^3, even if the salt containing 9wt% UCl3, a ~1.9g / cm ³ about the liquid cadmium Very low compared. In addition, since the solubility of the molten salt in liquid cadmium is very low, the molten salt contained in the metal uranium electrodeposit will float on top of the liquid cadmium. In this way, the metal uranium electrodeposit and the molten salt are separated inside the cadmium pool (54).

Further, a small amount of cadmium is mixed in the metal uranium electrodeposit led out of the electrolytic cell (40) by the first flexible screw conveyor (52).
However, since this cadmium has a lower boiling point than the molten salt, it can be easily removed from the salt in the distillation process, and most of the ultra-uranium salt is derived from the metal uranium electrodeposit by the first flexible screw conveyor. It is removed with molten salt in stages.
Therefore, after the step of removing cadmium, a highly pure metal uranium electrodeposit is obtained.

In addition, a first level sensor (53) capable of detecting and measuring the level of the cadmium pool (54) is installed inside the first flexible screw conveyor (52) transfer pipe.
This first level sensor (53) detects and measures the level of the cadmium pool (54) using the difference in spatial conductivity between the molten salt and cadmium, thereby continuously recovering metal uranium electrodeposits. If cadmium loss occurs, an appropriate amount can be replenished as needed.
Cadmium can be separated from the metal uranium electrodeposit and reused in the distillation step.

In addition, a cadmium pool (63) is also formed inside the transfer pipe of the second flexible screw conveyor (61) of the transition metal recovery section (60) and below the electrolytic cell (40), and the second flexible A second level sensor (62) for detecting and measuring the level H2 of the cadmium pool (63) is installed inside the transfer pipe of the screw conveyor (61).
Therefore, even in the case of transition metal sludge, since its density is higher than that of liquid cadmium, the transition metal precipitates in the lower part of the electrolytic cell (40) and is purified through a process based on the same principle as that of the aforementioned metal uranium electrolyte. Transition metal can be obtained.

1 is a schematic cross-sectional view illustrating a continuous electrolytic refining apparatus for metal uranium according to an embodiment of the present invention. FIG. 2 is a partially cut perspective view illustrating FIG. 1 in three dimensions. FIG. 3 is a perspective view showing the cathode part of FIG. 2 separated and enlarged in detail. FIG. 3 is an exploded perspective view showing the anode part of FIG. 2 separately. FIG. 5 is a partial cross-sectional view illustrating the shape of the discharge hole of the cylindrical basket of FIG. 4, the rotation direction of the anode portion, and the flow path of the molten salt. FIG. 2 is a partially cut perspective view showing a moving path of a molten material in the continuous electrolytic refining apparatus for metal uranium of FIG. FIG. 2 is a partially cut perspective view illustrating the level of a cadmium pool in the continuous electrolytic refining apparatus for metal uranium of FIG. 1.

Explanation of symbols

DESCRIPTION OF SYMBOLS 10 ... Radiating plate 20 ... Cathode part 21 ... Fixed plate 22 ... (Many) Graphite cathode 23 ... Screw type stirrer 24 ... Connecting member 30 ... Anode part 31 ... -Anode frame 32-cylindrical basket 33-arc-shaped baskets 35-spent nuclear fuel 40-electrolytic cell 50-metal uranium recovery part 51-metal uranium recovery tank 52- .... First flexible screw conveyor 53 ... first level sensor 54 ... cadmium pool 60 ... transition metal recovery part 61 ... second flexible screw conveyor 62 ... second level sensor 63 ... Cadmium pool

Claims (14)

A cathode part (20) fixed to the lower part of the heat sink (10) and fitted with a number of graphite cathodes (22);
An anode part (30) for receiving spent nuclear fuel that is rotatably fixed to the lower part of the heat radiating plate (10) while facing the cathode part (20) and surrounding the periphery thereof;
An electrolytic cell (40) filled with an electrolyte so as to receive the cathode part (20) and the anode part (30) and soak the cathode part (20) and the anode part (30); ,
At the lower part of the cathode part (20) inside the electrolytic cell (40), the metal uranium that is detached after being electrodeposited on the numerous graphite cathodes (22) is collected, and the outside of the electrolytic cell (40) is collected. A metal uranium recovery section (50) leading to
A transition metal recovery unit (60) connected to the lower part of the electrolytic cell (40) and derived from the anode part (30) and derived from the transition metal sludge precipitated and collected in the lower part of the electrolytic cell (40). A continuous electrolytic refining apparatus for metal uranium, characterized by comprising:   2. The continuous electrolytic refining apparatus for metal uranium according to claim 1, wherein the cathode part further includes a screw-type stirrer disposed on a central axis of the plurality of graphite cathodes. .   The anode portion (30) is formed in a cylindrical shape surrounding the periphery of the cathode portion (20), and a cylindrical basket (32) for receiving spent nuclear fuel (35) between the outer peripheral plate and the inner peripheral plate. The continuous electrolytic refining apparatus for metal uranium according to claim 1, wherein A plurality of discharge holes are formed in the outer peripheral plate and the inner peripheral plate of the cylindrical basket (32),
4. The continuous metal uranium according to claim 3, wherein the discharge holes extend along the longitudinal direction of the cylindrical basket (32) and are arranged in parallel at regular intervals along the circumference. Type electrolytic refining equipment.   5. The continuous electrolytic refining apparatus for metal uranium according to claim 4, wherein the discharge hole is inclined with respect to a circular center line (L) of a horizontal section of the cylindrical basket (32). .   6. The continuous metal uranium according to claim 5, wherein the discharge hole is formed to have an inclination angle of 45 degrees with a circular center line (L) of a horizontal section of the cylindrical basket (32). Type electrolytic refining equipment.   The continuous electrolytic refining apparatus for metal uranium according to claim 3, wherein the inner peripheral plate of the cylindrical basket (32) is in the form of a filter having a mesh of 100 to 325 mesh.   4. The metal uranium according to claim 3, wherein the cylindrical basket (32) is a combination of a plurality of arc-shaped baskets (33) separated individually along the circumference of the anode frame (31). Continuous electrolytic refining equipment. A metal uranium recovery tank (51), wherein the metal uranium recovery section (50) is disposed below the cathode section (20) inside the electrolytic cell (40);
Including a first flexible screw conveyor (52) which penetrates the lower part of the electrolytic cell (40) and is connected to the recovery tank (51) and leads out metal uranium collected in the recovery tank (51). The continuous electrolytic refining apparatus for metal uranium according to claim 1, wherein the apparatus is a continuous electrolytic refining apparatus.   The metal according to claim 9, wherein a cadmium pool having a preset level is formed inside the transfer pipe of the metal uranium recovery tank (51) and the first flexible screw conveyor (52). Uranium continuous electrolytic refining equipment.   The first level sensor (53) for detecting and measuring the level of the cadmium pool is further installed in the transfer pipe of the first flexible screw conveyor (52). The continuous electrolytic refining apparatus for metal uranium as described.   The transition metal recovery part (60) includes a second flexible screw conveyor (61) connected to a lower part of the electrolytic cell (40) and leading out the precipitated and collected transition metal. Item 2. A continuous electrolytic refining apparatus for metal uranium according to item 1.   The metal uranium according to claim 12, wherein a cadmium pool having a preset level is formed in the electrolytic cell (40) and a transfer pipe of the second flexible screw conveyor (61). Continuous electrolytic refining equipment.   The second level sensor (62) for detecting and measuring the level of the cadmium pool is further installed inside the transfer pipe of the second flexible screw conveyor (61). The continuous electrolytic refining apparatus for metal uranium as described.

Images