KR101233769B1 - The equipment for the removal of adhered salt from uranium deposits using conveyer and the method thereof - Google Patents

Abstract

An apparatus for removing uranium electrode salts and a method for removing salt using the same are disclosed. The uranium electrodeposition salt removal device is a first device including a uranium electrodeposition transfer conveyor for continuously removing the eutectic salts from the uranium electrodeposition material using a conveyor device, and the eutectic salt from the injected uranium electrodeposition material through vacuum distillation. A second device comprising a distillation conveyor device for removal and a third device for removing the collection basket from the uranium from which the eutectic salts have been removed and the recovered eutectic salt collection device, wherein the first device and the third device are It is used in conjunction with the second device.

Description

The apparatus for removing salt from uranium electrodeposits using a conveyor apparatus and the method for removing salt using the same {the equipment for the removal of adhered salt from uranium deposits using conveyer and the method

The present invention relates to a salt removing apparatus and a decontamination method using the same, and more particularly, to a continuous salt removing apparatus from uranium electrodeposition material using a conveyor apparatus and a salt removing method using the same.

Nuclear energy is attracting attention as an alternative to supply abundant energy with low generation of greenhouse gases such as CO _2, and countries around the world are speeding up the construction of nuclear power plants. As a result of the rapid increase in the use of nuclear energy, the amount of spent fuel also increases, and the amount of spent fuel to be managed in the short and long term also increases. The Korea Atomic Energy Research Institute uses a process called pyro process to recover long-lived nuclides from spent nuclear fuel and reuse them as fuels in high-speed reactors to greatly reduce the volume and toxicity of high-level waste and to reduce the space and management period of the repository. It is under study. There are two methods for recovering long-lived nuclides from spent nuclear fuel: wet and dry methods. Pyro process technology is a dry method where plutonium, uranium, and other ultra-uranic elements (Np, Am, Cm) are recovered together to increase nuclear proliferation resistance. In addition, the company is actively researching and developing in Korea, the United States, Japan, and Europe, due to its relatively simple process.

The Pyro process basically uses LiCl-KCl eutectic salts as electrolytes to recover actinide elements at high temperatures using electrochemical methods. The Pyro process, which is being developed by the Korea Atomic Energy Research Institute, is a pretreatment process for removing and powdering spent fuel coatings, an electrolytic reduction process for converting oxide fuel after the pretreatment to metals through reduction, and recovering nuclides from reduced metal bodies. It consists of detailed processes such as electrolytic refining and electrosmelting, and waste treatment to stabilize the waste produced in each process.

Electrolytic refining and smelting of these processes involves placing the metal ingot reduced in the electrolytic reduction process into the anode basket of the electrolytic refining process, using a solid cathode to separate uranium, which accounts for more than 90% of the spent nuclear fuel, and separating uranium. Residual uranium and TRU elements remaining in the LiCl-KCl eutectic salt used in the above were recovered to the liquid cathode using an electrosmelting process. The electrolytic refining process that can effectively recover only uranium is an electrorefining (ER) process that recovers uranium using electrochemical reactions, and an odorous process that removes the eutectic salts remaining in the uranium deposits recovered from ER. It consists of an ingot process that converts uranium from which salt is removed to an ingot. In the ER process, a solid sample that has undergone electrolytic reduction is placed in a positive electrode basket and then into a reactor with eutectic salts.

After inserting a solid cathode made of graphite and flowing a constant electricity, the solid sample in the anode basket is ionized and moved to the solid cathode through the eutectic salt electrolyte, dendritic uranium is electrodeposited on the solid cathode. In the solid cathode, when electrodeposited uranium grows to a certain size, the uranium is naturally desorbed from the cathode and precipitated at the bottom of the reactor, and the precipitated uranium electrodeposit is separated from the reactor to recover only uranium.

However, the recovered uranium electrodeposits contain a large amount of salt, so the salt must be removed to recover only pure uranium. In order to remove salts in uranium deposits, an inflammatory process using thermochemical properties is required, and an inflammatory process is generally performed in a vacuum and high temperature environment. Uranium electrodeposits made by inflammation are present in small dendritic particles, which undergo a metal agglomeration ingot process to facilitate storage, transportation, and use as recycled fuel. The uranium electrodeposits generated in the electrorefining process may be used later to adjust the composition of nuclear fuel such as high-speed reactors, and may be disposed of in a shallow layer because of its weak radioactivity compared to spent nuclear fuel.

     The US INL research center develops and uses a vacuum distillation column called Cathod Processor as an engineering scale device to separate eutectic salts from uranium electrodeposits generated in the ER process. The salt is distilled out by vacuum and heating, and the eutectic salt recovery crucible is placed in the condensation zone located at the bottom of the column to condense and recover the evaporated eutectic salt by air cooling cooling method. Since the device is operated in a batch type, the entire amount of uranium electrodeposits is vacuum distilled, which consumes a large amount of heat, and has a disadvantage of operating at a high temperature where the vapor pressure of the eutectic salt is high.

In addition, in order to increase the processing speed per unit time, the evaporation cross-sectional area must be increased, and thus the internal space must be increased, and the operation cost is high due to the operation of the material at high temperature and vacuum. In addition, the reaction time is increased by adding uranium electrodeposits to the distillation temperature and lowering the temperature inside the apparatus to room temperature in order to take out the recovered uranium and eutectic salts.

Therefore, the present inventors studied a method of removing eutectic salts from uranium electrodeposits generated in the solid cathode of the ER process in the process of recovering actinium elements from spent nuclear fuel using a pyro process, In order to solve the problem, continuous operation is possible, and an inflammatory flow method using a conveyor device has been developed for safe recovery of uranium and distilled salt from which salt has been removed. The continuous inflammatory device of the continuous concept was difficult to apply because the drive is located in a high temperature region due to the characteristics of the distillation apparatus requiring a vacuum, but the continuous inflammatory device manufactured by the present invention is a drive unit outside the high temperature region By making it exist, the continuous concept was made possible.

SUMMARY OF THE INVENTION An object of the present invention is to provide a continuous salt removal device that enables continuous salt removal from uranium electrodeposits using a conveyor device.

Another object of the present invention to provide a salt removal method using a continuous salt removal device from the uranium electrodeposition.

Uranium electrodeposited salt removing device using a conveyor apparatus according to an embodiment of the present invention for solving the above problems comprises a uranium electrodeposited material conveying conveyor for continuously removing the eutectic salt from the uranium electrodeposited material using a conveyor device 1 device; A second apparatus comprising a distillation conveyor apparatus for removing the eutectic salt from the injected uranium electrodeposit through vacuum distillation; And a third device for removing the collection basket from the uranium from which the eutectic salt has been removed and the recovered eutectic salt collection device, wherein the first device and the third device are used in connection with the second device. .

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In order to solve the above problems, a method of driving an apparatus for removing salt of an uranium electrodeposition material using a conveyor belt according to an embodiment of the present invention includes supplying uranium electrodeposition material generated in an external process to a second device using a transport conveyor (step 1 ); Heating and moving the supplied uranium electrodeposit through a distillation transfer conveyor to separate the eutectic salt and uranium (step 2); After distilling the resultant of step 2, collecting and cooling the eutectic salt present in a gaseous state, receiving the uranium separated from the eutectic salt in a collecting basket, and separating and recovering the collecting basket from a flange. (Step 3); And distilling the resultant under vacuum to distill the eutectic salt in the resultant (step 4).

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According to the present invention, the uranium electrodeposited salt removing device and its operation method can perform continuous salt distillation, thereby increasing the processing capacity, and the size of the device is reduced compared to the batch type device, saving the installation space of the device. In addition, the heat generated from the heater increases the heat transfer into the uranium deposit, which is advantageous in terms of thermal efficiency, making the vacuum distillation device more versatile, and spreading thinly over the conveyor belt area, increasing the rate of salt distillation at relatively low temperatures. It can also shorten operating time.

In addition, the batch type operation is performed once, but the energy consumption is increased by raising the temperature inside the reactor to the salt distillation temperature and cooling to room temperature after the completion of salt distillation. In addition, the continuous injection and recovery of the uranium electrodeposition has an effect of improving the linkage with other processes.

1 is an exemplary view showing a uranium deposit supply device for supplying the uranium deposits generated from the outside using a conveyor apparatus according to the present invention into the salt distillation reactor.
Figure 2 is an exemplary view showing in detail the transfer conveyor apparatus used to continuously supply the uranium electrodeposition according to the present invention.
3 is an exemplary view showing an apparatus for distillation and separation of continuous eutectic salts from uranium electrodeposits using a conveyor apparatus according to the present invention.
Figure 4 is an exemplary view showing in detail the distillation conveyor apparatus according to the present invention.
5 is an exemplary view showing an apparatus for recovering uranium and eutectic salts collected and collected in a basket using a cylinder and a conveyor apparatus according to the present invention.
6 is a flow chart illustrating a method for removing salt from uranium electrodeposits using a conveyor apparatus according to an embodiment of the present invention.

Specific structural to functional descriptions of embodiments according to the inventive concept disclosed in the specification or the application are only illustrated for the purpose of describing embodiments according to the inventive concept, and according to the inventive concept. The examples may be embodied in various forms and should not be construed as limited to the embodiments set forth herein or in the application.

Embodiments in accordance with the concepts of the present invention can make various changes and have various forms, so that specific embodiments are illustrated in the drawings and described in detail in this specification or application. However, this is not intended to limit the embodiments in accordance with the concept of the present invention to a particular disclosed form, it should be understood to include all changes, equivalents, and substitutes included in the spirit and scope of the present invention.

The terminology used herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention. Singular expressions include plural expressions unless the context clearly indicates otherwise. In this specification, terms such as "comprise" or "have" are intended to indicate that there is a feature, number, step, action, component, part, or combination thereof that is implemented, and that one or more other features or numbers are present. It should be understood that it does not exclude in advance the possibility of the presence or addition of steps, actions, components, parts or combinations thereof.

Hereinafter, exemplary embodiments of the present invention will be described in detail with reference to the accompanying drawings.

1 is an exemplary view showing a uranium deposit supply device for supplying the uranium deposits generated from the outside using a conveyor apparatus according to the present invention into the salt distillation reactor, Figure 2 is a continuous uranium deposits according to the present invention Exemplary drawing showing in detail the transfer conveyor apparatus used to supply.

As shown in Figures 1 and 2, the uranium electrodepositing device of the present invention includes the first to third devices.

The first device is a device for supplying an externally generated uranium electrodeposited material to the second device and its connectivity with other external processing devices.

The second device is a device for continuously removing the eutectic salt from the uranium electrodeposits using the conveyor device and the heating unit.

The third device is a device for recovering uranium and eutectic salts collected in a recovery basket separated by salt and uranium after the salt distillation process.

More specifically, the first device is a feeding device that delivers uranium electrodeposits generated in an external process to the inside of the second device, and receives external uranium deposits continuously transferred from an external process. The complex transport conveyor apparatus 11, the inner and outer uranium electrodeposition opening and closing cover 16 which can be opened and closed, the internal uranium deposit transport conveyor apparatus 14 for transporting the uranium deposits into the second apparatus, and the transport conveyor apparatus is the internal uranium Conveyor moving pedestal 24 for moving the conveyor to the electrodeposition inlet 15, argon (Ar) gas injection unit 12 and the vacuum pump connection unit 17, the conveyor device is included therein, vacuum and inert gas It is characterized in that it comprises a glove box 13 that can be injected.

The first device is an external uranium deposit transfer conveyor device 11 for transferring uranium deposits generated in an external process into the supply device glove box 13, and a vacuum pump connection part for removing impurity gas introduced from the outside. (17) and an inert gas injection unit 12 to be the same as the environment inside the second apparatus except the temperature environment, and an internal uranium electrodeposition transfer conveyor apparatus 14 for transferring the uranium electrodeposits into the second apparatus. In addition, the transfer conveyor apparatus 14 can adjust the width and height of the conveyor distillation dish 27 according to the processing capacity, without limiting the capacity, the left and right height is preferably at least 50mm or more.

The inner uranium electrodeposition inlet opening and closing cover 16 requires a cooling device to prevent breakage of the sealing device at a high temperature, and it is preferable to use an inert gas such as argon (Ar) gas as the coolant. However, it is not limited to argon (Ar) gas as a coolant.

3 is an exemplary view showing an apparatus for distillation of continuous eutectic salts from uranium electrodeposits using the conveyor apparatus according to the present invention, Figure 4 is an exemplary view showing in detail the distillation conveyor apparatus according to the present invention.

As shown in Figure 3 and 4, the second device is a distillation apparatus for separating the eutectic salt in the uranium electrodeposits through a distillation process, a conveyor distillation dish 34 that can contain and detachable uranium electrodeposition and It is coupled to the conveyor belt 47 having a mobility, the conveyor protection heat sink 46 for reducing the thermal damage of the drive unit of the conveyor belt 47, the external conveyor drive motor 48 for driving the conveyor belt 47, Heating the uranium recovery basket 39 connected to the lower part of the second device to be detachable, the eutectic salt recovery basket 41 to be detachably attached to the lower part of the second device, and the conveyor distillation dish at the end of the conveyor belt 47. Conveyor distillation dish heating heater 45, the uranium recovery basket 39 and the eutectic salt recovery basket 41 is included therein, and heating parts are provided on the upper and lower side surfaces thereof. Distillation conveyor drive shaft 33 is located at the lower end, characterized in that it comprises a reactor 32 including a condensation tank in the lower end side of the eutectic salt recovery basket and a vacuum pump 36 connected to the lower condensation tank.

The distillation conveyor apparatus includes a distillation conveyor drive shaft 33, a conveyor belt 47, a conveyor distillation dish supporter 49 connecting the conveyor distillation dish and the conveyor belt, and a conveyor distillation dish 34 capable of thermal treatment. Conveyor distillation dish 34 has a rectangular shape and its height is not limited.

The shape of the driving unit uses a gear of a sawtooth, and the size tuning is not limited regardless of the moving speed, and the motor of the driving unit is preferably rotated in one direction, and the rotational speed is not limited.

Conveyor belt is preferably in the form of a chain, it is necessary to minimize the heat transfer to the drive unit by mounting a removable conveyor distillation support stand 49 in the center of the belt plate cross-section and a heat sink in the center.

One end of the conveyor distillation dish stand 49 connects a removable conveyor distillation dish. The area of the conveyor distillation dish is not limited depending on the processing capacity, but the height is preferably at least 50 mm and the bottom of the conveyor distillation dish is preferably It should have a slope of up to 5 degrees around the column. In addition, a ceramic or alumina coating may be attempted as necessary.

At this time, the interval between the conveyor distillation dish 34 and the reactor 32 is preferably 1mm maximum but the interval is not limited.

When the uranium electrodeposits are introduced into the conveyor distillation dish, the side portion and the conveyor distillation dish heating heaters 42, 44, and 45 are operated to raise the temperature inside the reactor above the evaporation point of the eutectic salt, and at the same time the temperature rises above the evaporation point. By operating the conveyor drive to transfer the uranium deposits, it is separated into eutectic salts and solid uranium that has changed to a gaseous state.

Most of the salt becomes a gas and moves in the direction of the condensate tank in which the eutectic salt recovery basket 41 is located along the gradient of the upper part of the reactor, and is liquefied at the melting point temperature by the condensate heat sink 43. Solid uranium remains in the conveyor conveyor distillation dish 34 and finally collects in the uranium recovery basket 39.

5 is an exemplary view showing a recovery device for uranium and eutectic salt collected in the basket using a cylinder and a conveyor device according to the present invention.

As shown in FIG. 5, the third apparatus is a uranium and eutectic salt recovery apparatus, and the basket injection cylinder 56 and the recovery basket 51 which separate the uranium and eutectic salt recovery baskets 51 and 52 from the second apparatus. A basket injection plate 53 and a cylinder 54 for moving the 52 to the transfer conveyor device, and a transfer conveyor device 55 for moving the recovery basket to the outside; The transfer conveyor device 55 is located in the front, characterized in that it comprises a glove box (not shown) containing all of these devices therein.

The third apparatus is an apparatus for recovering the eutectic salts and uranium collected using the transfer conveyor apparatus 55; A cylinder 54 for pushing the recovery basket to the conveyor device and a basket injection plate 53 in combination with the surface of the side surface of the recovery basket, and the shape of the basket injection plate 53 is rectangular. It has but is not limited to.

The transfer conveyor device 55 is located at the same height as the uranium and eutectic salt recovery baskets 51 and 52 down from the front of the third device and is located in front of the recovery basket and reaches to the outer connection of the glove box. However, the length is not limited.

In addition, the basket injection cylinder 56, which is operated when the recovery baskets 51 and 52 are taken out of the second device, moves up and down, and can withstand the weight including the basket weight and the collected uranium and eutectic salt weight, respectively. The weight is not limited, but 60 to 100 kg is suitable.

The material of the first device, the second device 200 and the third device is preferably stainless steel, but is not limited thereto. When the material of the first device, the second device and the third device is stainless steel, there is less corrosiveness, and the device manufacturing cost is relatively low.

It is preferable that the conveyor distillation dish of the said 1st apparatus, the 2nd apparatus, and the 3rd apparatus is rectangular, and in principle, it has a fixed height, but the height is not restrict | limited.

When the conveyor distillation dish is rectangular, it is easy to control the contact portion between the dish and the dish, and having a certain height is first formed when the eutectic salt in the uranium electrodeposition changes in the shape of the gas. To prevent it from flowing down.

The uranium electrodeposited salt removing device is capable of continuously injecting uranium electrodeposited material, thereby enabling large-capacity treatment, and reducing the operating time due to the faster processing speed than the batch type in a certain amount of treatment.

In addition, the deposition height of the uranium electrodeposition material can be adjusted by adjusting the capacity of the conveyor distillation plate that can be attached to and removed from the conveyor. Accordingly, the heat generated from the heat source of the heater can be operated at a relatively low temperature due to the high heat transfer efficiency inside the uranium electrodeposit. Do.

In addition, the batch type device has an elevated temperature portion to reach the distillation temperature and a portion that needs to be dropped below room temperature to recover the uranium deposit after distillation. In contrast, the apparatus of the present invention can maintain the high temperature continuously once reaching the distillation temperature can reduce the amount of external energy used.

In addition, the transfer of external uranium deposits to the second device, which is a salt distillation unit, is performed by using the first device, which is an externally produced uranium electrodeposition device, to realize the automation of equipment without the need for manual operation. It can increase connectivity with the same devices.

In addition, the maintenance cost of the device is reduced by replacing only a part of components when the equipment constituting the device of the present invention has the advantage of reducing the amount of waste of the replaced parts.

6 is a flow chart illustrating a method for removing salt from uranium electrodeposits using a conveyor apparatus according to an embodiment of the present invention.

As shown in FIG. 6, the method for removing uranium deposit salt using a conveyor apparatus includes steps 1 (S10) to 4 (S40).

Step 1 (S10) is a step of supplying the uranium electrodeposits generated in the external process using the transfer conveyor to the second device.
Step 2 (S20) is a step of separating the eutectic salt and uranium by heating and moving the supplied uranium electrodeposits through a distillation transfer conveyor.
In step 3 (S30), after distilling the resultant of step 2 (S20), the eutectic salts present in a gaseous state are collected by cooling, and after receiving the uranium separated from the eutectic salts in a collection basket, It is a step of separating and collecting the collecting basket from the flange.
Step 4 (S40) is a step of distilling the eutectic salt in the resultant by distilling the resultant under vacuum.

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More specifically, step 1 (S10), referring to FIGS. 1 and 2, is a step of supplying uranium electrodeposits generated in an external process to the second device S200 using the first device.

First, the outer uranium electrodeposition inlet opening and closing cover 19 of the first device is opened, and the outer uranium electrodeposition transfer conveyor device 11 is pushed using a cylinder so as to be centered in the outer uranium electrodeposition inlet 18. Argon (Ar) gas, which is an inert gas, is suitable as the working gas of the cylinder, but the same gas as the inert gas used in the second apparatus is used, and the type of gas is not limited.

Subsequently, when the conveyor is operated while the external uranium deposit is introduced into the conveyor distillation dish, the uranium deposit is completed onto the internal uranium deposit transfer conveyor apparatus 14.

When the input is completed, the external uranium electrodepositing inlet opening and closing cover is closed after returning to the original position by using the cylinder of the external uranium electrodeposition transfer conveyor device.

The vacuum pump is operated to remove moisture and other contaminant gas inside the supply device (glove box), and then inert gas is injected. This process is repeated 2-3 times, and the number of repetitions is not limited. After the environment inside the feeder is filled with an inert gas, the inner uranium electrodeposition inlet opening / closing cover 16 is opened, and the inner conveyor device 14 is operated to transfer the uranium deposits into the second device. When this process is finished, close the opening and closing cover of the inner uranium deposit, and repeat the above process.

Step 2 (S20), referring to Figures 2 and 4, is a step of separating the eutectic salt and uranium from the uranium electrodeposits supplied in step 1 (S10) using a second device.

The external heaters 42 and 44 and the conveyor distillation heating heater 45 of the second device are operated to raise the internal temperature of the reactor 32 to the eutectic salt evaporation temperature in advance. When the eutectic salt evaporation temperature is reached, the distillation conveyor apparatus is operated, and uranium electrodeposits are supplied to the conveyor distillation dish 34 of the operated distillation conveyor using the first apparatus 100.

The supplied uranium electrodeposits are supplied to the conveyor conveyor distillation dish 34 by a certain amount. At this time, the inner uranium electrodeposition opening and closing cover of the first apparatus is opened so that the heat inside the second apparatus can be moved to the inside of the first apparatus. May occur, but is blocked by the supplied uranium electrodeposits.

The conveyor distillation dish 34 supplied with the uranium deposit is moved toward the uranium collection basket 39 according to the conveyor conveying speed, and during the movement, the eutectic salt is changed into a gaseous phase and evaporated to the final gas. Done.

The eutectic salt, gasified and retaining thermal energy, rises to the top of the reactor, and the solid uranium remains in the conveyor conveyor distillation dish, causing separation of the solid uranium and gaseous eutectic salts. The transfer of gasified eutectic salts is naturally directed towards the eutectic salt collection device and basket 41 by placing a slope above the reactor. The slope of the top of the reactor uses the principle that the gas tries to rise when it has thermal energy, and the slope is not limited but generally slopes of 45 degrees or less are suitable.

The eutectic salt that is separated and transported in a gaseous state is caused by a temperature difference between the upper and lower portions of the heat sink by the condenser heat sink 43, and the gasified eutectic salt moves to the lower portion of the heat sink at a relatively low temperature. After a liquid phase change occurs, it collects in the eutectic salt collection unit.

In step S30, referring to FIG. 5, a recovery basket for collecting uranium, a eutectic salt, and the like of the collected solid is separated and recovered from the second device.

In this step, the uranium recovered from the uranium electrodeposition with the eutectic salt removed may have a size of several centimeters to several um. Therefore, the smaller the particles of the uranium, the more heat generated by oxidation, so special attention is required. This is a necessary step. Therefore, complete disconnection with oxygen is required.

Step 3 (S30) is preferentially performed in a glove box filled with an inert gas such as argon (Ar) gas. First, the atmosphere inside the glove box is filled with an inert gas, and the basket injection cylinder 56 is operated to move down the second device of the uranium recovery basket to be taken out.

Thereafter, the basket injection plate coupled to the cylinder is operated to move the recovery basket onto the transfer conveyor apparatus, and then the transfer conveyor is operated to move out of the glove box. The inert gas is not limited to argon (Ar) gas, it is preferable to minimize the movement of heat by the operation of the vacuum pump when opening the recovery basket.

The glove box 13 of step 1 (S10) should be made of stainless steel, the temperature inside the device is preferably maintained at 30 ~ 400 ℃ or less at room temperature, it can be installed a cooling device if necessary.

The heat generated from the second device may enter the first device when the uranium electrodeposition opening / closing cover 16 of the first device is opened and closed, but the inflow of heat may be less as the uranium deposits are accumulated in the input pipe. have.

In general, at temperatures below 400 ° C, the injected uranium deposits (including eutectic salts) remain solid without phase changes, such as liquids and gases, and can limit the physical losses of cylinders and conveyors installed inside the unit. have.

However, when the temperature is above 400 ° C., the molten salt may be melted (liquidized) and flow out of the conveyor. When the temperature is above 600 ° C., the evaporation loss of the eutectic salt may occur.

In addition, the inner uranium deposit transfer conveyor 14, the drive motor should be mounted on the outside of the glove box, the conveyor movement support 24 is preferably a groove is present as more than one third of the conveyor moving wheel 25 enters. The conveyor wheel 25 should be fixed to the bottom of the glove box and should be removable.

Control of the temperature in the first device can be controlled by the opening and closing time of the inner uranium electrodeposition opening and closing cover 16, the conveyor conveying speed is preferably maintained at a speed of at least 8.0 mm / sec, but the speed is Do not limit.

The heating temperature of step 2 (S20) is preferably carried out in a temperature range of 700 ~ 900. If the evaporation temperature is less than 700, the evaporation rate of the eutectic salt is low, and thus, a problem may arise in that the feed rate of the distillation conveyor of the second apparatus is adjusted very slowly. In addition, if the temperature exceeds 900, the distillation rate may increase due to the high temperature, but problems may occur in the durability of the conveyor and reactor walls, and the uranium input device 100 of step 1 (S10) and the inside of the device of step 3 (S30) This can cause problems with temperature maintenance.

According to the present invention, the uranium electrodeposited salt removing device and its operation method using the conveyor belt can perform continuous salt distillation, thereby increasing the processing capacity, and the size of the device is reduced compared to the batch type device. In addition to saving installation space, the heat generated from the heater increases heat transfer into the uranium deposit, which is advantageous in terms of thermal efficiency, making the vacuum distillation device more versatile, and spreading thinly across the conveyor belt area, resulting in less salt at relatively low temperatures. In addition to increasing the distillation rate, the operating time can be shortened.

In addition, the batch type operation is performed once, but the energy consumption is increased by raising the temperature inside the reactor to the salt distillation temperature and cooling to room temperature after the salt distillation is terminated. In addition, the continuous injection and recovery of the uranium electrodeposition has an effect of improving the linkage with other processes.

As described above, the salt removal apparatus and the salt removal method using the same from the uranium electrodeposition material using the conveyor apparatus of the present invention have been described, but the present invention is not limited by the embodiments and drawings disclosed herein, and the scope of the technical idea is protected. It can be applied within.

11: external uranium electrodeposition conveyer
12: Ar gas injection unit
13: glove box
14: Internal Uranium Electrodeposition Conveyor
15: internal uranium electrodeposition inlet
16: cover opening and closing the inner uranium electrodeposition
17: vacuum pump connection
18: external uranium electrodepositing hole
19: opening and closing lid of the inner uranium deposit
20: cylinder stand
21: Cylinder
22: connecting cylinder and conveyor moving base
23: conveyor moving stand stop
24: conveyor moving pedestal
25: conveyor moving support wheel
26: conveyor drive shaft
27: conveyor distillation dish
31: external uranium electrodepositing device
32: reactor
33: distillation conveyor drive shaft
34: distillation dish
35: external Ar gas injection unit
36: vacuum pump
37: cooling device
38: Hippop Filter
39: Uranium Collector & Basket
40: cylinder
41: eutectic salt collection device and basket
42: condensing tank temperature maintenance heater
43: condenser heat sink
44: reactor heating heater
45: distillation dish heating heater
46: conveyor heat sink
47: conveyor belt
48: Conveyor Drive Motor
49: conveyor distillation dish pedestal
51: Uranium Recovery Basket
52: eutectic salt recovery basket
53: basket injection plate
54: cylinder
55 conveying conveyor
56: basket injection cylinder

Claims (9)

A first device comprising a uranium deposit transfer conveyor for continuously removing eutectic salts from the uranium deposit using a conveyor device;
A second apparatus comprising a distillation conveyor apparatus for removing the eutectic salt from the injected uranium electrodeposit through vacuum distillation; And
And a third apparatus for removing the collection basket from the uranium from which the eutectic salt has been removed and the recovered eutectic salt collection device,
The first device and the third device is used in conjunction with the second device salt removal device from the uranium electrodeposits using a conveyor device.
The method of claim 1,
The first device comprises:
A cylinder for moving the uranium electrodeposition conveyer to the uranium electrodeposition inlet, and a transfer device coupled thereto and detachable;
The uranium electrodeposition conveying conveyor comprising a drive motor;
An opening and closing cover of the uranium electrodepositing inlet to enable opening and closing of the uranium electrodepositing inlet;
The uranium electrodeposition inlet having a rectangular shape; And
Salt removal device from uranium deposit using a conveyor device including an input line.
The method of claim 1,
The second device comprises:
Inflammatory transport conveyor including a conveyor distillation plate and a conveyor drive shaft connecting plate which is detachably connected to the transfer conveyor connecting shaft, and a transfer conveyor belt drive shaft, a drive shaft protection heat sink and a drive motor;
A eutectic salt recovery basket and a uranium recovery basket connected to the lower flange to be detachable;
A reactor including the eutectic salt recovery basket and the uranium recovery basket therein, and a heating unit positioned on the reactor upper, lower, left, right, and bottom portions of the inflammatory flow conveyor, and a heat sink disposed at the bottom of the inflammatory flow conveyor. Condensation tank; And
And a vacuum pump connected to the lower end of the eutectic salt recovery basket and a gas line connection unit for recirculating into the reactor by using the vacuum pump.
The method of claim 1, wherein
The third device comprises:
A cylinder separating the uranium collection basket and the eutectic salt collection basket and a cylinder for pushing each of the uranium collection basket and the eutectic salt collection basket to a transfer conveyor;
A basket separation device having a conveyor for transferring each of the uranium collection basket and the eutectic salt collection basket moved to the transfer conveyor to the outside; And
Salt removal device from the uranium electrodeposition material using a conveyor device characterized in that it comprises a fan having a cooling function outside the basket separator.
The method of claim 3,
The conveyor distillation dish,
A salt removing device from uranium electrodeposited material using a conveyor device, characterized in that it is made of stainless steel and coated with ceramic or alumina therein.
Supplying uranium electrodeposits generated in an external process to a second apparatus using a transfer conveyor (step 1);
Heating and moving the supplied uranium electrodeposit through a distillation transfer conveyor to separate the eutectic salt and uranium (step 2);
After distilling the resultant of step 2, collecting and cooling the eutectic salt present in a gaseous state, receiving the uranium separated from the eutectic salt in a collecting basket, and separating and recovering the collecting basket from a flange. (Step 3); And
Distilling the resultant under vacuum to distill the eutectic salt in the resultant (step 4).
The method according to claim 6,
Step 2,
Salt removal method using a salt removal device from the uranium electrodeposition, characterized in that the heating temperature is carried out in the temperature range 30 ~ 400 ℃.
The method according to claim 6,
Step 3,
Salt removal method using a salt removal device from the uranium electrodeposition, characterized in that the distillation temperature is carried out in the temperature range of 600 ~ 900 ℃.
The method according to claim 6,
Step 4,
Salt removal method using a salt removal device from the uranium electrodeposition, characterized in that the distillation temperature is carried out in the temperature range of 30 ~ 500 ℃.

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