JP2006010424A - Uranium recovery facility and uranium recovery method - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide an uranium recovery facility and an uranium recovery method capable of reducing the waste quantity and recovering uranium suitably. <P>SOLUTION: This facility is equipped with an uranium adsorption tower 1 for adsorbing uranium from a halogenide including uranium. An adsorbent in the uranium adsorption tower 1 has a constitution capable of recovering uranium by incineration treatment and preventing generation of the waste. Thus, the waste quantity can be reduced by the incineration treatment of the adsorbent adsorbing uranium, and uranium can be recovered suitably. <P>COPYRIGHT: (C)2006,JPO&NCIPI

Description

  The present invention relates to a uranium recovery facility and a uranium recovery method for recovering uranium from a uranium-containing halide.

  In general, during the processing of nuclear fuel and the like, halides such as sodium fluoride (NaF) containing uranium are produced, and uranium-containing halides are variously collected by uranium recovery means in order to recover uranium. Processing is done.

  As an example of the uranium recovery means, a halide containing uranium is heated to 600 ° C. or more to form a molten salt, and the molten salt is electrolytically reduced to deposit uranium on the cathode side electrode. Some uranium is melted, and uranium and sodium fluoride are separated by specific gravity by cooling to recover uranium (see, for example, Patent Document 1).

As another example, there is one in which uranium hexafluoride (UF ₆ ) is adsorbed and recovered by an adsorbent of NaF (see, for example, Patent Document 2).
Japanese Patent Laid-Open No. 10-81989 Japanese Patent Laid-Open No. 11-304995

  However, when processing a halide containing uranium into a molten salt, the electrode to which uranium is attached becomes secondary waste and the molten salt itself (sodium fluoride) also becomes waste. There was a problem that the amount of waste increased. In addition, since the melting point of the molten salt needs to be 600 ° C. or higher, there are problems that the running cost is high and safety measures are excessive. Furthermore, it has been desired to reduce the amount of waste and to suitably recover uranium.

  The present invention has been made in view of the above circumstances, and an object of the present invention is to provide a uranium recovery facility and a uranium recovery method that reduce the amount of waste and suitably recover uranium.

  Claim 1 of the present invention comprises a uranium adsorption tower for adsorbing uranium from a uranium-containing halide, and the uranium adsorption tower adsorbent can recover uranium by incineration and prevent generation of waste. The present invention relates to a uranium recovery facility characterized by having a configuration to obtain.

  Claim 2 of the present invention comprises a dissolution tank for making a uranium-containing halide into an aqueous solution, and a uranium adsorption tower for adsorbing uranium from an aqueous solution of a uranium-containing halide, The present invention relates to a uranium recovery facility characterized by having a configuration capable of recovering uranium by incineration and preventing generation of waste.

  Claim 3 of the present invention comprises a desorption furnace for desorbing uranium from a uranium-containing halide, and a uranium adsorption tower for adsorbing uranium from a uranium-containing halide. The present invention relates to a uranium recovery facility characterized by having a configuration capable of recovering uranium by incineration and preventing generation of waste.

  According to a fourth aspect of the present invention, there is provided a desorption furnace for desorbing uranium from a uranium-containing halide, a dissolution tank for converting a uranium-containing halide into an aqueous solution, and uranium from an aqueous solution of a uranium-containing halide. A uranium adsorption tower, and the adsorbent of the uranium adsorption tower is a uranium recovery facility characterized in that it can recover uranium by incineration and prevent generation of waste. Is.

  Claim 5 of the present invention relates to the uranium recovery facility according to any one of claims 1 to 4, wherein the adsorbent of the uranium adsorption tower is an organic material capable of adsorbing uranium.

  Claim 6 of the present invention includes a precipitation tank for precipitating uranium from a uranium-containing halide, and when the concentration of uranium is high, the uranium-containing halide is sent to the precipitation tank so that the uranium concentration is low. In this case, the uranium recovery facility according to claim 2 or 4 is provided with a configuration for sending a halide containing uranium to a uranium adsorption tower.

  Claim 7 of the present invention is provided with a bypass line that avoids the desorption furnace, and when the concentration of uranium is high, a halide containing uranium is sent to the desorption furnace, and when the concentration of uranium is low, The uranium recovery facility according to claim 3 or 4, comprising a structure for sending a halide containing uranium to a bypass line.

  The eighth aspect of the present invention relates to the uranium recovery facility according to any one of the first to seventh aspects, which is configured to treat a halide solution after uranium adsorption.

  Claim 9 of the present invention is characterized in that uranium is adsorbed on an adsorbent from a halide containing uranium, and the adsorbent is incinerated to recover uranium and prevent generation of waste. , It is something that takes.

  According to claim 10 of the present invention, a halide containing uranium is made into an aqueous solution, uranium is adsorbed on the adsorbent from the aqueous solution of halide containing uranium, and the adsorbent is incinerated to recover uranium and to dispose of waste. The present invention relates to a uranium recovery method characterized by preventing generation.

  Claim 11 of the present invention recovers uranium by desorbing uranium from a uranium-containing halide in a desorption furnace, adsorbing uranium from the uranium-containing halide to an adsorbent, and incinerating the adsorbent. And a uranium recovery method characterized by preventing the generation of waste.

  According to claim 12 of the present invention, uranium is desorbed from a uranium-containing halide in a desorption furnace, the uranium-containing halide is made into an aqueous solution, and uranium is adsorbed to the adsorbent from the uranium-containing halide aqueous solution. And a method for recovering uranium by incinerating the adsorbent and preventing the generation of waste.

  According to the thirteenth aspect of the present invention, when the concentration of uranium is high, uranium is precipitated from a uranium-containing halide and then adsorbed on the adsorbent. When the concentration of uranium is low, the uranium-containing halogen is added. The uranium recovery method according to claim 10 or 12, wherein uranium is directly adsorbed on the adsorbent from the chemical.

  According to the fourteenth aspect of the present invention, when the concentration of uranium is high, uranium is desorbed from the uranium-containing halide by a desorption furnace. When the concentration of uranium is low, the uranium-containing halide is removed. The uranium recovery method according to claim 11 or 12, wherein the uranium recovery method is sent to the next treatment while avoiding the desorption furnace.

  A fifteenth aspect of the present invention relates to the uranium recovery method according to any one of the ninth to fourteenth aspects, wherein the halide solution after uranium adsorption is treated.

  Thus, according to the present invention, since the adsorbent that adsorbs uranium can prevent the generation of waste by incineration, it is possible to eliminate the need for an electrode for adhering uranium and reduce the amount of waste. it can. Moreover, since the adsorbent that adsorbs uranium can recover uranium by incineration, it can be recovered preferably without causing a loss in the amount of uranium recovered. Furthermore, since it is not necessary to convert the halide into a molten salt, a heating means for making the melting point 600 ° C. or higher is unnecessary, the running cost can be suppressed, and an excessive safety measure can be eliminated.

  When the halide containing uranium is made into an aqueous solution, the halide containing uranium is wet-dissolved and uranium is adsorbed appropriately to the adsorbent, so that contaminated radioactive secondary waste is decontaminated to the clearance level, The amount of waste can be further reduced. Further, since the halide containing uranium is wet-dissolved and uranium is appropriately adsorbed by the adsorbent, uranium can be recovered more suitably. Further, since the halide is wet-dissolved, there is no need to make it into a molten salt by heating, and it is possible to further reduce running costs and eliminate the need for excessive safety measures.

  When uranium is desorbed from a uranium-containing halide in a desorption furnace, the concentration of uranium contained in the halide is reduced, so contaminated radioactive secondary waste can be easily decontaminated to the clearance level, The amount of waste can be further reduced. Moreover, since the concentration of uranium contained in the halide is lowered, uranium can be easily and sufficiently adsorbed on the adsorbent, and uranium can be recovered more suitably.

  If the adsorbent of the uranium adsorption tower is made of an organic material capable of adsorbing uranium, the adsorbent can be suitably treated without incurring waste when incinerated, so that the amount of waste can be further reduced. it can. Further, uranium can be favorably recovered by adsorbing uranium to the adsorbent of the organic material.

  When the uranium concentration is high, the uranium-containing halide is sent to the precipitation tank, and when the uranium concentration is low, the uranium-containing halide is sent to the uranium adsorption tower. Is high, the concentration of uranium contained in the halide is lowered, so that contaminated radioactive secondary waste can be easily decontaminated to the clearance level, and the amount of waste can be further reduced. Moreover, since it can be selectively used depending on the concentration of uranium, the degree of freedom of equipment and method is high, and the amount of waste can be reduced appropriately.

  When the uranium concentration is high, the uranium-containing halide is sent to the desorption furnace, and when the uranium concentration is low, the uranium-containing halide is sent to the bypass line. Is high, the concentration of uranium contained in the halide is lowered, so that contaminated radioactive secondary waste can be easily decontaminated to the clearance level, and the amount of waste can be further reduced. Moreover, since it can be selectively used depending on the concentration of uranium, the degree of freedom of equipment and method is high, and the amount of waste can be reduced appropriately.

  When the structure for treating the halide solution after uranium adsorption is provided, the halide from which uranium has been removed can be treated and discarded, so that the amount of waste can be appropriately reduced.

  As described above, according to the uranium recovery facility and the uranium recovery method of the present invention, the amount of waste can be reduced by the incineration of the adsorbent that adsorbs uranium, and uranium is preferably recovered. Various excellent effects can be achieved.

  Hereinafter, a first example of an embodiment of the present invention will be described with reference to the drawings.

  FIG. 1 is a conceptual diagram showing a first example of an embodiment for carrying out the uranium recovery facility and the uranium recovery method of the present invention.

  The first example of the embodiment of the present invention is a uranium adsorption tower 1 capable of introducing a halide such as sodium fluoride (NaF) containing uranium, and a first treatment means for treating a treatment liquid downstream of the uranium adsorption tower 1. 2 and a second processing means 3 capable of incinerating the adsorbent of the uranium adsorption tower 1.

  The uranium adsorption tower 1 is filled with an organic material such as humic acid and tannin and an adsorbent composed of an ion exchange resin capable of adsorbing uranium. Here, the adsorbent is not particularly limited as long as it has a property capable of adsorbing uranium and can be safely disposed of in the atmosphere except for uranium by complete incineration of the adsorbent itself. Absent.

The first treatment means 2 dehydrates the adjustment tank 4 that receives the treatment liquid from the uranium adsorption tower 1, the coagulation sedimentation tank 5 that treats the treatment liquid from the adjustment tank 4, and the treatment liquid from the aggregation precipitation tank 5. A dehydrator 6, slaked lime and CaCl ₂ are introduced from the outside into the adjustment tank 4, and a stirrer 7 is provided. It has. Here, the structure of the adjustment tank 4, the coagulation sedimentation tank 5, and the dehydrator 6 is not specifically limited, You may comprise collectively.

  The second treatment means 3 includes an incineration means (not shown) capable of incinerating the adsorbent taken out from the uranium adsorption tower 1, and a recovery means (not shown) for recovering uranium from the adsorbent incinerated by the incineration means. And. Here, the configuration of the incineration means is not particularly limited as long as the adsorbent can be incinerated. Similarly, the configuration of the recovery means is also particularly limited if uranium can be recovered from the incinerated adsorbent. It is not something. Further, the incineration means and the recovery means may be configured together.

  Hereinafter, the operation of the first example of the embodiment of the present invention will be described.

When recovering uranium from halide containing uranium (used sodium fluoride (NaF)), the uranium-containing halide is made into an aqueous solution and introduced into the uranium adsorption tower 1 to adsorb uranium on the adsorbent. Let Next, the adsorbent is taken out from the uranium adsorption tower 1 and put into incineration means, and the adsorbent is completely burned to CO ₂ , H ₂ O, etc., and uranium is left as an oxide, and the remaining uranium oxide Is recovered by recovery means. Here, CO ₂ , H ₂ O, and the like generated by complete combustion of the adsorbent are released to the outside air except for uranium oxide. Note that CO ₂ , H ₂ O and the like released to the outside air have a safe clearance level.

Here, when uranium is adsorbed on the uranium adsorption tower 1, the treatment liquid is discharged from the uranium adsorption tower 1 at a safe clearance level, and the treatment liquid is sent to the adjustment tank 4. In the adjustment tank 4, slaked lime and CaCl ₂ are added to the treatment liquid and stirred, and the treatment liquid is allowed to flow into the coagulation sedimentation tank 5. In the coagulation precipitation tank 5, the coagulation precipitation agent is subsequently added to the treatment liquid and stirred. Then, the fluorine in the treatment liquid is precipitated as calcium fluoride (CaF ₂ ), and the treatment liquid and the precipitate are transferred to the dehydrator 6. In the dehydrator 6, water, NaCl, CaCl ₂ drainage and calcium fluoride precipitate are separated by dehydration, and the precipitate is treated as waste, and the wastewater is sent to a wastewater treatment facility. To be processed. Here, since NaCl and CaCl ₂ in the wastewater have high solubility, they are discharged after having a predetermined concentration with water.

Thus, according to the first example of the embodiment of the present invention, the adsorbent that adsorbs uranium generates CO ₂ , H ₂ O, and the like that can be released to the outside air by incineration, excluding uranium oxide. Since generation of waste can be prevented, an electrode for attaching uranium, which has been necessary in the past, is unnecessary, and the amount of waste can be reduced. In addition, since the adsorbent that adsorbs uranium can recover uranium oxides completely by incineration, it can be recovered without loss in the amount of uranium recovered. Furthermore, since it is not necessary to use a halide as a molten salt, it is possible to eliminate the heating means for making the melting point 600 ° C. or higher, which has been necessary in the past, thereby reducing running costs and making safety measures excessive.

  If the adsorbent of the uranium adsorption tower 1 is made of an organic material capable of adsorbing uranium, the adsorbent can be suitably treated without incurring waste when incinerated, thus further reducing the amount of waste. Can do. Further, uranium can be favorably recovered by adsorbing uranium to an adsorbent of an organic material. Further, when the adsorbent is humic acid or tannin, incineration can be easily performed, and the adsorption ratio of uranium can be sufficiently maintained.

  When the first treatment means 2 configured to treat the halide solution after uranium adsorption is provided, by treating the halide treatment liquid from which uranium has been removed, precipitates can be removed and the remaining waste water can be discarded. The amount of waste can be reduced appropriately.

  Next, a second example of the embodiment of the present invention will be described with reference to the drawings.

  FIG. 2 is a conceptual diagram showing a second example of an embodiment for carrying out the uranium recovery facility and uranium recovery method of the present invention. In the figure, the same reference numerals as those in FIG. 1 denote the same parts.

  A second example of the embodiment of the present invention is a dissolution tank 9 into which a halide gas such as sodium fluoride (NaF) containing uranium can be introduced, and an aqueous solution of halide containing uranium from the dissolution tank 9. A uranium adsorption tower 1, a first treatment means 2 for treating a treatment liquid downstream of the uranium adsorption tower 1, and a second treatment means 3 capable of incinerating the adsorbent of the uranium adsorption tower 1 are provided.

  The dissolution tank 9 is configured to be able to introduce water, hydrochloric acid, and NaOH from the outside, and is equipped with a stirrer 10, and further has a rough recovery line 13 that is sent to the uranium adsorption tower 1 through the precipitation tank 11 and the dehydrator 12. I have. The precipitation tank 11 is configured to be able to introduce hydrochloric acid, hydrogen peroxide, and NaOH, and includes a stirrer 14, and the dehydrator 12 is configured to dehydrate the processing liquid from the precipitation tank 11. Here, the structure of the dissolution tank 9, the sedimentation tank 11, and the dehydrator 12 is not specifically limited, and may be comprised collectively.

  The uranium adsorption tower 1 and the adsorbent, the adjustment tank 4 and the coagulation sedimentation tank 5 of the first treatment means 2, the dehydrator 6, the incineration means (not shown) and the recovery means (not shown) of the second treatment means 3 are the first. The structure is almost the same as that of the example.

  Hereinafter, the operation of the second example of the embodiment of the present invention will be described.

  When recovering uranium from a uranium-containing halide (used sodium fluoride (NaF)) gas, the uranium-containing halide gas is introduced into the dissolution tank 9, and water, hydrochloric acid, and NaOH are used. The solubility is adjusted appropriately to form an aqueous solution. Next, when the concentration of uranium is high, an aqueous solution of halide containing uranium is sent to the precipitation tank 11 of the rough recovery line 13, and when the concentration of uranium is low, an aqueous solution of halide containing uranium. Is sent to the uranium adsorption tower 1.

Here, when the concentration of uranium is high, the pH of the precipitation tank 11 is adjusted with hydrochloric acid and NaOH, and hydrogen peroxide as an oxidizing agent is added and stirred, so that a large amount of uranium out of the uranium-containing halide is added. Precipitate as uranium oxide (UO ₄ ), transfer the solution and the precipitate to the dehydrator 12, and dehydrate in the dehydrator 12 to separate the uranium-containing solution and the uranium oxide precipitate. The aqueous solution containing the remaining uranium is sent to the uranium adsorption tower 1 while being roughly recovered.

  Next, when an aqueous solution of halide containing uranium is directly introduced into the uranium adsorption tower 1 from the dissolution tank 9 or when introduced into the uranium adsorption tower 1 via the precipitation tank 11 and the dehydrator 12, In substantially the same manner as in the example, uranium oxide is recovered through adsorption of uranium to the adsorbent and incineration of the adsorbent, and the treatment liquid from the uranium adsorption tower 1 is treated.

  Thus, according to the second example of the embodiment of the present invention, it is possible to obtain substantially the same effect as the first example.

  When the halide containing uranium is made into an aqueous solution in the dissolution tank 9, the halide containing uranium is wet-dissolved and uranium is adsorbed appropriately to the adsorbent of the uranium adsorption tower 1, so that contaminated radioactive secondary disposal Objects can be decontaminated to the clearance level, and the amount of waste can be further reduced. Moreover, since the halide containing uranium is wet-dissolved and uranium is appropriately adsorbed on the adsorbent of the uranium adsorption tower 1, uranium can be recovered more suitably. Further, since the halide is wet-dissolved, there is no need to make it into a molten salt by heating, and it is possible to further reduce running costs and eliminate the need for excessive safety measures.

  When the uranium concentration is high, the uranium-containing halide is sent to the precipitation tank 11, and when the uranium concentration is low, the uranium-containing halide is sent to the uranium adsorption tower 1. In the case of high concentration, the concentration of uranium contained in the halide is reduced by rough recovery, so contaminated radioactive secondary waste can be easily decontaminated to the clearance level, and the amount of waste is further reduced. can do. Moreover, since it can be selectively used depending on the concentration of uranium, the degree of freedom of equipment and method is high, and the amount of waste can be reduced appropriately. Furthermore, since hydrochloric acid and NaOH are added in the precipitation tank 11 to adjust the pH and hydrogen peroxide as an oxidizing agent is added, uranium can be preferably precipitated and the uranium recovery rate can be improved.

  Then, the 3rd example of embodiment of this invention is demonstrated based on drawing.

  FIG. 3 is a conceptual diagram showing a third example of an embodiment for carrying out the uranium recovery facility and uranium recovery method of the present invention. In the figure, the same reference numerals as those in FIG. 1 denote the same parts.

  A third example of the embodiment of the present invention is a desorbing furnace 15 that can introduce a halide gas such as sodium fluoride (NaF) containing uranium, and a desorbing furnace 15 that contains a uranium halide. , A uranium adsorption tower 1 for allowing a uranium-containing halide to flow from the desorption furnace 15 or the bypass line 16, and a first treatment means 2 for treating the treatment liquid downstream of the uranium adsorption tower 1. And a second processing means 3 capable of incinerating the adsorbent of the uranium adsorption tower 1.

The desorption furnace 15 is configured to be able to introduce F ₂ gas and N ₂ gas from the outside, and includes an electric furnace 17 as a heating means on the outer periphery, and further to a cylinder 19 or an exhaust gas treatment facility via a cold trap 18. It has a configuration to send.

  The uranium adsorption tower 1 and the adsorbent, the adjustment tank 4 and the coagulation sedimentation tank 5 of the first treatment means 2, the dehydrator 6, the incineration means (not shown) and the recovery means (not shown) of the second treatment means 3 are the first. The structure is almost the same as that of the example.

  Hereinafter, the operation of the third example of the embodiment of the present invention will be described.

  When recovering uranium from a uranium-containing halide (used sodium fluoride (NaF)) gas, if the uranium concentration is high, the uranium-containing halide is desorbed for rough recovery. When the uranium concentration is low, the halide containing uranium is sent to the uranium adsorption tower 1 (subsequent treatment) via the bypass line 16.

In the desorption furnace 15, the halide containing uranium is heated to 350 ° C. or more and less than 600 ° C. by the electric furnace 17 to convert uranium to uranium fluoride (UF ₆ ), and send uranium fluoride to the cold trap 18, and the remaining The uranium-containing halide is sent to the uranium adsorption tower 1. Here, the cold trap 18 is divided into uranium fluoride and nitrogen by being cooled to a predetermined temperature. The uranium fluoride is sent to the cylinder 19 for rough recovery, and nitrogen is sent to the exhaust gas treatment facility for processing. .

  Next, when uranium is directly introduced into the uranium adsorption tower 1 via the bypass line 16 or when it is introduced into the uranium adsorption tower 1 via the desorption furnace 15, the following is substantially the same as in the first example. The uranium oxide is recovered through adsorption of uranium on the adsorbent and incineration of the adsorbent, and the treatment liquid from the uranium adsorption tower 1 is treated.

  Thus, according to the third example of the embodiment of the present invention, it is possible to obtain substantially the same operational effects as the first example.

  When uranium is desorbed from a uranium-containing halide in the desorption furnace 15, it is roughly recovered and the concentration of uranium contained in the halide is reduced, so contaminated radioactive secondary waste can be easily cleared to the clearance level. The amount of waste can be further reduced. Further, since the concentration of uranium contained in the halide is lowered, uranium can be easily and sufficiently adsorbed on the adsorbent of the uranium adsorption tower 1 and uranium can be recovered more suitably. Furthermore, since the halide containing uranium is desorbed at 350 ° C. or more and less than 600 ° C. in the desorption furnace 15, the running cost can be further suppressed.

  When a uranium-containing halide is sent to the desorption furnace 15 when the uranium concentration is low, and a uranium-containing halide is sent to the bypass line 16 when the uranium concentration is low, uranium is provided. The concentration of uranium contained in the halide is reduced when the concentration of selenium is high, so that contaminated radioactive secondary waste can be easily decontaminated to the clearance level, and the amount of waste can be further reduced. it can. Moreover, since it can be selectively used depending on the concentration of uranium, the degree of freedom of equipment and method is high, and the amount of waste can be reduced appropriately.

  Next, a fourth example of the embodiment of the invention will be described with reference to the drawings.

  FIG. 4 is a conceptual diagram showing a fourth example of an embodiment for carrying out the uranium recovery facility and uranium recovery method of the present invention. In addition, in the figure, the part which attached | subjected the code | symbol same as FIGS. 1-3 represents the same thing.

  A fourth example of the embodiment of the present invention includes a roughly recovered desorption furnace 15 capable of introducing a halide gas such as sodium fluoride (NaF) containing uranium, and a uranium-containing halide desorption furnace 15. A bypass line 16 for avoiding uranium, a dissolution tank 9 for introducing a halide containing uranium from the desorption furnace 15 or the bypass line 16, and a uranium adsorption tower 1 for allowing an aqueous solution of a halide containing uranium to flow from the dissolution tank 9 And a first processing means 2 for processing the processing liquid downstream of the uranium adsorption tower 1 and a second processing means 3 capable of incinerating the adsorbent of the uranium adsorption tower 1.

  The desorption furnace 15 and the bypass line 16 have substantially the same structure as in the third example, and the dissolution tank 9 and the precipitation tank 11 and the dehydrator 12 have substantially the same structure as in the second example, and the uranium adsorption tower 1 and the adsorbent, The adjustment tank 4 and the coagulation sedimentation tank 5 of the one processing means 2, the dehydrator 6, the incineration means (not shown) and the recovery means (not shown) of the second processing means 3 have substantially the same structure as the first example.

  The operation of the fourth example of the embodiment for carrying out the present invention will be described below.

  When recovering uranium from a uranium-containing halide (used sodium fluoride (NaF)) gas, as in the third example, when the concentration of uranium is high, the uranium-containing halogen is used. When the concentration of uranium is low, the halide containing uranium is sent to the dissolution tank 9 (subsequent treatment) via the bypass line 16, and in the desorption furnace 15, Process in substantially the same way as in the third example.

  Next, in the dissolution tank 9, in the same manner as in the second example, a uranium-containing halide gas is adjusted to an aqueous solution by appropriately adjusting the solubility with water, hydrochloric acid, and NaOH, and when the concentration of uranium is high, An aqueous solution of halide containing uranium is sent to the coarse recovery precipitation tank 11, and when the concentration of uranium is low, an aqueous solution of halide containing uranium is sent to the uranium adsorption tower 1. Process in the same way as the example.

  Subsequently, in the uranium adsorption tower 1, as in the first example, uranium is adsorbed on the adsorbent, and then the adsorbent in the uranium adsorption tower 1 is burned to recover the uranium oxide. The processing liquid discharged from the uranium adsorption tower 1 is processed in substantially the same manner as in the first example.

  Thus, according to the fourth example of the embodiment of the present invention, it is possible to obtain substantially the same operational effects as the first to third examples.

  Further, since the uranium can be roughly recovered by individually applying the desorption furnace 15 and the dissolution tank 9, the degree of freedom of equipment and method is the highest, and the amount of waste can be suitably reduced.

  Note that the uranium recovery facility and the uranium recovery method of the present invention are not limited to the above-described embodiments, and various modifications may be made without departing from the scope of the present invention.

It is a conceptual diagram which shows the 1st example of the form which implements the uranium collection | recovery equipment and uranium collection | recovery method of this invention. It is a conceptual diagram which shows the 2nd example of the form which implements the uranium collection | recovery equipment and uranium collection | recovery method of this invention. It is a conceptual diagram which shows the 3rd example of the form which implements the uranium recovery equipment and uranium recovery method of this invention. It is a conceptual diagram which shows the 4th example of the form which implements the uranium recovery equipment and uranium recovery method of this invention.

Explanation of symbols

1 Uranium adsorption tower 9 Dissolution tank 11 Sedimentation tank 15 Desorption furnace 16 Bypass line

Claims (15)

  It is equipped with a uranium adsorption tower that adsorbs uranium from halides containing uranium, and the uranium adsorption tower adsorbent has a structure that can recover uranium by incineration and prevent generation of waste. Uranium recovery equipment.   It is equipped with a dissolution tank for making an aqueous solution of halide containing uranium and an uranium adsorption tower for adsorbing uranium from an aqueous solution of halide containing uranium. The adsorbent of the uranium adsorption tower is incinerated to recover uranium. A uranium recovery facility characterized in that it has a structure capable of preventing waste generation as well as being obtained.   Equipped with a desorption furnace that desorbs uranium from uranium-containing halides and a uranium adsorption tower that adsorbs uranium from uranium-containing halides, and the uranium adsorption tower adsorbent recovers uranium by incineration And a uranium recovery facility characterized by having a configuration capable of preventing generation of waste.   A desorption furnace for desorbing uranium from uranium-containing halides, a dissolution tank for converting uranium-containing halides into aqueous solutions, and a uranium adsorption tower for adsorbing uranium from uranium-containing halide aqueous solutions The uranium recovery facility is characterized in that the adsorbent of the uranium adsorption tower has a structure capable of recovering uranium by incineration and preventing generation of waste.   The uranium recovery facility according to any one of claims 1 to 4, wherein the adsorbent of the uranium adsorption tower is an organic material capable of adsorbing uranium.   A precipitation tank is provided for precipitating uranium from halides containing uranium. When the concentration of uranium is high, the halide containing uranium is sent to the precipitation tank. When the concentration of uranium is low, uranium is contained. The uranium recovery facility according to claim 2 or 4, further comprising a structure for sending the halide to the uranium adsorption tower.   Equipped with a bypass line to avoid the desorption furnace, when uranium concentration is high, send uranium-containing halide to the desorption furnace, and when uranium concentration is low, bypass uranium-containing halide The uranium recovery facility according to claim 3 or 4, comprising a configuration for sending to a line.   The uranium recovery facility according to any one of claims 1 to 7, comprising a configuration for processing a halide solution after uranium adsorption.   A uranium recovery method characterized by adsorbing uranium from an uranium-containing halide to an adsorbent, incinerating the adsorbent to recover uranium and preventing generation of waste.   It is characterized in that a halide containing uranium is made into an aqueous solution, uranium is adsorbed on an adsorbent from an aqueous solution of halide containing uranium, and the adsorbent is incinerated to recover uranium and prevent generation of waste. To recover uranium.   Desorb uranium from halide containing uranium in a desorption furnace, adsorb uranium from adsorbent from uranium-containing halide, incinerate the adsorbent to recover uranium and prevent waste generation A method for recovering uranium.   The uranium is desorbed from the uranium-containing halide in a desorption furnace, the uranium-containing halide is made into an aqueous solution, uranium is adsorbed on the adsorbent from the uranium-containing halide aqueous solution, and the adsorbent is incinerated. A method for recovering uranium and preventing generation of waste.   When the concentration of uranium is high, uranium is precipitated from the uranium-containing halide and then adsorbed on the adsorbent. When the concentration of uranium is low, uranium is directly applied to the adsorbent from the uranium-containing halide. The uranium recovery method according to claim 10 or 12, which is adsorbed.   When the concentration of uranium is high, uranium is desorbed from the uranium-containing halide in a desorption furnace. When the concentration of uranium is low, the uranium-containing halide is separated from the desorption furnace. The uranium recovery method according to claim 11 or 12, which is sent to processing.   The uranium recovery method according to any one of claims 9 to 14, wherein the halide solution after uranium adsorption is treated.

Images