JPH07187679A - Uranium enriching device and method thereof - Google Patents

Abstract

PURPOSE:To provide an uranium enriching device and a method thereof in which energy efficiency is heightened. CONSTITUTION:An uranium generating mechanism 100 has a gas mixing part 110 in which calcium powder is added to gaseous uranium hexafluoride to mix them, and a reaction accelerating part 120 in which the gaseous reaction between the uranium hexafluoride and the calcium powder 4 is started to form gaseous uranium. When a discharge electrode 7 is energized to heat the gas mixture, the following reactions take place: UF6 (g) UF4 (g) + F2 (g); UF4 (g) + 2Ca (g) U (g) +2 CaF2 (s), thus forming gaseous uranium in a reaction chamber 6. The head of the reaction chamber 6 of the reaction accelerating part 120 is restricted to jet the gas mixture from a nozzle 9. Laser rays 14 are irradiated in a vacuum vessel 11 to selectively ionize only uranium 235, which is turned into positive ions.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a uranium fuel used in a nuclear reactor, and more particularly to a uranium enrichment apparatus and a uranium enrichment method for separating and enriching uranium-235 from natural uranium by using a laser method.

[0002]

2. Description of the Related Art Uranium enrichment methods used for the production of uranium fuel used in nuclear reactors include a gas diffusion method and a centrifuge method. Slight shift in absorption spectrum (isotope shift)
A laser method that utilizes the fact that there is is proposed.

The conventional uranium enrichment apparatus using the laser method has the following configuration, as shown in, for example, US Pat. No. 4,210,814. That is, the conventional uranium enrichment apparatus includes a vacuum container, a crucible and an electron gun provided at the bottom of the vacuum container, a plurality of product uranium recovery plates provided in a fan shape above the crucible, and a product uranium recovery plate. And a waste uranium recovery plate provided above. Raw metal uranium is placed in the crucible, and the surface of the metal uranium is irradiated with a deflected electron beam from an electron gun. As a result, metallic uranium is heated to 3000 K or more and evaporated, and gaseous uranium is produced. At this time, the crucible is made of a material having a high thermal conductivity such as copper and is cooled by a coolant, which prevents the metallic uranium from reacting with other substances at a high temperature. The gaseous uranium produced by being heated by the polarized electron beam and being vaporized expands over a wide area above the crucible and flows into between the plurality of product uranium recovery plates. A laser beam that selectively excites and ionizes uranium-235 is irradiated between the product uranium recovery plates. At this time, the laser light is composed of light having a plurality of wavelengths that resonate with uranium-235, and the positive ion uranium-235 is recovered by the product uranium recovery plate by the electric field applied between the product uranium recovery plates. On the other hand, the unrecovered gaseous uranium passes through the product uranium recovery plate, collides with the waste uranium recovery plate, and condenses.

[0004]

However, the above-mentioned known technique has the following problems. That is, in the above-mentioned known technique, since metallic uranium is heated and evaporated to generate gaseous uranium, about 500 kJ of energy is required to obtain 1 mol of gaseous uranium. In addition, while heating the metallic uranium in the crucible with a deflected electron beam, the crucible is cooled with a coolant in order to prevent the reaction of the uranium, and there is a problem that the energy input is large and the energy efficiency is low. .

Even if the product uranium recovery plate is installed in a fan shape at an angle of 50 degrees including vertically above the crucible, the vaporized gaseous uranium expands freely into the vacuum, so that a part of the vaporized gaseous uranium. However, there is a problem in that the recovery efficiency of the gaseous uranium generated due to the loss of hydrogen is low.

A first object of the present invention is to provide a uranium concentrating device and a uranium concentrating method capable of increasing energy efficiency. A second object of the present invention is to provide a uranium concentrator that can enhance the recovery efficiency of gaseous uranium.

[0007]

In order to achieve the first object, according to the present invention, a uranium generating means for generating gaseous uranium from a gaseous uranium compound and the uranium generating means are supplied. In the uranium concentrating device having a uranium recovery means for irradiating the gaseous uranium with a laser beam and selectively ionizing and recovering uranium-235 from the gaseous uranium, the uranium generating means includes the gaseous uranium. Gas mixing means for adding a reducing substance that reduces the uranium compound to the compound and mixing, and a reaction for starting a gas phase reaction between the gaseous uranium compound and the reducing substance in the mixed gas to generate gaseous uranium A uranium enrichment device is provided, which has an accelerating means.

In order to achieve the above first and second objects, according to the present invention, a uranium generating means for generating gaseous uranium from a gaseous uranium compound and the gas supplied from the uranium generating means. In a uranium concentrating device having a uranium recovery means for irradiating laser light on the gaseous uranium and selectively ionizing and recovering uranium-235 from the gaseous uranium, the uranium generating means is characterized in that A gas mixing means for adding and mixing a reducing substance for reducing the uranium compound, and a reaction promoting means for initiating a gas phase reaction between the gaseous uranium compound and the reducing substance in the mixed gas to generate gaseous uranium. And at least one of the uranium generating means and the uranium recovering means recovers the mixed gas from the uranium generating means by the uranium recovering means. Uranium enrichment apparatus comprising means stop supplying while squeezing the flow to the stage is provided.

[0009] Preferably, in the uranium concentrating device, the reaction promoting means has a discharge electrode arranged around the flow path of the mixed gas to discharge and heat the mixed gas. Provided.

Further preferably, in the uranium enrichment apparatus, the uranium generating means is arranged above the uranium recovering means, and the uranium recovering means includes a vacuum container whose inside is maintained in a vacuum and the uranium generating means. A laser means for irradiating the gaseous uranium supplied from the inside of the vacuum container with laser light, and a voltage is applied to the gaseous uranium irradiated with the laser light, which is arranged below the inside of the vacuum container so as to face each other. There is provided a uranium concentrator having a pressure electrode.

More preferably, in the uranium concentrator, the gaseous uranium compound is uranium hexafluoride.

Further preferably, in the uranium concentrating device, there is provided a uranium concentrating device, wherein the reducing substance is an alkaline earth metal.

Further, in order to achieve the above first object,
According to the present invention, in a uranium enrichment method for generating gaseous uranium from a gaseous uranium compound and irradiating the generated gaseous uranium with laser light to selectively ionize and recover uranium-235, A method for enriching uranium, characterized in that gaseous uranium is generated by reacting a uranium compound in the form of a gas with a reducing substance that reduces the uranium compound.

[0014] Preferably, in the uranium enrichment method, the gaseous uranium compound is uranium hexafluoride.

Also preferably, in the uranium enrichment method, there is provided the uranium enrichment method, wherein the reducing substance is an alkaline earth metal.

[0016]

In the present invention configured as described above, the reducing substance is added to the gaseous uranium compound by the gas mixing means to form a mixed gas, and the gas phase reaction between the gaseous uranium compound and the reducing substance is performed by the reaction promoting means. Is initiated to produce gaseous uranium, thereby reducing the uranium compound to produce gaseous uranium. Therefore, as compared with the case of evaporating metallic uranium, the energy required for making uranium in a gaseous state can be reduced, and energy loss due to cooling of the crucible does not occur.

Further, in the present invention, a reducing substance is added to the gaseous uranium compound by the gas mixing means to form a mixed gas,
The reaction promoting means initiates a gas phase reaction between the gaseous uranium compound and the reducing substance to generate gaseous uranium, thereby reducing the uranium compound and generating gaseous uranium.
Therefore, as compared with the case of evaporating metallic uranium, the energy required for making uranium in a gaseous state can be reduced, and energy loss due to cooling of the crucible does not occur. Further, by supplying the mixed gas while restricting the flow rate by the throttling means, gaseous uranium contained in the mixed gas is ejected from the throttling means in the form of a narrow atomic beam to the uranium recovery means, and all gaseous uranium is discharged. It is possible to recover the uranium-235 by irradiating it with laser light and ionizing it without leakage. Further, by discharging and heating the mixed gas with the discharge electrode arranged around the flow path of the mixed gas, it is possible to start the gas phase reaction between the uranium or the uranium compound contained in the uranium raw material and the reducing substance. Further, by disposing the vacuum vessel below the uranium generating means, the gaseous uranium supplied from the uranium generating means forms a downward flow from the uranium generating means to the vacuum vessel and is guided downward, and the laser Uranium-235 is selectively ionized by irradiating laser light by means of a means, and further, uranium-235 is applied by applying a voltage between the pressure electrodes arranged below each other in the vacuum container so as to face each other. Only 235 is collected on the negative side of the pressure electrode. Therefore, the compounds and the like produced from the reducing substances other than uranium-235 are collected below the pressure electrode without scattering in the vacuum container.
These can be collected separately.

As the gaseous uranium compound, for example, uranium hexafluoride can be used, and as the reducing substance, alkaline earth metals such as calcium and magnesium can be used.

[0019]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIGS. The overall structure of the uranium enrichment apparatus of this embodiment is shown in FIG.
2 is a partially enlarged view. Here, FIG. 1 is a cross-sectional side view of the uranium enrichment apparatus, where the upper side in the figure shows the upper side of the apparatus and the lower side in the figure shows the lower side of the apparatus. 2 is a cross-sectional view of the details of the reaction promoting unit 120 and the uranium recovery mechanism 200 (described later) shown in FIG. 1, viewed from the direction A in FIG. Figure 1
2, the uranium enrichment apparatus of the present embodiment is a uranium generating mechanism 100 that generates gaseous uranium, and a uranium-235 that selectively ionizes and recovers uranium-235 from the gaseous uranium supplied from the uranium generating mechanism 100. Collection mechanism 20
Has 0 and.

The uranium generating mechanism 100 has a raw material cylinder 1 storing uranium hexafluoride which is a gaseous uranium compound, and a downstream side of the raw material cylinder 1 forms a series of pipes through which gas from the raw material cylinder flows. is doing. The raw material cylinder 1 is always kept at 60 degrees because uranium hexafluoride sublimes at 56.5 degrees, and a gas flow rate control device 2 is connected downstream of the raw material cylinder 1 and flows into the apparatus from the raw material cylinder 1. The amount of uranium hexafluoride gas used is controlled.

Further, the uranium generating mechanism 100 is provided with a gas mixing section 110 in the downstream pipe line of the gas flow rate control device 2 for adding calcium powder 4 as a reducing substance for reducing uranium hexafluoride to uranium hexafluoride gas and mixing them. ing. The gas mixing unit 110 has a reducing substance reservoir 5 provided in a shape to form a depression in the gas pipeline, and a funnel-shaped structure provided above the reducing substance reservoir 5 and having a tip protruding into the gas pipeline. And a substance supply device 3. As a result, when the gas flows in the pipeline, the calcium powder 4 in powder form is sucked into the pipeline from the reducing substance supply device 3 due to the pressure loss in the pipeline. A part of the calcium powder 4 sucked into the pipe is directly mixed with the gas flow and further moved, and the rest is accumulated in the reducing substance reservoir 5. At this time, the calcium powder 4 accumulated in the reducing substance reservoir 5 can be taken into the gas flowing in the pipe by increasing the gas flow rate.

Further, the uranium generating mechanism 100 promotes a reaction in which a gas phase reaction between uranium hexafluoride and calcium powder 4 is started in the mixed gas in the downstream side pipeline of the gas mixing section 110 to generate gaseous uranium. It has a part 120. The reaction promoting unit 120 includes a reaction chamber 6 that causes a gas phase reaction, a discharge electrode 7 that is wound around the reaction chamber 6 in a coil shape, and a high-frequency power source 8 that applies a high-frequency voltage to the discharge electrode 7. Have. When the high frequency power supply 8 energizes the discharge electrode 7, the reaction chamber 6
The mixed gas that has flowed into the chamber is discharged and the mixed gas is heated.
As a result, the uranium hexafluoride gas and the calcium powder 4 are respectively heated, and the uranium hexafluoride becomes UF6 (g) → UF4 (g) + F2 (g) and decomposes into uranium tetrafluoride and fluorine. Furthermore, the calcium powder 4 collides with this, and a reaction of UF4 (g) + 2Ca (s) → U (g) + 2CaF2 (s) occurs, and finally, in the reaction chamber 6, gaseous uranium and solid calcium fluoride are generated. And are generated. At this time, the reaction chamber 6 has a fan-shaped spread structure (see FIG. 2), so that the pressure in the reaction chamber 6 is kept lower than the pressure in the flow passage on the upstream side of the reaction chamber 6, It is possible to prevent the generated gas from flowing back.

Here, the tip of the reaction chamber 6 is throttled to form a nozzle 9 (for example, a width of about 3 mm) as a throttle means, and the flow rate of the mixed gas is throttled from the uranium generating mechanism 100 to the uranium recovering mechanism 200. The gas is supplied, and thereby the mixed gas is ejected from the nozzle 9.

The uranium recovery mechanism 200 is disposed below the uranium generation mechanism 100 and has a vacuum container 11 connected to the nozzle 9. This vacuum container 11
Has its interior evacuated by a vacuum pump 12 and is maintained in a substantially vacuum state.
The mixed gas 10 containing gaseous uranium supplied from 0,
Go straight downward in the vacuum container 11 while spreading slightly. Although the spread of the mixed gas 10 depends on the pressure of the gas supplied to the nozzle 9 and the width of the cross section of the nozzle 9,
In this embodiment, the width of the cross section of the nozzle 9 is kept constant, and the spread of the mixed gas 10 is adjusted to, for example, 5 cm or less by controlling the gas flow rate control device 2.

A mixed gas 10 that has gone straight in the vacuum container 11
In the lower part of the vacuum container 11, the laser light 14 generated by the laser generator 13 outside the vacuum container 11 and introduced into the vacuum container 11 through the laser light transmission window 15 is irradiated (see FIG. 2). This laser light 14 is a combination of light of three wavelengths that is absorbed and resonated only by uranium-235, and selectively ionizes only uranium-235. That is, it has almost no effect on fluorine and calcium fluoride. As a result, only uranium-235 is selectively ionized from the gaseous uranium into positive ions.

Further, the uranium recovery mechanism 200 faces each other below the vacuum container 11 (for example, the interval is 5 cm).
Recovery plate 1 which is an electrode for applying a voltage to the mixed gas 10 containing gaseous uranium, which is arranged in a row and is irradiated with the laser beam 14.
It has 6a and 16b. That is, a negative voltage is applied to one of the recovery plates 16a, and a positive voltage is applied to the other recovery plate 16b, so that the uranium-having positive ions is generated.
Only 235 is attached to the recovery plate 16a and recovered, and other components contained in the mixed gas 10, that is, waste uranium (uranium-238 other than uranium-235, uranium-234, etc.)
Since fluorine / calcium fluoride is electrically neutral, it goes straight on and collides with the waste collection unit 17. Then, the waste uranium and calcium fluoride that are solid at room temperature are accumulated in the waste collection unit 17, and the gas fluorine reaches the compressor 18 provided further downstream and the pressure is increased, and then the fluorine-filled cylinder 19 is supplied. It can be stored.

Next, the operation of this embodiment will be described. As a comparative example of the present embodiment, a conventional uranium enrichment device is shown in FIG. The uranium concentrator has a vacuum container 27 and a vacuum container 27.
Crucible 20 and electron gun 22 provided at the bottom of the crucible 20, a plurality of product uranium recovery plates 16 provided in a fan shape above the crucible 20, and a waste uranium recovery plate 26 provided further above the product uranium recovery plate 28. Have and. A metal uranium 21 as a raw material is arranged in the crucible 20, and the surface of the metal uranium 21 is irradiated with a deflected electron beam 23 from an electron gun 22. As a result, the metallic uranium 21 is heated to 3000 K or more and evaporated, and the gaseous uranium 25 is generated. At this time, the crucible 20 is made of a material having a high thermal conductivity such as copper and is cooled by the coolant 24. This prevents the metal uranium 21 from reacting with other substances at a high temperature. The gaseous uranium 25 that is heated and evaporated by the deflected electron beam 23 expands over a wide area above the crucible 20 and flows into between the product uranium recovery plates 28. A laser beam 29 that selectively excites and ionizes uranium-235 is irradiated between the product uranium recovery plates 28. At this time, the laser beam 29 is uranium-2.
Light of a plurality of wavelengths that resonate with 35 is synthesized, and positive ion uranium-235 is recovered by the product uranium recovery plate 28 by the electric field applied between the product uranium recovery plates 28. On the other hand, the gaseous uranium 25 that was not recovered was
Waste uranium recovery plate 2 passing through the product uranium recovery plate 28
6 hits and condenses.

In the above, in the above comparative example, since the metallic uranium is heated and evaporated to generate the gaseous uranium, about 500 kJ of energy is required to obtain 1 mol of the gaseous uranium. In addition, while heating the metallic uranium in the crucible with a deflected electron beam, the crucible was cooled with a coolant in order to prevent the reaction of the uranium, and the energy input was large and the energy efficiency was low. However, in the uranium concentrating device of the present embodiment, the gas mixing mechanism 100 adds the calcium powder 4 to the gaseous uranium hexafluoride to form a mixed gas, and the reaction promoting unit 120 combines the uranium hexafluoride gas and the calcium powder 4. Uranium hexafluoride is reduced to produce gaseous uranium by initiating a gas phase reaction to produce gaseous uranium. That is, UF6 (g) → UF4 (g) + F2 (g) (heat of formation + 474k
J) UF4 (g) + 2Ca (g) → U (g) + 2CaF2 (s) (heat of formation −315 kJ (however, (s): solid: (g) gas), so that the gas phase reaction is carried out. ,
In order to decompose uranium hexafluoride into uranium tetrafluoride,
It can be seen that an energy of 474 kJ is required for 1 mol of uranium. On the other hand, when uranium tetrafluoride is produced, the uranium tetrafluoride reacts with calcium to produce gaseous uranium and releases energy of 315 kJ. From these, the energy required to generate 1 mol of gaseous uranium when the reaction became stationary was 159 kJ (= 474-315), which was the sum of these, and evaporated the metallic uranium of the above comparative example. The energy required to turn uranium into a gaseous state can be reduced to about 1/3 as compared with the energy required in the case of 500 kJ. In addition, there is no loss of energy due to cooling of the crucible as in the conventional case.

Further, in the above comparative example, even if the product uranium recovery plate 28 is installed in a fan shape having an angle of 50 degrees including vertically above the crucible 20, the vaporized gaseous uranium 25 freely expands into a vacuum. Therefore, a part of the gaseous uranium 25 was lost and the recovery efficiency was low. However, in the present embodiment, by supplying the mixed gas 10 while reducing the flow rate by the nozzle 9, the flow rate from the gas flow rate control device 2 is controlled to adjust the pressure of the mixed gas 10, and the gaseous uranium is discharged from the nozzle. 9
The uranium-235 can be recovered by ejecting it in the form of a narrow atomic beam to the uranium recovery mechanism 200, irradiating all the gaseous uranium with the laser light 14 and ionizing it without leakage.

Further, in the present embodiment, the discharge electrode 7 disposed around the flow path of the mixed gas discharges the mixed gas and heats it to start the gas phase reaction between the uranium hexafluoride and the calcium powder 4. Can be made. Further, by disposing the vacuum container 11 below the uranium generating mechanism 100, the gaseous uranium supplied from the uranium generating mechanism 100 forms a downward flow from the uranium generating mechanism 100 to the vacuum container 11 and moves downward. Guided by laser light 14
Uranium-235 is selectively ionized by the irradiation of uranium, and is further guided between the recovery plates 16a and 16b arranged below the vacuum chamber 11 so as to face each other and a uranium-235 is applied. Only 235 is collected in the recovery plate 16a on the negative electrode side. Therefore, uranium-23
Waste containers other than 5 such as uranium and calcium fluoride are vacuum containers 1
Since they can be collected below the recovery plates 16a and 16b without scattering into the inside 1, they can be recovered separately.

As described above, according to this embodiment,
In the gas mixing mechanism 100, the calcium powder 4 is added to gaseous uranium hexafluoride to form a mixed gas, and the reaction promoting unit 120 starts a gas phase reaction between the gaseous uranium hexafluoride gas and the calcium powder 4 to form a gaseous state. Since uranium is produced, the energy required to vaporize uranium can be reduced as compared with the case of vaporizing metallic uranium. In addition, there is no loss of energy due to cooling of the crucible as in the conventional case. Therefore, energy efficiency can be improved. Further, since the mixed gas 10 is supplied while the flow rate is reduced by the nozzle 9, all the gaseous uranium is irradiated with the laser light 14 and ionized without leakage to recover the uranium-235 and enhance the recovery efficiency of the gaseous uranium. be able to. Further, since the discharge electrode 7 arranged around the flow path of the mixed gas discharges and heats the mixed gas, uranium hexafluoride and calcium powder 4
A gas phase reaction with can be initiated. Further, since the vacuum container 11 is arranged below the uranium generating mechanism 100, the gaseous uranium supplied from the uranium generating mechanism 100 forms a downward flow and is guided downward, and the laser light 14 is irradiated, so that the uranium- Only 235 is selectively ionized. Further, since a voltage is applied by being guided between the recovery plates 16a and 16b arranged below the vacuum container 11 so as to face each other, only uranium-235 is collected in the recovery plate 16a on the negative electrode side. Therefore, waste uranium other than uranium-235
Since calcium fluoride and the like are collected below the recovery plates 16a and 16b without scattering in the vacuum container 11, they can be recovered separately.

Although calcium powder 4 is used as the reducing substance and uranium hexafluoride, which is a fluoride, is used as the uranium compound in the above embodiments, the present invention is not limited to this. That is, as the reducing substance, a substance that is more likely to generate a halide than uranium, for example, an alkaline earth metal (magnesium, barium, strontium,
Radium, etc.) and alkali metals (lithium, sodium,
Potassium, cesium, rubidium, etc.) are conceivable, and as the uranium compound, halogen compounds of other halogens (chlorine, odor, iodine, etc.) which are more likely to form a compound and are more active than existing alone are considered. The total amount of energy that must be added to produce uranium is 5 per mole of uranium.
The same effect as that of the present embodiment can be obtained by appropriately selecting a value smaller than 00 kJ. As an example, when magnesium is used as the reducing substance and uranium hexafluoride is used as the uranium compound, UF6 (g) → UF4 (g) + F2 (g) (heat of formation + 474k
J) UF4 (g) + 2Mg (g) → U (g) + 2MgF2 (s) (heat of formation-377 kJ), and the energy required to generate 1 mol of gaseous uranium is 97 kJ (total). = 474
-377), the same effect as that of the above embodiment can be obtained.

In the above embodiment, the uranium generating mechanism 100 is provided with the nozzle 9 which is a throttle means for supplying the mixed gas from the uranium generating mechanism 100 to the uranium recovering mechanism 200.
However, it may be provided on the uranium recovery mechanism 200 side or on both sides. The nozzle is not limited to the nozzle as long as it has a function of reducing the flow rate. Also in this case, the same effect is obtained.

[0034]

According to the present invention, a reducing substance is added to a gaseous uranium compound by a gas mixing means to form a mixed gas, and a gas phase reaction between the gaseous uranium compound and a reducing substance is started by a reaction promoting means. Since the gaseous uranium is generated by means of the above method, the energy required for making the uranium into a gaseous state can be reduced as compared with the case of vaporizing metallic uranium, and the energy loss due to the cooling of the crucible does not occur. Therefore, energy efficiency can be improved.

Further, according to the present invention, the reducing substance is added to the gaseous uranium compound by the gas mixing means to form a mixed gas, and the reaction promoting means starts the gas phase reaction between the gaseous uranium compound and the reducing substance. Since gaseous uranium is produced, the energy required to vaporize the uranium can be reduced as compared with the case of vaporizing metallic uranium, and energy loss due to cooling of the crucible does not occur. Therefore, energy efficiency can be improved. Further, since the mixed gas is supplied while restricting the flow rate by the restricting means, it is possible to irradiate all the gaseous uranium with laser light and ionize it without leakage to recover the uranium-235, thereby increasing the recovery efficiency of the gaseous uranium. it can. Further, since the discharge electrode arranged around the flow path of the mixed gas discharges and heats the mixed gas, it is possible to start the gas phase reaction between the uranium or the uranium compound contained in the uranium raw material and the reducing substance. Further, since the vacuum vessel is arranged below the uranium generating means, the gaseous uranium supplied from the uranium generating means forms a downward flow from the uranium generating means to the vacuum vessel and is guided downward, and further the laser means is provided. Uranium-23 because it is irradiated with laser light at
Only 5 is selectively ionized, and further, uranium-235 is collected on the negative electrode side of the pressure electrode because a voltage is applied between the pressure electrodes, which are arranged under the vacuum container so as to face each other. . Therefore, a compound or the like generated from a reducing substance other than uranium-235 is collected below the pressure electrode without being scattered in the vacuum container, and these can be separately collected.

[Brief description of drawings]

FIG. 1 is an overall structural diagram of a uranium enrichment device according to an embodiment of the present invention.

FIG. 2 is a partially enlarged view of a uranium enrichment device.

FIG. 3 is an overall configuration diagram of a conventional uranium enrichment device.

[Explanation of symbols]

 3 Reducing substance supply device 4 Calcium powder 5 Reducing substance reservoir 6 Reaction chamber 7 Discharge electrode 8 High frequency power source 9 Nozzle 10 Mixed gas 11 Vacuum container 13 Laser generator 14 Laser light 16a, b Collection plate

Claims (9)

[Claims] 1. A uranium generating means for generating gaseous uranium from a gaseous uranium compound, and irradiating the gaseous uranium supplied from the uranium generating means with laser light to produce uranium-235 from the gaseous uranium. In a uranium concentrating device having a uranium recovery means for selectively ionizing and recovering, the uranium generating means is a gas mixing means for mixing the gaseous uranium compound with a reducing substance for reducing the uranium compound, and A uranium concentrating device comprising: a reaction promoting means for initiating a gas phase reaction between the gaseous uranium compound and the reducing substance in a mixed gas to generate gaseous uranium. 2. A uranium generating means for generating gaseous uranium from a gaseous uranium compound, and irradiating the gaseous uranium supplied from the uranium generating means with laser light to produce uranium-235 from the gaseous uranium. In a uranium concentrating device having a uranium recovery means for selectively ionizing and recovering, the uranium generating means is a gas mixing means for mixing the gaseous uranium compound with a reducing substance for reducing the uranium compound, and And a reaction promoting means for generating a gaseous uranium by initiating a gas phase reaction between the gaseous uranium compound and the reducing substance in the mixed gas, and at least the uranium generating means and the uranium recovering means. One has a throttle means for supplying the mixed gas from the uranium generating means to the uranium recovery means while reducing the flow rate. Uranium enrichment equipment to. 3. The uranium concentrator according to claim 1 or 2, wherein the reaction promoting means has a discharge electrode arranged around the flow path of the mixed gas to discharge and heat the mixed gas. Uranium enrichment device. 4. The uranium concentrating device according to claim 1, wherein the uranium generating means is disposed above the uranium recovering means, and the uranium recovering means includes a vacuum container whose interior is maintained in vacuum. Laser means for irradiating the gaseous uranium supplied from the uranium generating means with laser light in the vacuum container, and gas uranium irradiated with the laser light, which are arranged below each other in the vacuum container so as to face each other. A uranium concentrating device having a pressure electrode for applying a voltage. 5. The uranium concentrator according to claim 1 or 2, wherein the gaseous uranium compound is uranium hexafluoride. 6. The uranium concentrator according to claim 1 or 2, wherein the reducing substance is an alkaline earth metal. 7. A uranium enrichment method for producing gaseous uranium from a gaseous uranium compound, irradiating the produced gaseous uranium with laser light to selectively ionize and recover uranium-235, wherein A method for enriching uranium, characterized in that gaseous uranium is generated by reacting the uranium compound with a reducing substance that reduces the uranium compound. 8. The uranium enrichment method according to claim 7, wherein the gaseous uranium compound is uranium hexafluoride. 9. The uranium enrichment method according to claim 7, wherein the reducing substance is an alkaline earth metal.