KR20150051928A - Method of processing composite wastes - Google Patents

Abstract

The present invention provides a method of processing composite waste to separate remaining waste and collect uranium from a uranium electrolytic refining positive electrode basket for a pyro process. The method of processing composite waste provided in the present invention is to use a chemical and electrochemical treatment of molten salt at high temperatures, therefore metal uranium can be collected by immersing composite waste contained in a positive electrode basket together with a reference electrode and a negative electrode into a crucible, and applying preset voltage or electric current.

Description

METHOD OF PROCESSING COMPOSITE WASTES [0002]

The present invention relates to a method of treating composite waste in a cathode basket resulting from uranium electrolytic refining of a pyrogenic process, and more particularly to a pyrogenic process for dry reprocessing of spent nuclear fuel or spent nuclear fuel The present invention relates to a process for treating an anode basket residual waste resulting from electrolytic refining for recovering uranium.

Pyroprocess is a non-nucleated, diffusible spent fuel treatment technology that can reduce the amount of high-level waste by extracting and recycling uranium from spent nuclear fuel and discharging actinide elements such as plutonium.

The pyrofloor process consists of a preprocessing step and a post-processing step.

In the pretreatment step, the spent nuclear fuel assemblies are disassembled and the cladding tubes are withdrawn from the reactor, cut off, and fabricated to process the spent nuclear fuel materials. In the subsequent post treatment step, uranium is recovered through electrolytic reduction, electrolytic refining and electrolytic smelting of the spent nuclear fuel material, and the ultra uranium compound is separated.

In particular, during the electrolytic refining process for recovering metal uranium in the post-treatment step, the anode basket contains uranium oxide (U ₃ O ₈ ) and zirconium oxide (ZrO ₂ ) which are not reduced in the electrolytic reduction and metal uranium and zirconium , It is not easy to treat and solidify waste, and there is a problem that loss of uranium that can be reused as fuel is inevitable.

Therefore, a method for solving this problem and recovering uranium that can be reused as fuel can be considered.

It is an object of the present invention to provide a composite waste treatment method capable of recovering uranium from the composite waste remaining in the anode basket after electrolytic refining and improving the uranium recovery rate in the pyrogenic process and securing the safety of solidification and reduction of waste that can not be recycled .

It is another object of the present invention to provide a method for separating and recycling spent uranium effectively from electrolytic refining anode wastes by chemical and electrochemical methods in a high temperature molten salt and treating various kinds of noble metals including oxides, And to provide a composite waste treatment method.

According to an aspect of the present invention, there is provided a method of treating a composite waste according to an embodiment of the present invention, the method comprising: (a1) preparing a composite waste containing at least a part of uranium oxide, zirconium oxide, metal zirconium, (A2) introducing a primary cathode into the molten salt and applying a voltage or an electric current to uranium chloride dissolved in the molten salt to form uranium chloride from the uranium chloride dissolved in the molten salt; (A3) removing salts contained in zirconium oxide and noble metal in the anode basket, and recovering the residue.

According to one example of the present invention, a method for treating a composite waste comprises the steps of: (a2) between (a2) and (a3), (a2 ') an initiator for immersing a secondary cathode in the molten salt and promoting an oxidation- Further comprising the step of selectively adding zirconium tetrachloride to recover metal zirconium from the anode basket.

(B1) a composite waste containing at least a part of uranium oxide, zirconium oxide, metal zirconium and noble metal, and containing the composite waste contained in the anode basket, in a molten salt containing zirconium tetrachloride (B2) reacting the zirconium tetrachloride or the further added zirconium tetrachloride with the uranium oxide to induce the formation of uranium chloride, (b3) (B4) removing salts contained in the zirconium oxide and the noble metal in the anode basket, and removing the residues from the noble metal in the anode basket; And collecting the collected data.

In another aspect of the present invention, there is provided a method of treating a composite waste, comprising the steps of: (c1) preparing a composite waste containing at least a portion of uranium oxide, zirconium oxide, metal zirconium, and noble metal, (C2) immersing the basket in a second molten salt containing zirconium tetrachloride so as to use the basket containing the reduced metal as an anode, together with a primary cathode; dipping the first molten salt in the first molten salt together with the anode and reducing the oxide to a metal (C3) replacing the primary cathode with a secondary cathode and applying a voltage or an electric current to recover uranium; and (c4) recovering uranium by applying a voltage or current to the noble metal contained in the noble metal in the basket Removing the salt and recovering the residue.

(D1) reacting a composite waste containing at least a part of uranium oxide, zirconium oxide, metal zirconium and noble metal with a gas containing chlorine in the reactor to produce a composite waste (D2) recovering the noble metal by accommodating zirconium tetrachloride as a recovered product, uranium oxide as a residue, zirconium oxide and noble metal in a cathode basket, immersing the recovered product in a molten salt together with a primary cathode, applying a voltage or an electric current, (d3) replacing the primary cathode with a secondary cathode and applying voltage or current to recover metallic zirconium, (d4) replacing the secondary cathode with a tertiary cathode, and applying a voltage or current to recover uranium And (d4) removing the residual salt contained in the anode basket and recovering zirconium oxide.

According to another embodiment of the present invention, the concentration of the initiator is 0.1 to 40 parts by weight based on 100 parts by weight of the molten salt.

According to another embodiment of the present invention, when the zirconium is reduced, a voltage of -1.8 to -0.1 V or a current of -0.01 to -20 A / cm 2 is applied to the Ag / Ag ⁺ reference electrode.

According to another embodiment of the present invention, when the uranium is reduced, a voltage of -2.2 to -0.4 V or a current of -0.01 to -20 A / cm 2 is applied to Ag / Ag ⁺ reference electrode.

According to another embodiment of the present invention, the molten salt includes at least one selected from the group consisting of LiCl, LiCl-KCl, NaCl, and NaCl-KCl.

According to another example related to the present invention, the initiator comprises at least one selected from the group consisting of _{ZrCl 4, ZrF 4, K 2} ZrF6, Li 2 O.

According to another embodiment of the present invention, the temperature of the molten salt is 400 to 900 占 폚.

According to another embodiment of the present invention, the molten salt includes an additive for improving the microstructure of the metal zirconium, and the additive includes at least one selected from the group consisting of LiF, ZnF ₂ , AlF ₃ and CaF ₂ do.

According to another embodiment of the present invention, the step of removing the salt and recovering the residue comprises a distillation step for removing residual salts, wherein the distillation step is carried out at a temperature of 500 to 1200 ° C and a pressure of atmospheric pressure Air or an inert gas atmosphere.

According to another embodiment of the present invention, the chlorine-containing gas is diluted with argon (Ar) at a concentration of 10 to 80% of chlorine gas.

The flow rate of the mixed chlorine gas may be 5 to 300 ccm.

According to another embodiment of the present invention, the composite waste treatment method further includes an oxidation step of preventing the rapid reaction due to contact with air during treatment of the metal zirconium and the noble metal.

According to another embodiment of the present invention, the composite waste treatment method further comprises removing (d0) the salt before the step (d1).

According to another example of the present invention, a voltage of -1.5 to +0.1 V or a current of -0.01 to -20 A / cm ² is applied to the Ag / Ag ⁺ reference electrode during the recovery of the noble metal.

According to the present invention, uranium can be separated from the composite waste by chemical and electrochemical methods using zirconium tetrachloride by immersing the composite waste containing uranium oxide, zirconium and noble metal in a molten salt, The uranium recovery rate of the process can be increased, the recovered uranium can be recycled, and the amount of waste that can not be recycled can be reduced.

Further, the present invention can separate uranium and treat wastes in accordance with the nature of the composite waste, so that it is possible to provide a base for efficiently manufacturing a solid body.

In addition, the present invention can minimize the number of devices required for complex waste treatment and can recycle metals such as uranium and zirconium by performing the process by replacing electrodes in a stepwise manner in one reactor.

1 and 2 are flow charts and conceptual diagrams of a composite waste treatment method according to an embodiment of the present invention, respectively.
3 and 4 are flow charts and conceptual diagrams of a composite waste treatment method according to another embodiment of the present invention, respectively.
5 and 6 are flow charts and conceptual diagrams of a composite waste treatment method according to another embodiment of the present invention, respectively.
7 and 8 are flow charts and conceptual diagrams of a composite waste treatment method according to another embodiment of the present invention, respectively.

Hereinafter, the composite waste treatment method according to the present invention will be described in detail with reference to the drawings. In the present specification, the same or similar reference numerals are given to different embodiments in the same or similar configurations. As used herein, the singular forms "a", "an" and "the" include plural referents unless the context clearly dictates otherwise.

First, Table 1 below shows the reversibility of the chemical reaction with zirconium tetrachloride for various nuclides at 500 DEG C using HSC codes. The element mark U represents uranium, TRU represents uranium, and NM represents noble metal.

In Table 1, deltaG indicates a stabilizing reaction when the value is smaller than 0, and a spontaneous reaction occurs when the rate constant K is larger than 0. [ According to Table 1, uranium oxide contained in the composite waste can be thermodynamically converted to uranium chloride by zirconium tetrachloride, and uranium chloride dissolved in the molten salt can be electrochemically reduced to be separated and recovered into the cathode Can be confirmed.

1 and 2 are flow charts and conceptual diagrams of a composite waste treatment method according to an embodiment of the present invention, respectively.

The composite waste treatment method includes a step (S110) of producing uranium chloride, a step (S120) of recovering metal uranium, and a step (S130) of removing the salt and recovering the residue.

First, the step of producing uranium chloride (S110) immerses the composite waste in the molten salt. Composite wastes include uranium oxide, zirconium oxide, metal zirconium and precious metals. The molten salt includes at least one selected from the group consisting of LiCl, LiCl-KCl, NaCl, and NaCl-KCl. In the example shown in FIG. 1B, zirconium tetrachloride is included in the LiCl-KCl molten salt (500 DEG C) to promote uranium chloride production.

The molten salt may include an additive for improving the microstructure upon recovery of zirconium, and the additive may include at least one selected from the group consisting of LiF, ZnF ₂ , AlF ₃ and CaF ₂ .

The composite waste separation apparatus remaining in the anode basket after uranium electrolytic refining of the spent fuel includes a crucible, a basket, a reference electrode and a cathode electrode, and a power supply. The basket may be made of a mesh or a porous metal film or ceramic, and the material of the basket may be higher in reducing potential than zirconium and uranium. The composite waste is immersed in a crucible containing a molten salt while being accommodated in a cathode basket.

When the composite waste is immersed in a molten salt and reacted for a predetermined time, uranium oxide is converted to uranium chloride by chemical conversion (U _x O _y -> UCl ₃ or UCl ₄ ). A process of agitating the composite waste contained in the basket to actively chemically react with zirconium tetrachloride in the molten salt can be added. Uranium chloride is dissolved in the molten salt.

Next, the primary cathode is inserted into the molten salt and a voltage or current is applied to recover metal uranium from uranium chloride (S120).

The reference electrode and the cathode electrode are immersed in the molten salt, and the cathode electrode can recover uranium, zirconium or noble metal according to the electrochemical redox reaction. In the step of recovering metal uranium (S120), the primary cathode is inserted into the molten salt and a voltage of -2.2 to -0.4 V versus Ag / Ag ⁺ reference electrode or a current of -0.01 to -20 A / cm 2 The uranium chloride dissolved in the molten salt precipitates on the primary cathode and the uranium metal can be recovered therefrom.

Finally, in step S130 of recovering the residue, the zirconium oxide in the basket and the salt contained in the noble metal are removed. The conditions of the distillation step for removing residual salts for solidification of the final waste can be performed in air, vacuum or inert gas atmosphere at a temperature of 500 to 1200 ° C and a pressure lower than atmospheric pressure. After removing the salt, the residue can be recovered. The recovered residues may be solidified using a metal, glass, ceramic or mixed solidification medium.

The composite waste treatment method may further include recovering metal zirconium between the step of recovering metal uranium (S120) and the step of collecting the residue (S125).

A secondary cathode is immersed in the molten salt and optionally zirconium tetrachloride is added as an initiator to promote the redox reaction, if necessary. When a voltage of -1.8 to -0.1 V or a current of -0.01 to -20 A / cm 2 is applied to the Ag / AgCl reference electrode using a power supply, metal zirconium can be further recovered and separated from the oxide.

Materials that can be used as an initiator may include _{ZrCl 4, ZrF 4, K 2} ZrF 6, Li 2 O.

3 and 4 are flow charts and conceptual diagrams of a composite waste treatment method according to another embodiment of the present invention, respectively.

The composite waste treatment method includes a step S210 of recovering metal zirconium, a step S220 of producing uranium chloride, a step S230 of recovering metal uranium, and a step S240 of removing the salt and recovering the residue do.

The step S210 of recovering metal zirconium is performed by immersing the composite waste contained in the anode basket together with the primary cathode in a molten salt containing zirconium tetrachloride, and applying a voltage or an electric current using a power supply.

Composite wastes may comprise uranium oxide, zirconium oxide, metal zirconium, and noble metals, as in the embodiments illustrated in FIGS. 1A and 1B, and the molten salt (500 ° C.) may include LiCl-KCl. Zirconium tetrachloride may be added to the molten salt to accelerate oxidation and reduction reactions.

When a voltage or current is applied using a power supply, zirconium precipitates on the primary cathode, and metal zirconium can be recovered from the zirconium.

Next, uranium chloride is produced using a chemical reaction (S220).

When zirconium tetrachloride and uranium oxide are reacted for a predetermined time after metal zirconium is recovered, uranium chloride is produced.

Subsequently, metal uranium is recovered from uranium chloride (S230).

When a secondary cathode is immersed in a molten salt and a voltage or current is applied, uranium chloride produced in the molten salt can be recovered as metal uranium.

Finally, removing the salt and recovering the residue (S240) is a step of removing the salt contained in the zirconium oxide and the noble metal in the anode basket. The zirconium oxide remaining in the anode basket and the noble metal may be solidified together or the noble metal may be recovered and separated by immersing the tertiary cathode as necessary.

5 and 6 are flow charts and conceptual diagrams of a composite waste treatment method according to another embodiment of the present invention, respectively.

The composite waste treatment method includes the steps of reducing oxides to metals (S310), recovering metal zirconium (S320), recovering uranium (S330), and removing salts and recovering the residue (S340) do.

First, in step S310 of reducing an oxide to a metal, the composite waste is immersed in a lithium chloride first molten salt containing lithium oxide at 650 DEG C together with a positive electrode, and a potential is applied to reduce the oxide to a metal.

Subsequently, the basket containing the reduced metal is immersed in a second molten salt of 500 ° C LiCl-KCl containing zirconium tetrachloride together with the primary cathode, and metal zirconium is recovered by applying a voltage or an electric current at step S320.

Next, the primary cathode is replaced with a secondary cathode, uranium chloride is added as an initiator, and uranium is recovered by applying a voltage or current (S330).

Finally, the salt contained in the noble metal in the basket is removed, and the noble metal is separated to recover the residue (S340).

7 and 8 are flow charts and conceptual diagrams of a composite waste treatment method according to another embodiment of the present invention, respectively.

The complex waste treatment method includes a step S410 of producing a chloride, a step S420 of recovering a noble metal, a step S430 of recovering metal zirconium, a step S440 of recovering uranium, a step S440 of removing uranium, (S450).

First, in the step of generating chloride, the composite waste is put into a chlorination apparatus, and mixed chlorine gas is introduced at a proper temperature and reacted to chlorine uranium oxide, zirconium and noble metal in a gas phase (S410). The mixed chlorine gas is diluted with argon (Ar) at a chlorine gas concentration of 10 to 80%, and the flow rate of the mixed chlorine gas is preferably 5 to 300 ccm. And then volatilizing the salt remaining in the composite waste for an effective chlorination reaction.

Next, in the step of recovering the noble metal (S420), the recovered zirconium tetrachloride and the residues uranium oxide, zirconium oxide and noble metal are accommodated in the anode basket and then immersed in the LiCl-KCl molten salt together with the primary cathode. Then, a voltage or current is applied to recover the noble metal. A voltage of -1.5 to +0.1 V or a current of -0.01 to -20 A / cm ² can be applied to the Ag / Ag ⁺ reference electrode during the recovery of the noble metal.

Subsequently, the metal zirconium is recovered by replacing the primary cathode with a secondary cathode and applying a voltage or current (S430). The secondary cathode is replaced with a tertiary cathode, and uranium is recovered by applying a voltage or current S440). At this time, uranium oxide is recovered as uranium chloride by zirconium tetrachloride.

Finally, in step S450 of removing the salt and recovering the residue, the residual zirconium oxide is separated and solidified.

The composite waste treatment method described above is not limited to the configurations and the methods of the embodiments described above, but the embodiments may be configured by selectively combining all or some of the embodiments so that various modifications may be made .

Claims (12)

(a1) producing uranium chloride by chemical conversion by immersing a composite waste containing at least a part of uranium oxide, zirconium oxide, metal zirconium and noble metal in a positive electrode basket in a molten salt containing zirconium tetrachloride;
(a2) inserting a primary cathode into the molten salt and applying a voltage or current to recover metal uranium from the uranium chloride dissolved in the molten salt;
(a3) removing the salts contained in zirconium oxide and noble metal in the anode basket and recovering the residue. The method according to claim 1,
Between the step (a2) and the step (a3)
(a2 ') further comprising the step of selectively immersing the secondary anode in the molten salt and selectively adding zirconium tetrachloride as an initiator for promoting the oxidation and reduction reaction, thereby recovering the metal zirconium from the cathode basket. Processing method. (b1) a composite waste containing at least a part of uranium oxide, zirconium oxide, metal zirconium and noble metal, the composite waste contained in the anode basket is immersed in a molten salt containing zirconium tetrachloride together with a primary cathode, and a metal zirconium ;
(b2) reacting the zirconium tetrachloride or the further added zirconium tetrachloride with the uranium oxide to induce the formation of uranium chloride;
(b3) immersing the secondary cathode in the molten salt and applying a voltage or current to recover metal uranium from the uranium chloride; And
(b4) removing the salts contained in zirconium oxide and noble metal in the anode basket and recovering the residue. 4. The method according to any one of claims 1 to 3,
Using an initiator that promotes said oxidation and reduction reactions in at least one step associated with oxidation and reduction reactions,
Wherein the concentration of the initiator is 0.1 to 40 parts by weight based on 100 parts by weight of the molten salt. 4. The method according to any one of claims 2 to 3,
Wherein a voltage of -1.8 to -0.1 V or a current of -0.01 to -20 A / cm 2 is applied to the Ag / Ag ⁺ reference electrode during the reduction of zirconium. 4. The method according to any one of claims 1 to 3,
Wherein a voltage of -2.2 to -0.4 V or a current of -0.01 to -20 A / cm 2 is applied to the Ag / Ag ⁺ reference electrode during the reduction of uranium. 4. The method according to any one of claims 1 to 3,
Wherein the molten salt comprises at least one selected from the group consisting of LiCl, LiCl-KCl, NaCl, and NaCl-KCl. 4. The method according to any one of claims 1 to 3,
Using an initiator that promotes said oxidation and reduction reactions in at least one step associated with oxidation and reduction reactions,
The initiator is _{ZrCl 4, ZrF 4, K 2} ZrF 6, a composite waste treatment method characterized in that it comprises at least one selected from the group consisting of Li ₂ O. 4. The method according to any one of claims 1 to 3,
Wherein the temperature of the molten salt is between 400 and < RTI ID = 0.0 > 900 C. < / RTI > 4. The method according to any one of claims 1 to 3,
Wherein the molten salt contains an additive for improving the microstructure of the metal zirconium,
The additives include LiF, ZnF _2, AlF _3, complex waste treatment method characterized in that it comprises at least one selected from the group consisting of CaF _2. 4. The method according to any one of claims 1 to 3,
The step of removing the salt and recovering the residue comprises a distillation step to remove residual salts,
Wherein the distillation step is carried out at a temperature of 500 to 1200 DEG C and at a pressure lower than atmospheric pressure in an air or inert gas atmosphere. 4. The method according to any one of claims 1 to 3,
Further comprising the step of oxidizing the metal zirconium and the noble metal so as to prevent the occurrence of abrupt reaction due to contact with air during the treatment of the metal zirconium with the noble metal.

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