KR101572763B1 - Total processing facility for manufacturing radionuclides from fission products - Google Patents

Abstract

The present invention relates to comprehensive process equipment for producing useful nuclides from a fission product, including a hot cell bank unit for producing radio isotopes. The hot cell bank unit comprises: a receiving hot cell which a target can be inserted into and withdrawn from; a dissolution hot cell for a filtration process; a purification hot cell for separation and purification of useful nuclides; and a bulk source hot cell for demultiply with the amount of radioactivity of a required solution.

Description

TECHNICAL FIELD [0001] The present invention relates to a process facility for producing a useful radionuclide from a fission product,

The present invention is based on the fact that facilities for producing radioactive isotopes are directly linked to the reactor facilities so that radioactive isotopes can be produced while ensuring sufficient shielding performance when transporting target radioactive isotopes, A system for storing and managing solid, gaseous, liquid and solid radioactive wastes is integrated so that the efficiency and safety of operation can be improved, and the integrated process facility for producing useful radionuclides from fission products that can easily realize mechanical operation and chemical treatment will be.

Today, the range of radioisotope utilization and utilization technology are rapidly developing.

Despite the general tendency to abhor radiation from radioactive isotopes, the reason for such a high utilization rate is due to the inherent characteristics of the radioactive isotope. A typical characteristic of the radioactive isotope is that it radiates radiation having a small but high permeability, Industry and many other aspects.

This means that various types of radioactive isotopes have various lifetimes and emit radiation of various energies and various types of radiation such as alpha, beta, gamma, etc., This means that the unlimited potential is an energy source and that is why it makes a significant contribution to industry, medical science, and scientific research.

Currently, there are about 3,000 radioactive isotope companies in Korea, including radiation nondestructive testing, radioactive isotope gauge, industrial radioactive tracer, in-body diagnosis and treatment, in vitro diagnosis, in vitro radiation therapy, radiation sterilization, Research and development, industrial research, engineering research, and so on, it is very difficult to enumerate all kinds of industrial technology development, productivity improvement, pollution prevention, industrial safety, medical technology development and welfare implementation, food production and food preservation, It is a fact to contribute.

In order to produce useful radioactive isotopes obtained from nuclear fission among the radioactive isotopes used in various fields as described above, nuclear material safeguards (nuclear safeguards) as facilities for handling nuclear materials and radioactive isotopes, and reliability in terms of radiation safety Facilities.

When uranium is irradiated by neutron irradiation, 700 kinds of radioactive isotopes are generated. In order to separate useful radioactive isotopes from them, various kinds of solvents are used to dissolve, precipitate, filter, purify through columns and the like In the process of separating and dispensing, various kinds of radioactive waste are generated in proportion to the production scale of RI. Therefore, it is desirable that waste treatment and management facilities as well as production facilities are integrated in order to effectively and safely treat them.

Existing production facilities for producing radioactive isotopes from fission products may be installed at or remote from the reactor, or may be located adjacent to, but capable of providing a sufficient level of radiation shielding for the transport of neutron radiation to produce radioactive isotopes. , They are transported into a building such as lead to be transported into the building, and then the radioactive isotope is separated through chemical treatment.

This is because, when the material for producing radioactive isotopes is transferred from the reactor to the production facility, if there is not sufficient shielding, there is a possibility of radiation hazard of workers, there is a risk of radioactive leakage during transportation, There is a problem that an extra cost is excessively spent.

US Patent No. 8374306 (Mar. 02, 2013) US Published Patent US 20090196390 (Aug. 06, 2009)

SUMMARY OF THE INVENTION The present invention has been made to solve the above problems,

The integrated process facility for producing useful radionuclides from fission products is directly linked to the reactor facilities, so that the radioactive isotope production can be facilitated while ensuring sufficient shielding performance when transporting radioactive isotope target materials, Comprehensive facilities including waste facilities and management system are organized for each functional level so that the convenience of storage and management of gas, liquid and solid radioactive waste generated during the process can be secured. And to increase the efficiency and safety of the system.

In an integrated process facility for producing useful radionuclides from a fission product according to the present invention, the hot cell bank unit comprises a Receiving Hot Cell configured to be able to enter and exit the target to receive a neutron irradiation rig or a neutron irradiation target; And a Dissolution Hot Cell for filtration after dissolving the targets of the inert gas and the neutron irradiation target generated at the time of dissolving the neutron irradiation target and the neutron irradiation target; Purification Hot Cell for purification and separation of useful radionuclides; A Bulk Source Hot Cell for dispensing with the amount of radioactivity required; And a transfer hot cell for packing and transporting the prepared radioactive isotope; And a control unit.

The hot cell bank unit according to the present invention has a structure in which a gas, liquid, solid waste storage space, which is a type of waste, and a waste storage system, which are provided in a storage space according to the level of the waste, Until the elapse of the period, the waste carry-out can be minimized.

The integrated process facility for producing useful radionuclides from the fission products according to the present invention is able to transport the target radioisotope directly through the passages connected from the reactor, thereby enhancing safety and operational efficiency.

The present invention is also applicable to a radioisotope production facility without using a separate shielding container, except that a target for producing isotopes containing nuclear material irradiated with neutrons is transported to the outside of the facility within a short time By minimizing the time taken from the end of neutron irradiation to the production of radioactive isotopes in nuclear reactors, thereby reducing the unnecessary extinction caused by the collapse of radioactive isotopes, thereby improving the productivity. Thus, the required amount of the substance used in the production of radioactive isotopes And waste generation amount can be minimized.

In addition, the present invention relates to a method for producing a fission moly (Mo-99), which is separated from a nuclear fission product of uranium, after transferring a neutron irradiation fuel material from a reactor core to a reactor after a predetermined cooling time, Separation, purification and waste transfer management system are integrated and installed in the facility, so that production and distribution of radioisotope raw material are constituted as a continuous closed system, thereby improving the efficiency, rationality and safety of the process simultaneously .

Further, the present invention is capable of storing gas, liquid, and solid radioactive waste generated during operation of a radioactive isotope production process including Fission Moly (Mo-99) So that the radiation safety can be improved.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a cross-sectional view of an integrated process facility for producing useful radionuclides from a fission product according to the present invention; FIG.
2 is a schematic cross-sectional view showing an integrated process facility according to the present invention,
3 to 6 are plan views showing respective layers of the integrated processing facility according to the present invention,
7 is a perspective view showing the solid waste storage means of the integrated process facility according to the present invention,
8 to 10 are perspective views illustrating an internal space and a work space of a hot cell according to the present invention,
11 and 12 are perspective views showing a transfer unit according to the present invention,
13 and 14 are conceptual diagrams showing the first material transfer means of the first transfer means according to the present invention,
Fig. 15 is a conceptual view showing a second material transfer means of the first transfer means according to the present invention,
16 is a conceptual diagram showing a second conveying means according to the present invention,
17 and 18 are perspective views showing gas waste storage means according to the present invention,
19 and 20 are perspective views showing liquid waste storage means according to the present invention,
21 is a perspective view showing a gas compression storage means according to the present invention;

Hereinafter, an integrated process facility for producing a useful radionuclide from a fission product according to the present invention will be described in detail with reference to the accompanying drawings.

As shown in FIGS. 1 to 21, an integrated process facility for producing useful radionuclides from a fission product according to the present invention comprises

A hot cell bank unit 30 for producing radioactive isotopes from neutron irradiated low enriched uranium (LEU) irradiated targets and a neutron irradiation target for radioactive isotope production from outside or from a reactor into a hot cell bank unit And a transfer unit for transferring.

First, the integrated process facility according to the present invention is constructed to have a layered structure in which structures 'Level +1', 'Level 0', 'Level -1' and 'Level -2' are sequentially arranged from the top to the bottom.

First, 'Level +1' is provided at the upper part of the hot cell bank unit as shown in FIG. 3 so as to enable work or a railing for preventing the fall of the object. The nuclear material management area and the chemical storage , An assembly room for manufacturing and testing, and the like.

In addition, a large-capacity crane is installed at the upper part to enable transfer of equipment, devices, and goods.

In addition, in the 'Level 0', 'Level -1' and 'Level -2', the integrated process facility according to the present invention is arranged.

4, the hot cells of the hot cell bank unit described below are arranged, a transfer device and a space for transferring the material are arranged in the lower part of the hot cells, do.

As shown in FIG. 5, a water pool, a hot cell for target transport, a gas and liquid waste storage means, and the like are disposed in 'Level -1', and a transfer device and a space are disposed for transferring materials and various wastes.

6, a water tank management system, a solid and liquid waste storage means, and the like are disposed at 'Level-2', and a transfer device and a space for transferring various wastes are disposed.

The transfer unit according to the present invention is not intended for transfer or discharge from a hot cell to another hot cell and is intended for transferring an irradiation target from an external or reactor structure to an integrated process facility for the production of radioisotopes.

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The first hot cell of the integrated process facility according to the present invention is connected to an in-pool elevator which is a transfer unit installed in a passage connected to the reactor to move the neutron irradiation target to the receiving hot cell installed at 'Level 0' .

The tablet elevator 11 is installed at 'Level -1' and is configured to be transferred between the hot cell and the water pool 21 so that the target is transferred from the hot cell to the neutron irradiation position, or conversely, the neutron irradiation target It is used to transfer from the water pool to the hot cell.

In the receiving cell, a conveying device such as a crane (C) is installed on the upper part for conveying and installing materials and equipment.

That is, the transfer unit according to the present invention enables the transfer of the radioisotope target directly from the reactor to the process facility through the material transfer fan elevator directly connected to the integrated process facility when the water pool of the reactor facility is directly connected thereto.

The transfer unit may be configured to install a transfer hot cell 16 so as to isolate the service pool (not shown) of the reactor building or the water pool of the integrated process facility as needed.

The transfer hot cell is installed so as to be connected to the service space of the reactor facility or the ship space of the material conveyed from the other facility. In this transfer hot cell, a plant elevator connected to each water pool is installed. And a crane (C) for lifting and lowering the object from the lower part of the hot cell to the upper part.

Conventional fission product production facilities are located at remote sites or near nuclear reactors, but they are installed in adjacent areas. However, when transporting neutron irradiation targets when they are installed in isolation, shielded containers such as lead And then transferred into the building. Then, the radioactive isotope is removed by chemical treatment.

That is, since the existing production facilities are physically separated from the reactor, it is difficult to ensure a sufficient shielding performance in transferring the irradiation target, and a separate shielding body must be introduced.

In order to solve this problem, the transfer unit 10 according to the present invention makes it possible to transfer the irradiation target from the reactor directly to the process facility while ensuring a sufficient shielding performance, so that the conventional problems can be solved at once.

Particularly, as shown in Figs. 1, 2, 11 and 12, the transfer unit 10 is provided with the transfer hot cell 16, the water pool 21 or the water pool 21 to the receiving hot cell 31 There is provided a toll elevator 11 for conveying the material.

The inflator elevator 11 includes a liner 12 formed on the water pool 21 and a raising and lowering rail 13 mounted on the liner 12 and a cart 14 moving along the raising and lowering rail 13 (15) provided on the liner (12) and the lifting / lowering rail (13) and capable of detaching and attaching each other.

The liner 12 is disposed in an inclined form inside the water pool 21 and is installed on the ascending and descending rail 13 on the inclined surface of the liner 12. The liner 12 is supported by the cart 14 along the ascending and descending rail 13, To move the material upward and downward.

The ascending / descending rail 13 can be constituted by an equilateral rail such as a monorail or a train line.

In this case, a pair of guides 14a connected to the raising and lowering rails 13 and moving along the raising and lowering rails 13 are provided below the cart 14, and friction is minimized in the lower portion of the rails 14a A roller 14b is provided in the inward direction to facilitate transportation,

Guide grooves for the rollers 14b of the guide 14a are formed on both sides of the ascending and descending rail 13 so that the stability of the cart 14 can be ensured when the cart 14 is moved.

At this time, the cart 14 is configured so that the guide 14a can be separated from the upper end or the lower end of the raising and lowering rail 13, so that the cart 14 can be easily and conveniently separated from the raising and lowering rails 13, Replacement is also easy and easy.

The lower surface of the cart 14 is provided with an inclined portion 14c corresponding to the inclined surfaces of the liner 12 or the elevating and lowering rails 13 so that the cart 14 can maintain the vertical state when the material is transported, So that it can be smoothly formed.

The coupling means 15 is provided with a mounting portion 15a formed by bending the upper end of the elevating and lowering rail 13 in order to avoid the joining structure such as welding, bolting or the like between the elevating railing rail 13 and the liner 12 And the upper surface of the liner 12 is formed in the mounting groove 15b so that the mounting portion 15a can be inserted or mounted.

This is preferable not only for ensuring the integrity of the liner 12 used during the lifetime of the facility but also for facilitating the maintenance of the transport raising and lowering rail 13.

Therefore, the lifting and lowering rail 13 can be easily installed on the liner 12 by the coupling means 15, and the disassembling operation can be performed easily and easily.

The filler elevator may be constructed of a liner 12 formed in a water pool connected to a hot cell and a cart moving along the liner. In this case, the cart is provided with a roller attached to the liner so as to minimize friction, can do.

Here, the hot cell connected with the water pool and the liner is constructed so that a closed door is installed on the bottom surface of the hot cell to prevent mixing of air between the spaces. If the water level of the water pool is not maintained at a certain level or more, .

Furthermore, the radioactive isotope index can be transferred to the hot cell bank unit through various paths,

For example, from the service pool of the reactor to the hot cell bank unit via the inflator elevator, or to the hot cell valve unit by sequential transfer through the service pool of the reactor, the inflator elevator, the water pool, and the inflator elevator.

In addition, the radioisotope questionnaire can be transferred to the hot cell bank unit by sequential transfer through the service pool of the reactor, the inflator elevator, the transfer hot cell (transfer unit), and the inflator elevator.

In addition, it is possible to transfer the radioisotope survey table to the hot cell bank unit through the hot cell (transfer unit) and the blow-up elevator for transfer.

That is, as described above, the path for transporting the radioisotope target to the hot cell bank unit can be configured in various ways, thereby enabling more efficient operation of the apparatus.

As shown in FIGS. 1 and 2, the water pool 21 according to the present invention is for storing a neutron irradiation league and an irradiation target for radioisotope production. The water pool 21 is connected to a purifying system 23 are provided.

As shown in FIGS. 1 and 2, the hot cell bank unit 30 according to the present invention produces a radioactive isotope from a neutron irradiated low enriched uranium (LEU) irradiation target.

For this purpose, 'Level 0' includes Receiving Hot Cell 31, which is configured to allow the target to be taken in and out to accommodate the neutron irradiation league or neutron irradiation target; and,

A dissolution hot cell 33 for filtering and treating the generated solid waste after dissolving the neutron irradiation target and the target of the generated inert gas and the neutron irradiation target when the neutron irradiation target is dissolved; and,

Purification Hot Cell (35) for separation and purification of useful radionuclides; and,

And a Bulk Source Hot Cell 37 for dispensing with a required amount of the solution. .

In addition, if necessary, a transfer hot cell 39 (Transfer Hot Cell) may be installed.

The hot cell bank unit 30 is configured such that the receiving hot cell 31, the descaling hot cell 33, the hot cell for refining 35 and the bulk source hot cell 37 are divided into functional and continuous functions, This makes it possible to construct a high facility, whereby the mechanical operation and the chemical treatment can be performed easily.

Each hot cell has a structure in which a tunnel (T) is provided to prevent the diffusion of contaminants from the hot cell when the one cell is opened so that the other cell can not be opened. And is configured to take negative pressure where there is a high risk due to the amount of radiation being treated, radiation level, or radiation leakage. In order to prevent the diffusion of contaminants, the negative pressure between each of the hot cells is preferably set to be the lowest of the solution hot cell, followed by the hot cell for purification, the receiving hot cell, and the bulk source hot cell.

Each hot cell of the hot cell bank unit 30 according to the present invention is composed of lower cells arranged in a multi-layer structure so as to facilitate the transfer of the material and the management of the waste.

That is, a structure is provided so that facilities such as the one shown in FIG. 1 can be disposed therein, and is configured to perform the functions as described in FIG.

At this time, each hot cell of the hot cell bank unit 30 is disposed in 'Level 0' as described above, and various kinds of waste are stored in the lower cells formed at 'Level -1 and Level -2' A transfer device for transferring the waste, a processing facility, and the like are provided.

1 and 2, the receiving hot cell 31 of the hot cell bank unit 30 according to the present invention includes an irradiation rig loaded with a neutron irradiation target (for producing radioactive isotopes, uranium Lt; RTI ID = 0.0 > and / or < / RTI > containing target).

The receiving rig 31 and the irradiation rig 11 stored in the water pool 21 are transported to the receiving hot cell 31 by the tow elevator 11 by being connected to the tow elevator 11.

A crane C is provided above the receiving cell 31. The crane C is movable in three axes in the x, y, and z axes to facilitate the transfer of the material in the hot cell.

In addition, a gas compression storage means 70 for responding to an accidental discharge of an inert gas generated during a process operation or a hot cell 31a for target transport is provided below the receiving hot cell 31. [

Here, the hot cell 31a for target transfer will be described first. The hot cell 31a for target transfer is provided with a target cutting device for disassembling other neutron irradiation targets except the fission generating radioactive isotope, Or a receiving device for transferring a required material including a neutron irradiation target to the receiving hot cell 31 is installed.

The target hot cell 31a is provided with a drawing device for drawing out the radioactive isotope production material by cutting the neutron irradiation target and a double blocking type drawer D for drawing and discharging necessary materials into the hot cell Respectively.

The conveying device and the drawing device are selected and used as needed among the first and / or second material conveying means or the second conveying means of the first conveying means described below.

In this case, it is desirable that the transfer device, the drawing device, and the double barrier type drawer D are provided with an interlock function so as to suppress the external emission of the radioactive material, thereby enhancing the radiation safety.

A space is formed in the hot cell 31a for target feeding so that a cascade (CA) (cask) can be dug. Above this space, a double-block type direct-current transport system, that is, a second transport means 90 And a double shielding type drawer D is disposed on one side of the cascade (azimuth) azimuth zone for inputting and discharging a specific material.

The material transfer from the rebasing hot cell to the hot cell 31a for target transfer is carried out by the first material transfer means 80 of the first transfer means or by the second material transfer means 100 or the second transfer means 90 In this case, when the moving distance between the receiving hot cell 31 and the target hot cell 31a is long, the first material conveying unit 80 or the second material conveying unit 100 of the first conveying unit is applied And when the moving distance is short, the second feeding means 90 is introduced.

However, the first material conveying means 80, the second material conveying means 100 or the second conveying means 90 should be constructed so as to prevent air entrainment between the respective cells, Will be described in more detail.

Next, the gas compression storage means 70 as shown in FIG. 21

It is a radioisotope generated during the process operation and is connected to the receiving hot cell and / or the solution hot cell in response to the accidental release of the inert radioactive gas, and is activated upon leakage of the inert gas radioactive material.

That is, the gas compression storage means may be a receiving hot cell in which an inert radioactive material is present and a situation such as a breakage of a neutron target for FM production, melting of an FM production target, The inert gas radioactive material generated when the gas radioactive material having a normal operating level or higher is leaked due to the occurrence of an abnormal situation in the decomposition hot cell 31 and the decomposition hot cell 33 is compressed and stored.

When the abnormal gas radioactive material flows out, the exhaust system of the hot cell is stopped first and the discharge to the external environment is inhibited. Then, the valve connected to the storage tank, which is maintained at a negative pressure, is opened, The air is directly sucked in, and after a certain negative pressure is formed, the air inlet is opened so that the hot air can enter the hot cell, and the pressurizing storage pump is operated to extrude and store.

The gas compressing and storing means 70 includes a piping 71 connected to the receiving hot cell 31 and the descaling hot cell 33 and a storage tank connected to the piping 71 for compressively storing the inert gas ST), and the pipe 71 and the storage tank are installed at the lower part of the hot cell because the density of the inert gas is larger than that of air.

In this case, a pump or other device is provided for forced inhalation of the inert gas, and the storage tank (ST) is operated under the reduced pressure state so that measures can be taken to bring the radioactive gas into the storage tank .

In addition, the gas compression storage means 70 is installed in parallel to ensure safety, so that it can be prepared for the failure of a pump or a storage tank and can be taken immediately in case of an accident. Thus, It is possible to increase the safety of the process.

Next, as shown in FIGS. 1 and 2, the solution solution hot cell 33 of the hot cell bank unit 30 according to the present invention is used to dissolve the neutron irradiation target, to collect the inert gas generated upon dissolution, And process equipment to filter and remove solid waste containing dissolved nuclear material.

First, the di-solution hot cell 33 is connected to the receiving hot cell 31 by a tunnel T in which the material transfer system between the hot cells is installed.

In this case, the tunnel T may be provided with two through-holes inclined in different directions for the inclined path transfer, or a material transfer system capable of transferring the materials to each other may be installed.

In order to prevent cross contamination between the receiving hot cell 31 and the decomposition hot cell 33 when the material is moved through each of the through-holes, an interlocking system in which one side is normally opened and the other side is not opened .

If necessary, the negative pressure is kept low to prevent complete cross contamination. Using a decompression device to prevent leakage during operation of the radioactive gas, induce air movement toward the decomposition hot cell (33), which has a high radiation level and is equipped with a safety system. .

In the inside of the di-solution hot cell 33, process equipments necessary for dissolving, filtering and chemical treatment including a melting tank 33a for dissolving a neutron irradiation target are installed.

The gaseous waste storage means 40 is connected to the lower part of the degas solution hot cell 33 to collect and store the radioactive gaseous waste (inactive radioactive gas) generated during the dissolution process, and to store and store the gaseous waste.

The liquid waste storage means 50 is connected to store the liquid waste according to the radiation level (middle level, low level) generated during the dissolution process occurring during the operation of the di-solution hot cell 33.

At the lowermost end of the receiving hot cell 31 and / or the lower side of the decomposition hot cell 33, 'Level -2', a monolith for storing and storing high level solid radioactive waste, which is a filter cake produced after target dissolution, ) Solid waste storage means 60 is connected.

The solid waste storage means 60 is kept below constant temperature and constant humidity, and is provided with a shield cap which is movable to a crane with respect to each monolith storage hole so that the surface dose rate and the air dose rate can be maintained below a certain level Respectively.

The transfer of the filter cake generated in the degaussing hot cell 33 is performed by the first material conveying means 80 of the first conveying means using the motor or the second material conveying means 100.

In order to prevent air mixing between the decomposition hot cell 33 and the solid waste storage means 60 during the transfer of the filter cake by the first substance transfer means 80 or the second substance transfer means 100, It is preferable that the direct downward transfer passage TP can be ensured.

In order to store solid waste in the form of a filter cake in a monolith installed in the solid waste storage means 60, a sealable double vessel is used.

The solid waste storage means 60 may contain filter cakes produced by filtering during the melting process and may be packed in a primary container (filter cake storage container) which is not destroyed by corrosion or erosion during storage A system for making a filter cake storage vessel and a system for making the filter cake as a secondary vessel in which several filter cakes are stacked in a vertical direction all at once are constituted.

Also, in the case of a filter cake storage container which is a primary container, a system capable of forced cooling is provided to cool heat (decay heat) generated by radioactive decay. To this end, a filter cake cooling container is installed, and a cooling pipe for cooling by pneumatic cooling or circulating cooling solvent is installed, and a temporary storage space for a filter cake storage container equipped with a cooling system is provided.

The sealing of the filter cake storage container as the primary container is attenuated to a level that does not affect the integrity of the container due to the decay of the nuclide which changes into gas or inert gas due to radioactive decay to a certain level or more, And a pinhole is formed on the side surface so as to be sealed.

The filter cake processing system includes a filter cake storage container capable of storing a batch scale which is processed once to produce a radioactive isotope, and a rotatable up and down movable container for welding and sealing a plurality of storage containers. A sealing welder is provided for welding the table and the sides of the container. In the case of the container, the material is configured to be transportable and the material and the sealing method suitable for the sealing method of the sealing device installed.

In addition, the solid waste storage means 60 is provided with a crane capable of moving in three axes in order to store the filter cake storage containers into a plurality of vertical holes 61a formed in the monolith,

As shown in Fig. 7, there are provided a conveying rail 63 and a conveying carriage 65 for conveying the filter cake container container and the charging cask to the rear management space of the hot cell, and various solid materials.

It is preferable that the charging cylinder is first mechanically fastened and secondarily sealed by welding as will be described below.

Various methods can be used as the welding method, but the TIG welding method is preferable.

As shown in FIGS. 1 and 2, the hot cell 35 for purification of the hot cell bank unit 30 according to the present invention can separate and purify the useful radionuclide by the difference in solubility of the target substance by chemical substances using various columns So that the primary, secondary and tertiary stepwise purification processes are carried out.

The hot cell for purification 35 is connected to the decomposition hot cell 33 by a tunnel T and a material transfer system for transferring the inclined path ), And through-holes for providing tubes for transferring the solution and the gas (including those containing radioactive isotopes)

A double cut-off type drawer (D) is installed under the refill hot cell (35), and the column and the material required during the refining process are transferred into the hot cell.

Further, a space in which a cask (CA) capable of transporting the radioactive material can be inserted is secured in the lower portion of the hot cell, and the space for installing the cask (CA) Is connected by an installed transfer passage (TP)

The hot cell 35 for purification is connected to the reservoir 51 of the liquid waste storage means 50 by a transfer pipe P for transferring the liquid waste generated during the process operation.

As shown in FIGS. 1 and 2, the bulk source hot cell 37 of the hot cell bank unit 30 according to the present invention is configured to be able to be divided into a radioactive amount of a solution required to dispense the solution type radioactive material.

The bulk source hot cell 37 is connected to the hot cell 35 for purification by the tunnel T and is connected to a material transfer system (a mutual ramp transfer passage or a hot cell transfer system ) And a through-hole for installing tubes for transferring the solution and the gas (including the radioactive isotope).

Further, a double-cut type drawer (D) is provided under the bulk source hot cell (37) to transfer the material required in the process,

In addition, a space is provided in the lower part of the bulk source hot cell 37 to accommodate a cask (CA) capable of transporting the radioactive material. The space for installing the cask (CA) Is connected to a transfer passage (TP) provided with a material transfer system,

A system for measuring the radioactivity of the required solution and a radioactive dose measuring device (DC) (Dose Calibrator) are provided.

Also, the bulk source hot cell 37 is connected to the promoting tank 51 of the liquid waste storage means 50 by a transfer pipe P for transferring the liquid waste generated during the process operation.

1 and 2, the hot cell bank unit 30 according to the present invention is provided with a transfer hot cell 39 (transfer hot cell)

The transfer hot cell 39 is a material transfer system (mutual ramp transfer path or hot cell material transfer system) that enables slant movement to the bulk source hot cell 37 and the tunnel T, (Including those containing radioactive isotopes) are provided.

In addition, a space is provided in the lower part of the transfer hot cell 39 so that a cask (CA) capable of transporting the radioactive material can enter. The space for installing the cask (CA) Is connected to a transfer passage (TP) provided with a double-blocked material transfer system,

In the lower part, a double blocking type drawer (D) is installed to transfer the material required in the process.

Furthermore, in order to prevent the diffusion of contamination between each hot cell, when the substance is sent from a high radiation level to a low radiation level, the air movement is induced to a place where the radioactive substance is treated at a high level. In addition, a vacuum pump system connected to a filter can be constructed and operated to prevent diffusion of contamination and cross contamination between material transfers.

In addition, all of the hot cells are provided with a leaky liquid waste collection tank, which is shielded from the hot cell bottom and has radiation safety, so that they can be collected in one place in case of leakage of liquid waste in the hot cell due to an accident during operation.

The liquid waste is configured to be installed externally and has a discharge tube at the lower portion of the vessel for transferring the contents of the liquid waste to another container.

13 to 15, in some or all of the hot cells of the hot cell bank unit 30 according to the present invention, the first transfer means for transferring the material between each of the hot cells and the lower cells is connected to the first material transfer means 80) and / or second material transfer means.

First, as shown in FIGS. 13 and 14, the first material transporting means 80 of the first transporting means is manufactured in the form of an elevator in which a transporting body is applied and a wire transporting method or an LM guide method is applied.

The first material conveying means 80 is configured to be capable of transferring the material between the receiving cells of the hot cell bank unit 30 and the descaling hot cells 33,

In contrast, when hot cells are required to transfer materials to the lower cells, they can be introduced.

The first material conveyance means 80 according to the present invention includes a first conveyance pipe 81 connecting each of the lower cells and having a plurality of first inlet and outlet 81a, To discharge the radioactive material including contaminated air in the first conveyance pipe 81 to prevent cross contamination between hot cells connected to the first inlet and outlet 81a after being opened and closed And a second discharge portion 83 connected to the pump.

The first conveying pipe 81 of the first material conveying means 80 is provided with a guide bar 84 connected to the first housing 82 to guide the lifting and lowering operation of the first housing 82 ,

The first inlet port 81a of the first material transfer means 80 is disposed at the upper and lower portions of the first transfer pipe 81 and the first inlet port 81a is provided with a side opening type or a door (85) is provided to open / close the first inlet / outlet (81a).

The first conveying unit 82 of the first material conveying unit 80 is provided with a first conveying plate 82a which can horizontally draw in and out from the floor, So that they can be drawn out and / or drawn out in a stepwise manner.

The first discharge portion 83 of the first material transfer means 80 includes a first discharge pipe 83a connected to the upper portion of the first transfer pipe 81; And the first inlet 81a is opened and closed by the door 85 for transferring the material and then the radioactive material existing in the first transfer tube 81 is introduced into the first inlet pipe 81a, A first pump 83b for providing a pumping pressure so as to suck it out; .

Therefore, the first material conveying means 80 not only transports the material between the receiving cells and the descending hot cells 31 and / or the descaling hot cells 33, but also the inside of the first conveying pipe 81 It is possible to prevent mixing of air between the hot cells and the lower cells to prevent cross contamination between hot cells due to radioactive substances.

15, in the hot cells of the hot cell bank unit 30 according to the present invention, the second material conveying unit 100 of the first conveying unit is moved in a different manner between the adjacent hot cells and the lower cells Respectively.

The second material conveying means 100 is manufactured so as to be able to convey using the second housing 101 by means of electrically driveable wires such as a winch or a hoist,

The second housing 101 is provided with an opening / closing door 101a to enable material transfer,

It is preferable that the opening and closing door 101a has a hermetic structure so that airtightness can be maintained.

The second material transferring means 100 is configured to transfer the material between the receiving cells 31 and the descaling hot cells 33 of the hot cell bank unit 30,

In contrast, when hot cells are required to transfer materials to the lower cells, they can be introduced.

The second material conveying means 100 according to the present invention includes a second inlet 101a connecting the lower cells and constituting a conveying passage of the second enclosure 101 and having a door 103a operable by a remote controller, A second conveyance pipe 103 having an outlet 103b and a second conveyance pipe 103 for preventing cross contamination between the hot cells connected to each other after opening and closing the second inlet and outlet 103b, And a second discharging unit 105 connected to the second pump 105b to discharge the radioactive material.

The second material conveyance means 100 is provided with a second conveyance plate 107 capable of pulling in and out of the second enclosure 101 in the horizontal direction on the bottom of the second conveyance pipe 103, The door 107 is folded when the door 103a is closed, and when the door 103a is opened, it forms a certain angle while being unfolded, thereby facilitating the entry and / or withdrawal of the transfer container 101. [

At this time, the door 103a is provided with a door of the ascending / descending type or the side opening / closing type or the door of the down type opening / closing type.

The second discharge portion 105 of the second material transfer means 100 is connected to the second discharge pipe 105a connected to the upper portion of the second transfer pipe 103 and to the second discharge pipe 105a And a second pump 105b that opens and closes for material transfer and provides a pumping pressure to suck up the radioactive material present in the second transfer pipe 103.

Accordingly, the second material conveying means 80 not only transports the material between the receiving cells and the descasing hot cells 31 and / or the descaling hot cells 33, but also the inside of the second conveying pipe 103 It is possible to prevent air mixing between the hot cells and the lower cells to prevent diffusion of contamination and cross contamination between the hot cells due to inflow of the radioactive material.

16, in some or all of the hot cells of the hot cell bank unit 30 according to the present invention, near-vertical transfer of the target for radioisotope production and transfer of the target including the radioisotope product to the outside of the hot cell And a second conveying means 90 for conveying the sheet.

The second conveying means 90 is provided with a guide pipe 91 for guiding the conveyed article and a valve 93 for conveying the conveyed article moving through the guide pipe 91 downward.

In this case, the valve 93 is constituted by an actuator 93a and an opening / closing port 93b operated by the actuator 93a. At this time, the opening / closing port 93b is provided with a through hole 93c, When the through hole 93c is rotated and arranged in the vertical direction, the transported article is transported downward through free fall by its weight.

The actuator 93a may be a pneumatic actuation type or an electric actuation type.

In addition, the valve 93 of the second conveying means 90 is vertically arranged to operate at different times to prevent mixing of air between the cells when conveying the articles, or to prevent air mixing between the hot cells and the outside . If necessary, a small-sized pump may be installed to discharge air in an area of the middle part of the upper and lower valves, and then discharged through a pipe located at the upper end of the valve installed at the upper part.

The second conveying unit 90 is configured to be installed, maintained, and replaced from the outside of the hot cell.

The first material transfer means 80 and / or the second material transfer means 100 and the second transfer means 90 of the first transfer means according to the present invention can transfer the transferred object, particularly the possibility of breakage and the transfer of the target Depending on the distance.

In the case of the second conveying means 90, since the conveyed article moves in a free fall manner by gravity, it is determined according to the movement distance and the size of the floor area of the conveyed article.

This is because, if the moving distance is long, a problem such as an impact on the article may occur, so that it is preferable to be able to be introduced when the moving distance of the target is short.

Therefore, when the distance of travel is long, the article is transported by using the first material transporting means 80 and / or the second material transporting means 100 of the first transporting means applying the elevator system or the wire transporting system, It is preferable to allow the article to be transported by using the second conveying means 90 in which the free fall method is introduced.

Meanwhile, the hot cell bank unit 30 according to the present invention is provided with a plurality of storage means for storing gas, liquid, and solid waste as described above. Hereinafter, these storage means will be described in detail.

First, as shown in Figs. 1, 2 and 17, the gas waste storage means 40 is disposed below the decomposition hot cell 33 and connected to the dissolution tank 33a, and collects the radioactive inert gas generated during dissolution And is stored in a plurality of storage tanks (ST). After being filled once, it is stored for a predetermined time for sufficient damping and discharged when it meets the discharge standard.

In this case, a predetermined number of storage tanks ST are arranged in the storage tank 41 formed below the decomposition hot cells 33.

In addition, an electric drive valve control system or a pneumatic actuated valve control system (PAVS) is applied to each of the storage tanks ST of the gaseous waste storage means 40 to allow the gas to flow in and out.

The system is structured so that the operation of the valve and the level of radiation (surface dose rate), the pressure of the storage tank and the inflow timing to the formal tank can be managed. In case of a problematic container, A control system is configured to prevent the entry and exit from proceeding.

A vacuum pump capable of crossing operation is installed for the introduction and discharge of the radioactive gaseous waste, and a system capable of managing such radioactive gaseous waste is installed in such a manner that the floor is shielded so that sufficient shielding can be performed at the upper part of the storage tank Reference).

In addition, as shown in FIG. 18, it is preferable that the storage tank 41 is provided with a shielding door 43 to improve the shielding performance.

The arrangement of the storage tanks is arranged according to the arrangement of the spaces taking into account the way of shielding horizontally or vertically, and the capacity of each storage tank (ST) is determined in proportion to the amount of gas used, the volume of the vessel and the piping .

The storage tank (ST) is divided into a shielded zone and a shielding unit connected to the storage tank so that the storage tank can be detached from the outside so that the problem can occur or the surface dose rate at which replacement operation of the storage tank, Respectively.

The discharge from the storage tank (ST) is a forced discharge mode which blows the carrier gas to the top of the storage tank (ST) to be discharged through the pipe inserted deep into the storage tank (ST) It is discharged to the pipe connected with the hot cell or the filter bank of the hot cell, and purified and discharged through the multi-stage filter.

The storage tank (ST) discharged by using a carrier gas is sufficiently decompressed by a vacuum pump to be formed in a vacuum so that it can be used in the operation of the next process.

In order to distinguish according to the storage period, several storage tanks are divided so as to be shielded so that the storage tanks can be easily repaired or replaced in case of trouble or trouble.

The liquid waste storage means 50 according to the present invention as shown in Figs. 1, 2 and 19 is connected to the decomposition hot cell 33, the refining hot cell 35 and the bulk source hot cell 37, A plurality of storage tanks 51 for storing the intermediate level and low level liquid waste are provided so as to separate the radiation level of the waste and the acid salt group and a plurality of storage tanks ST are built in each of the storage tanks. The bottom of the storage tank can be operated by attaching a replaceable container to collect sludge and sediment.

The capacity of the storage tank (ST) may vary depending on the setting of the storage period for the radiation operator's radiation attenuation, but it is appropriate that it can be stored for more than 90 days (90 to 110 days) per tank based on the amount of generation.

For example, when the storage capacity of the storage tank is 50 liters / week, the storage capacity of the storage tank is 700 liters, and the storage tank having the inner diameter of 80 cm is 150 centimeters in height.

The waste storage space is divided into two layers, a 'Level -1' layer disposed under each hot cell, and a 'Level -1' layer disposed under the 'Level -1' layer in order to improve space utilization and ensure radiation safety. 'Level-2' is preferable because it is possible to secure a sufficient storage space without additional shielding.

The last storage unit for storing sufficiently damped radioactive materials can be constructed with a sump-type storage tank that utilizes the space as much as possible to secure a sufficient storage capacity.

Sump type storage tank should be constructed so that the lid installed on the upper part of the storage tank can be opened so that the pipe connected to the pump can be connected from the outside to the storage tank in order to extract the solution from the outside. The induction tube is configured to be installed,

At this time, when the induction tube is installed, the through-hole communicating with the outside is configured to be opened from the outside, and a cap having a sufficient shielding function is provided. The cap with a shielding function can be composed of a shielding mage and an outer mage to ensure the efficiency and safety of shielding and sealing.

The liquid waste storage tank storage space (installation space) is configured to have a slope so that the solution does not stay on the bottom when an accident such as breakage of the storage tank occurs. It is a tube that penetrates each layer and is installed to allow the solution from each layer to come in. (Last storage area) is composed of sink sink to enable discharge to the outside. The ThinkPad should be configured so that the aforementioned emission methods can be applied.

Also, as shown in FIG. 20, the storage tank ST is provided with an agitator AG to homogenize the concentration of the substances stored in the storage tank by mixing and stirring to prevent the concentration from dropping below a certain level, Management.

1, 2, 6 and 7, the solid waste storage means 60 stores and stores the high-level solid radioactive waste, which is the filter cake produced after the target dissolution,

To this end, the solid waste is provided with a reservoir 61 in which a monolith type storage tank ST is built, and a triaxially movable crane C arranged in the reservoir 61.

In addition, a crane (C) is installed in the upper space of the reservoir (61), and a manipulator, a lead window, and a sliding door are configured to transport the filter cake containing container to a specific area in the reservoir A transfer module 63 is disposed.

In this case, the transfer of the filter cake, which is a high-level solid waste, from the di-solution hot cell 33 to the solid waste storage means 60 is performed by the first and second mass transfer means 80 and 100 of the first transfer means, And the filter cake thus transferred is conveyed to the reservoir 61 through the manipulator, the lead window, and the sliding door, and is stored and stored.

The reservoir is provided with a filter cake storage container for storing the filter cake mentioned above and a charging cage for storing a plurality of filter cake storage containers and a system for welding the filter cake storage container and the charging cask.

In this case, the charging cask is provided with a lid capable of closing the upper portion, so that the filter cake storage container is stacked as much as desired in the charging cask, and then the charging lid is firstly joined by a screw- Respectively.

In addition, a solid waste reservoir 61 composed of a monolith can be installed on the rear side of the solid waste storage means 60 for storing and storing the solid radioactive waste including the filter cake charging / .

The plurality of monoliths provided in the solid waste repository 61 are provided with a plurality of vertical holes 61a as described above. In the vertical holes 61a, a plurality of filter cake storage containers, A solid radioactive waste having a high radiation level including a waste column and the like is accommodated.

In addition, the solid waste reservoir 61 is provided with a plurality of lower cells, in which a monolith is installed, the transfer rack 63 for transferring the filter cake storage container and / or the charging cask from the hot cell zone to the rear zone, And a transporting carriage 65 equipped with a transporting roller 65a for transporting the transporting rail 63 is installed and transported so as to store the waste. This transporting system can be utilized alternately by connecting to the opposite hot- .

The conveying carriage 65 is constructed so as not to be conveyed during conveyance and is mounted on the conveying rail 63 to facilitate installation, maintenance, and replacement.

In the solid waste repository installed at the rear edge, a crane capable of 3-axis operation is installed at the upper part so that the transferred solid waste can be stored in a desired hole of the waste repository, so that it can be stored separately according to the kind and level of the material, A space for loading into a transportation container is secured for transportation to a place.

The hot cell exhaust system required for operation of the hot cell is constituted, which is installed separately from the level and the risk.

Such an exhaust system is provided with a filter bank that is configured to be used in accordance with the characteristics of the emitted gaseous radioactive material, and is configured to manage the release of the radioactive material to the external environment during operation of the facility.

Furthermore, all hot cells are rearwardly placed with double-blocked doors to prevent the release of radioactive material.

In addition, as shown in FIG. 10, a space for work is formed in each layer of the hot cell bank unit,

This work space is formed in the passageway 3, the railing 1, and the stairs 5, so that convenience and safety of the work can be ensured. In order to facilitate the installation and transportation of equipment and objects, the railing is constructed so that the railing can be opened adjacent to the entrance so that the convenience of the material transfer operation is secured.

While the present invention has been described with reference to specific embodiments thereof, it will be apparent to those skilled in the art that various modifications and variations can be made in the present invention without departing from the spirit and scope of the invention. Modifications and variations should be construed as being included within the scope of the present invention.

C: Crane CA: Cask
TP: Double pass type direct feed path ST: Storage tank
AG: Stirrer T: Tunnel
P: Transfer tube D: Double blocking drawer
DC: Radioactivity measuring device PAVS: Valve control system
AG: stirrer
1: railings 3: passage
5: Stairs
10: Feed unit
11: Flour elevator 12: Liner
13: ascending / descending rail 14: cart
14a: guide 14b: roller
14c: inclined portion 15: engaging means
15a: mounting portion 15b: mounting groove
16: Hot cell for transport
20: purification system
21: Water pool
30: Hot cell bank unit
31: Receiving hot cell 31a: Hot cell for target transport
33: di-solution hot cell 33a:
35: Hot cell for refining 37: Bulk source hot cell
39: Transfer Hot Cell
40: Gas waste storage means
41: Retention tank mounting portion 43: Shielding door
50: liquid waste storage means
60: Solid waste storage means
61: Solid waste storage 61a: Vertical hole
63: rail 65: carriage
65a: Feed roller
70: gas compressed storage means
71: Piping
80: first material conveying means
81: first conveyance pipe 81a: inlet port
82: Enclosure 82a: First conveying plate
83: first discharge portion 83a: first discharge tube
83b: first pump 84: guide bar
85: Door
90: second conveying means
91: guide tube 93: valve
93a: Actuator 93b:
93c: Through hole
100: Second material conveying means
101: conveying container 101a: opening / closing door
103: second conveyance pipe 103a: door
103b: inlet / outlet 105: second outlet
105a: second discharge pipe 105b: second pump
107: second conveyance plate

Claims (24)

A hot cell bank unit for producing a radioactive isotope from a neutron irradiated fission target,
The hot cell bank unit includes:
A Receiving Hot Cell configured to allow entry and exit of a target to receive a neutron irradiation rig or a neutron irradiation target,
After dissolving neutron irradiation target and dissolution of neutron irradiation target, the generated inert gas and neutron irradiation target, a dissolution hot cell for filtration treatment,
Purification Hot Cell for separation and purification of useful radionuclides,
And a bulk source hot cell for dispensing with a radioactivity amount of the required solution,
Characterized in that one side of the bulk source hot cell is filled with a required amount of radioactive solution and further comprises a transfer hot cell for packaging.
The method according to claim 1, wherein
Neutron irradiated fissionable survey table An integrated process facility for producing useful radionuclides from fission products characterized by a low uranium containing target.
The method according to claim 1,
Wherein the facility for managing gas, liquid, and solid radioactive waste generated in the production of radioactive isotopes by utilizing the hot cell bank unit is integrated with a hot cell bank unit, and an integrated process facility for producing useful radionuclides from a fission product.
The method according to claim 1,
Further comprising a blower elevator for transferring a neutron irradiation target for radioisotope production from the service pool of the nuclear reactor building to the hot cell bank unit.
The method according to claim 1,
Further comprising a transfer unit for transferring the neutron irradiation target for radioisotope production from the outside or the reactor to the hot cell bank unit.
6. The method of claim 5,
Wherein the transfer unit further comprises a transfer hot cell disposed between the external or reactor facility and the hot cell bank unit. The integrated process facility for producing useful radionuclides from a fission product.
The method according to claim 6,
Further comprising a water pool connecting the reactor facility and the hot cell bank unit,
Characterized in that the water pool further comprises a toll elevator for transferring material. The integrated process facility for producing useful radionuclides from fission products.
8. A method according to claim 4 or 7,
A liner formed in the water pool,
A lifting rail mounted on the liner,
A cart moving along the elevating rail,
And an engaging means provided on the liner and the ascending / descending rail for enabling mutual detachment and attachment. The integrated process facility for producing a useful radionuclide from a fission product.
delete The method according to claim 1,
Further comprising a gas compression storage means for collecting and compressively storing the inert radioactive gas during the abnormal leakage of the inert radioactive gas during the fracture or dissolution of the neutron irradiated nuclear fuel material in the receiving hot cell or the dissolution hot cell, A process facility for producing a useful radionuclide from a fission product.
The method according to claim 1,
And a gaseous waste storage means connected to the dissolution tank of the dissolution hot cell, wherein the gaseous waste storage means further comprises a plurality of gaseous waste storage tanks for storing and attenuating an inert radioactive gaseous fission product, and a system for operating the gaseous waste storage tanks Wherein the fission product is produced from a fission product.
The method according to claim 1,
A plurality of reservoirs disposed at the bottom of the hot cell bank unit for storing and storing the filter cake,
And a solid waste storage means in the form of a monolith formed in the reservoir. The integrated process facility for producing useful radionuclides from fission products.
13. The method of claim 12,
Characterized in that the reservoir further comprises a system for cooling the filter cake and a solid waste treatment system for sealing and storing after sufficient cooling. The integrated process facility for producing useful radionuclides from fission products.
13. The method of claim 12,
The solid waste storage means is provided with a transfer rail for connecting the respective reservoirs for transferring waste,
And a transporting carriage for sliding the transporting rail is provided. The integrated process facility for producing useful radionuclides from the fission products.
The method according to claim 1,
Further comprising liquid waste storage means disposed below the hot cells of the hot cell bank unit and consisting of at least one layer. The integrated process facility for producing useful radionuclides from fission products.
16. The method of claim 15,
Wherein the liquid waste storage means is equipped with a plurality of storage tanks which are divided into acid bases and radiation levels. The integrated process facility for producing useful radionuclides from fission products.
The method according to claim 1,
In some or all of the hot cells of the hot cell bank unit, the lower cells are arranged,
Wherein the hot cell bank unit further comprises first transfer means for transferring material between each of the hot cells and the lower cells. 2. The integrated process facility for producing useful radionuclides from a fission product.
The apparatus as claimed in claim 17, wherein the first conveying means
A transfer pipe connecting the lower cells to each other and having a plurality of injection ports,
A housing which moves along the inside of the conveyance pipe,
And a discharging unit for discharging the radioactive material in the transfer pipe after opening and closing the charging port. The integrated process facility for producing the useful radionuclide from the fission product.
19. The apparatus according to claim 18, wherein the discharging portion of the conveying means
A discharge pipe connected to the transfer pipe,
And a pump connected to the discharge pipe for discharging the radioactive material in the transfer pipe. The integrated process facility for producing the useful radionuclide from the fission product.
The method according to claim 1,
Wherein some or all of the hot cells of the hot cell bank unit further include second transfer means for short-distance transfer of irradiation targets or material transfer to the outside of the hot cells. Process equipment.
21. The apparatus according to claim 20, wherein the second conveying means
A guide tube for guiding the conveyed article,
And a valve for transferring the transported material supplied through the guide pipe. The integrated process facility for producing the useful radionuclide from the fission products.
22. The apparatus according to claim 21, wherein the valve of the second conveying means
An actuator,
And an opening and closing port that is operated by the actuator and has a through-hole for the transported article. The integrated process facility for producing the useful radionuclide from the fission product.
22. The method of claim 21,
Wherein the plurality of valves are vertically disposed and operate at a different time from each other. The integrated process facility for producing useful radionuclides from a fission producing material.
8. The method of claim 7,
And a purification system is further provided in the lower part of the water pool. The integrated process facility for producing the useful radionuclide from the fission producing material.

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