KR102051577B1 - Apparatus and method for treating radioactive waste - Google Patents

Abstract

The present invention relates to an apparatus for treating radioactive waste, and more specifically, to an apparatus for treating radioactive waste, and a method using the same. According to one embodiment of the present invention, the apparatus for treating radioactive waste comprises: a grinding unit for grinding radioactive waste fed from the outside; a transfer unit including a plurality of transfer containers for storing the radioactive waste ground by the grinding unit and transferring the transfer containers along a predetermined transfer path; a radioactivity level measurement unit provided on the transfer path of the transfer containers, and configured to measure a radioactivity level of the radioactive waste contained in the transfer containers; a plurality of waste drums configured to receive and store the radioactive waste of which the radioactivity level measurement is completed from the transfer containers, wherein the radioactive waste are classified according to a radioactivity level; a sample collecting unit provided on the transfer path of the transfer containers, and configured to collect a portion of the radioactive waste fed into the waste drums from the transfer containers as a representative sample; and a control unit configured to receive a radioactivity level measurement result of the radioactive waste from the radioactivity level measurement unit and to control the transfer unit to feed the radioactive waste stored in the transfer containers to the waste drums corresponding to the result. According to the present invention, it is possible to efficiently select and treat the radioactive waste.

Description

Radioactive waste disposal apparatus and method {APPARATUS AND METHOD FOR TREATING RADIOACTIVE WASTE}

The present invention relates to a radioactive waste treatment apparatus and method.

Radioactive waste is generated during nuclear decommissioning, and radioactive waste can be divided into four levels: low level, low level, medium level and high level. Referring to Figure 15, the disposal method is different for each radioactivity level, the low and mid-level radioactive waste from the low level to "nuclear safety committee notification 2017-65 (regulation on radioactive waste classification and self-disposal standards)" "Can be delivered to and disposed of in a cave disposal facility.

For the treatment of radioactive waste, each radioactive waste needs to be sorted by level, and for the low and middle level wastes, the radiation characteristics based on the Notification of Nuclear Safety Committee 2017-60 (Medium and Low Level Radioactive Waste Delivery Regulation). Evaluation should be performed. For radiological evaluation, radionuclide concentrations for radionuclides in the following [Table 1] should be evaluated so that they can be classified into low level, low level, and low level.

Mid-level, low-level, and low-level radiation concentration limits Radionuclide Self-disposed radiation concentration limit (Bq / g) Very low level radiation concentration limits (Bq / g) Low level radiation concentration limit (Bq / g) H-3 100 10000 1.11E + 6 C-14 One 100 2.22E + 5 Co-60 0.1 10 3.70E + 7 Ni-59 100 10000 7.40E + 4 Ni-63 100 10000 1.11E + 7 Sr-90 One 100 7.40E + 4 Nb-94 0.1 10 1.11E + 2 Tc-99 One 100 1.11E + 3 I-129 0.01 One 3.70E + 1 CS-137 One 100 1.11E + 6 Whole alpha - 3.70E + 3

In order to ensure the reliability of such radionuclide concentration assessments, the samples used for evaluation must be representative of the packaging units in which the radioactive waste is packaged, and representative sampling should be preceded by each packaging unit. Generally, 200 L drums are used as such packaging units.

In the related art, a representative sample was collected after reopening a drum containing radioactive waste for sample collection. However, this conventional method may cause cross contamination during reopening process, resulting in inefficiency resulting in higher disposal costs.

In addition, it is fundamentally difficult to take representative samples from drums in which wastes of various radioactive levels are mixed.

In such a situation, research on representative sampling techniques and radioactive waste treatment technologies including the same, which can reduce disposal costs and enable reliable radionuclide concentration assessment, is required.

Korean Laid-Open Patent Publication No. 10-2018-0050016 (Published: 2018.05.14)

Embodiments of the present invention allow for the collection of samples that can clearly demonstrate representativeness from each radioactive waste packaging unit for reliable radionuclide concentration assessment, while efficiently and costlyly screening and selecting radioactive waste in terms of cost and time. It is an object of the present invention to provide a radioactive waste treatment apparatus and method.

According to an aspect of the present invention, a pulverization unit for crushing the radioactive waste introduced from the outside, a plurality of transfer containers for receiving the radioactive waste pulverized in the crushing unit, the transfer container is transferred along a predetermined transfer path A transfer unit configured to be provided on the transfer path of the transfer container, the level measurement unit measuring a radioactivity level of the radioactive waste contained in the transfer container, receiving and receiving the radioactive waste from which the radioactive level measurement is completed; A plurality of waste drums separated by radioactivity levels, a sample collection unit provided on the transfer path of the transfer container and collecting a portion of the radioactive waste introduced into the waste drum from the transfer container as a representative sample; and Level measurement of the radioactive waste from the level measurement unit A radioactive waste treatment apparatus may be provided that includes a control unit configured to receive a fruit and control the transfer unit to input the radioactive waste contained in the transfer container to the waste drum corresponding to the result.

In addition, according to another aspect of the invention, the first step of pulverizing the radioactive waste introduced into the crushing unit from the outside, the radioactive level of the radioactive waste contained in the second transfer container in the level measuring unit to measure the radioactive level In a second step, the radioactive waste of which the radioactivity level is measured is introduced into a collection hopper from a third transport container, and a representative sample is a representative sample of a portion of the radioactive waste that is sampled from the third transport container on the upper side of the collection hopper. And a fourth step of injecting the radioactive waste from the collection hopper into the waste drum, and a fourth step of moving the transfer containers one by one.

According to embodiments of the present invention, it is possible to take samples from each radioactive waste packaging unit that can clearly demonstrate representativeness for reliable radionuclide concentration assessment, but at the cost and time efficiency of radioactive waste There is an effect that can be screened and processed.

1 is a perspective view showing a radioactive waste treatment apparatus according to an embodiment of the present invention.
2 is a perspective view of the radioactive waste treatment apparatus of FIG. 1 from another angle.
3 is a perspective view illustrating a crushing unit of the radioactive waste treatment apparatus of FIG. 1.
4 is a perspective view illustrating a transfer unit of the radioactive waste treatment apparatus of FIG. 1.
FIG. 5 is a conceptual view illustrating a state in which crushed radioactive waste is introduced into a transfer container of FIG. 4.
FIG. 6 is a conceptual view illustrating a state in which radioactive waste is introduced into a waste drum through a collection hopper by rotating a transfer container of FIG. 4.
7 is a perspective view illustrating a level measurement unit of the radioactive waste treatment apparatus of FIG. 1.
8 is a graph illustrating a result of measuring the level of radioactive waste by the level measuring unit of FIG. 7.
FIG. 9 is a diagram illustrating a process of collecting a representative sample by using a sampler of a sample collection unit of the radioactive waste processing apparatus of FIG. 1.
10 is a flowchart illustrating a method of treating radioactive waste using the radioactive waste treatment apparatus of FIG. 1.
11 to 14 are views sequentially illustrating a process of treating the radioactive waste by the radioactive waste treatment apparatus of FIG.
15 is a diagram illustrating a method for treating radioactive waste by levels.

Hereinafter, specific embodiments for implementing the spirit of the present invention will be described in detail with reference to the accompanying drawings.

In addition, in describing the present invention, when it is determined that the detailed description of the related well-known configuration or function may obscure the gist of the present invention, the detailed description thereof will be omitted.

In addition, it is to be understood that when a component is referred to as being 'connected' or 'contacted' to another component, the component may be directly connected or contacted with the other component, but other components may be present in between.

The terminology used herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention. A singular expression includes a plural expression unless the context clearly indicates otherwise.

Hereinafter, with reference to the drawings will be described an automatic chamfering device of the plate-shaped base material according to an embodiment of the present invention.

1 and 2, the radioactive waste treatment apparatus 1 according to an embodiment of the present invention is a crushing unit 10, the transfer unit 20, the level measuring unit 30, the sample collection unit 40, The waste drum 50 and the control unit 60 may be included. The radioactive waste treatment apparatus 1 pulverizes the radioactive waste in the form of particles in the crushing unit 10, and the pulverized radioactive waste is transferred by the transfer container 230 of the transfer unit 20 to measure the level measurement unit 30 and Level measurement and representative sample collection are performed via the sampling unit 40. This is done until the representative sample is finally delivered to the waste drum (50).

The radioactive waste treated by this process may be, for example, solid waste such as concrete or soil generated during dismantling of a nuclear power plant. However, the idea of the present invention is not limited by the type of radioactive waste to be treated. For reference, FIGS. 1 and 2 only show characteristic components included in the radioactive waste treatment apparatus 1, and members such as a support, a frame, etc., which support these components are omitted.

The waste drum 50 receives radioactive waste received from the transfer container 230 by separating the radioactive level and completing the radioactive level measurement. The waste drum 50 filled with radioactive waste is transferred to a separate treatment facility such as a cave and post-treated according to the measured radioactivity level. The waste drum 50 is transferred through a waste transfer line 500 disposed below the collection hopper 400 of the sample collection unit 40.

Hereinafter, specific components of the radioactive waste treatment apparatus 1 according to the present embodiment will be described in detail with reference to the drawings.

Referring to FIG. 3, the pulverization unit 10 pulverizes the radioactive waste introduced from the outside in the form of particles. In addition, the crushing unit 10, for example, may be provided to crush the radioactive waste in the form of agglomerate into particles 1 mm or more in diameter. The grinding unit may include a grinding chamber 100, an input hopper 110, a grinder 120, and a discharge guide 130.

The pulverization chamber 100 provides a space in which radioactive waste introduced from the outside is accommodated for pulverization. For example, the pulverization chamber 100 may be provided as a chamber of a cube, but the spirit of the present invention is not limited thereto.

The input hopper 110 is connected to the pulverization chamber 100 and is provided to input radioactive waste. The input hopper 110 may be provided in a funnel shape in which the cross-sectional area is reduced from the upper end to the lower end to facilitate the input of radioactive waste.

The grinder 120 is provided inside the grinding chamber 100 and is provided to grind the radioactive waste introduced from the charging hopper 110. The grinder 120 may be configured such that, for example, a pair of grinding blades are rotated while being engaged with each other, such that radioactive wastes interposed between the pair of grinding blades are cut and ground by the grinding blades.

The discharge guide 130 is connected to the grinding chamber 100 and configured to discharge the radioactive waste crushed by the grinder 120. For example, the discharge guide 130 may have a bottom surface formed in a downwardly inclined duct shape, and the radioactive waste crushed in the grinding chamber 100 may fall through the discharge guide 130 to be discharged to the transfer container 230. Can be. Although not shown, the crushing unit 10 may further include an opening and closing device for adjusting the amount of the radioactive waste discharged to distribute to the transfer container 230 in a predetermined amount.

Meanwhile, referring to FIGS. 4 to 6, the transfer unit 20 includes a plurality of transfer containers 230 for receiving radioactive waste crushed by the crush unit 10, and the transfer container 230 includes a predetermined transfer path. It is configured to transfer along. The transfer part 20 may include a container transfer line 200, a connection member 210, a rotation member 220, and a transfer container 230.

The container transfer line 200 is formed along a preset transfer path. For example, the container transfer line 200 may be formed in a circular shape, and for this purpose, the container transfer line 200 may also be formed in a loop shape. The vessel transfer line 200 may be provided as a conveyor apparatus as an example, and may be driven by a driving member (not shown) that provides power for transfer.

The connection member 210 connects the container transfer line 200 and the transfer container 230. In addition, the connection member 210 may be formed to extend downward from the bottom of the container transfer line 200 may be connected to the transfer container 230. The connecting member 210 may include a bifurcated frame to fix the transfer container 230 on both sides.

The rotating member 220 is connected to the connecting member 210 and provided to rotate the transfer container 230 with respect to the connecting member 210. The rotation member 220 may be installed at the center portion of the circumferential surface of the transfer container 230, and may be installed at both ends of the diameter of the transfer container 230. In addition, the rotation member 220 may include a member for rotational driving such as a motor for rotating the transfer container 230, and thus the transfer container 230 may be rotated with respect to the connecting member 210. .

The transfer container 230 is provided to receive the radioactive waste pulverized in the crushing unit 10, and is connected to the vessel transfer line 200 through the connection member 210, and is driven by driving the vessel transfer line 200. It can be transported along a transport path. The transfer container 230 may be provided in plural, and thus, the connection member 210 may also be provided to correspond to the number of the transfer containers 230. The transfer container 230 may be provided in a cylindrical shape having an upper surface opened, and may be provided in a cylindrical shape as an example, but the spirit of the present invention is not limited thereto. In this embodiment, although the transfer container 230 is provided with a total of ten along the vessel transfer line 200 as an example, the idea of the present invention is not limited by the number of the transfer container (230). The plurality of transfer containers 230 may be provided with unique IDs that are distinguished from each other. Information of the ID included in each of the transfer containers 230 may be stored in the controller 60.

The transfer container 230 passes along the container transfer line 200 while receiving the crushed radioactive waste, passes through the level measurement unit 30 and the sample collection unit 40, and returns to the crush unit 10 side again. Can be. Accordingly, the radioactive waste contained in the transfer container 230 is processed through a process of finally entering the waste drum 50 after the level measurement and sampling.

In this case, the container transfer line 200 may transfer the transfer containers 230 in such a manner that the plurality of transfer containers 230 move one space at a time and stop for a predetermined time and then move one space again. Thus, while the vessel transfer line 200 is stopped, the radioactive waste pulverized from the crush unit 10 is introduced into any one of the plurality of transfer vessels 230 as shown in FIG. 5, and the level is measured by the level measuring unit 30. 6 is measured, and processes of introducing radioactive waste into the waste drum 50 may be simultaneously performed while a representative sample of the radioactive waste is collected as shown in FIG. 6.

Meanwhile, referring to FIG. 7, the level measuring unit 30 measures the radioactive level of the radioactive waste provided on the transfer path of the transfer unit 20 and accommodated in the transfer container 230. The level measuring unit 30 may include a fixed body 310, a door body 320, and a door driving member 330. The fixed body 310 and the door body 320 may include a shielding member 302 and It may consist of a detector 304.

The fixture 310 is fixed to a position that does not interfere with the transfer path of the transfer container 230, and is provided to cover a portion of the side surface of the transfer container 230. In addition, the door 320 is provided to open and close the transfer path of the transfer container 230 selectively interferes with the transfer path of the transfer container (230). In addition, when the door 320 closes the transport path, the remaining part of the side surface of the transport container 230 which is not covered by the fixture 310 may be covered by the door 320. To this end, the door 320 may be opened and closed by the door driving member 330. The door driving member 330 may be provided as, for example, a hydraulic cylinder, but the spirit of the present invention is not limited thereto.

For example, two fixed bodies 310 and doors 320 may be provided to cover four surfaces of the transfer container 230. Accordingly, the entire peripheral surface of the transfer container 230 may be covered by the fixing body 310 and the door body 320. Hereinafter, a case in which two fixed bodies 310 and two door bodies 320 are provided will be described as an example, but the number of the fixed bodies 310 and the door bodies 320 is the entire circumferential surface of the transfer container 230. Any number can be modified as long as it can cover.

Referring to the operation of the door body 320, while the container transfer line 200 is driven to be introduced into the level measuring unit 30, the door 320 is retracted to the lower side of the transfer container 230. The transport path can be kept open. Thereafter, when the transfer container 230 requiring the level measurement enters the space between the two fixtures 310, the vessel transfer line 200 stops driving, and the door driving member 330 is driven to drive the door body 320. Will rise. As a result, a state in which the entire circumferential surface of the transfer container 230 requiring the level measurement is covered by the fixed body 310 and the door body 320 may be implemented, and in this state, the radiation level for the transfer container 230 may be realized. Can be measured. FIG. 7 illustrates each operation of the door 320, and FIG. 7A illustrates a state in which the door 320 is retracted downward and does not interfere with the transfer path of the transfer container 230. 7 (b) shows a state in which the door 320 is lifted by the door driving member 330 and the transport path of the transport container 230 is interfered by the door 320.

For the radioactivity level measurement, the fixture 310 and the door 320 are provided with a detector 304 installed in the shield member 302 to face the shield member 302 having a radiation shielding capability and the transfer container 230. It can be configured to include. The shielding member 302 may be made of a material capable of shielding radiation, and the detector 304 may be provided to measure radioactivity by measuring a gamma ray spectrum emitted from radioactive waste.

Specifically, the radionuclide is the main radionuclide in radioactive waste (Co-60, Eu-152, Eu-154, etc.), and the fission product (Cs-137, etc.). The level selection algorithm determines the radioactive concentrations of these nuclides and sorts the radioactive waste contained in the transport vessel 230 into a medium level, a low level, an extremely low level, and a self-disposing level. The radioactive concentration of the radioactive waste is determined through the gamma ray spectrum and the detection efficiency measured by the level measuring unit 30. The detection efficiency can be obtained through actual measurement using a standard source or through Monte Carlo computer simulation, and it is databased according to the conditions of radioactive waste, detector 304, shield member 302, etc. and applied to the level selection algorithm. The level selection algorithm and the database may be stored in the control unit 60 so that the level selection process may be performed by the control unit 60.

For clarity, the Monte Carlo simulation results when NaI (Tl) is used as a detector to obtain detection efficiency are shown in FIG. 8. To achieve these results, Monte Carlo simulations were performed using a detector made of NaI (Tl) with a radioactive waste consisting of concrete, soil, etc. in a 0.2 cm thick Teflon container with a radius of 4 cm and a height of 20 cm. As a result, a gamma ray spectrum (Co-60, Eu-152 in Concrete / Cs-137 in Soil) was obtained. The peak area of each nuclide is obtained from the gamma ray spectrum thus obtained, and finally, the detection efficiency can be obtained.

On the other hand, referring to Figure 9, the sample collection unit 40 is provided on the transfer path of the transfer container 230, a portion of the radioactive waste introduced into the waste drum 50 from the transfer container 230 as a representative sample Collect. To this end, the sample collection unit 40 may include a collection hopper 400, a collector 410, a sample container 420, and a sample transfer line 430.

The collection hopper 400 is provided to input the radioactive waste discharged from the transfer container 230. To this end, the collection hopper 400 may be provided in a cylindrical shape with the upper and lower openings, and a hole formed in the lower portion may be formed toward the upper surface of the waste drum 50 transferred through the waste transfer line 500. have. Accordingly, when the transfer container 230 rotates by the rotation member 220 above the collection hopper 400, the radioactive waste stored in the transfer container 230 passes through the upper surface of the transfer container 230. The falling radioactive waste is passed through the collection hopper 400 and is introduced into the waste drum 50 under the collection hopper 400.

The harvester 410 collects some of the radioactive waste introduced into the collection hopper 400 as a sample. The harvester 410 is connected to the rotating body 412, the collecting pocket 414 connected to the rotating body 412 and the rotating body 412 and the collecting pocket 414 rotatably provided about the central axis. It may include a pocket connecting bar (416).

The rotating body 412 is provided in a columnar shape so as to be rotatable about an inner central axis. To this end, it may further include a rotation drive member (not shown) such as a motor connected to the central axis of the rotation body 412. The collecting pocket 414 is provided in a small cylindrical shape with an open top surface, and an end thereof may be connected to the pocket connecting bar 416. The pocket connection bar 416 is provided to be rotatable about an inner central axis in a state connected to the rotating body 412, and for this purpose, a motor such as a motor connected to the central axis of the pocket connecting bar 416 is provided. It may further include a rotation drive member (not shown).

Accordingly, the pocket for collecting 414 can revolve around the rotating body 412 by the rotation of the rotating body 412, and the pocket connecting bar 416 is rotated about the axis by the rotation of the pocket connecting bar 416. Rotating is provided. 9 illustrates each operation of the extractor 410, and FIG. 9 (a) shows that radioactive waste is removed from the transfer container 230 with the collecting pocket 414 positioned above the collection hopper 400. By pouring down toward the collection hopper 400, a part of this is collected into the collecting pocket 414, and FIG. 9B shows that the collecting pocket 414 is rotated by the rotation of the rotating body 412. Revolving around the body 412 shows the state disposed above the sample container 420, Figure 9 (c) is a pocket connecting bar 416 is rotated so that the collecting pocket 414 is collected therein while rotating The radioactive waste, which has been used, is introduced into the sample container 420 and collected as a representative sample. This representative sampling process may be repeated until the waste drum 50 is all filled.

The sample container 420 may be provided to accommodate a sample collected by the extractor 410, and may be provided in a cylindrical shape having an upper surface open like the transfer container 230. For example, the sample container 420 may be provided in a cylindrical shape. However, the spirit of the present invention is not limited thereto. In addition, since the sample container 420 is used to collect representative samples, the sample container 420 may have a smaller capacity than the transfer container 230. In addition, the ratio of the capacity of the transfer container 230 and the capacity of the waste drum 50 may be set equal to the ratio of the capacity of the collecting pocket 414 and the capacity of the sample container 420.

The sample transfer line 430 is disposed below the sampler 410 and is provided to transfer the sample container 420. The sample transfer line 430 may be composed of a plurality of conveyors, for example, may be provided with one line for each radioactivity level, the sample container (not shown) to the outside of the sample storage chamber (not shown) at the end of each level line A line for transferring the 420 may be further provided.

Like the sample transfer line 430, the waste transfer line 500 may be composed of a plurality of conveyors, and may be provided with one line for each radioactivity level, and an external treatment facility (not shown) at the end of each level line. ) May be further provided with a line for transferring the waste drum 50.

The sample transfer line 430 and the waste transfer line 500 may include a number of level-specific lines corresponding to each other, and radioactive waste having the same radioactive level may be representative of the sampling and waste drums 50 on the same level-specific line. Input to can be carried out. Accordingly, the sample container 420 and the waste drum 50 may correspond one to one with respect to the same radioactivity level, and one sample container 420 may be filled with radioactive waste per one waste drum 50.

For example, if the volume of the waste drum 50 is set to 200L and the capacity of the transfer container 230 is set to 2L, and a representative sample is collected at 10 mL per transfer container 230, a total of 1L of representative samples are collected from the sample container ( 420). This can be said to be statistically representative data, since the radioactivity level corresponds to the level of 100 representative samples taken from selected radioactive waste.

The waste drum 50 may be provided in plural numbers, and each of the waste drums 50 may be provided separately. The waste drum 50 may contain only radioactive waste having the same level as the divided radioactive level among the radioactive wastes in the transfer container 230 in which the radioactive level is measured by the level measuring unit 30. Similarly, the sample container 420 may also be provided in plural numbers, each of which may be provided separately by radioactivity level. In the sample container 420, only representative samples collected from radioactive waste having the same level as the divided radioactive level among the radioactive waste in the transport container 230 in which the radioactivity level is measured by the level measuring unit 30 may be accommodated. .

The control unit 60 receives the result of the level measurement of the radioactive waste from the level measuring unit 30 and inputs the radioactive waste contained in the transfer container 230 to the waste drum 50 divided into the radioactive level corresponding to the result. The transfer unit 20 is controlled. In this process, the control unit 60 may control the sample collection unit 40 to inject a representative sample collected from the radioactive waste introduced into the corresponding waste drum 50 into the sample container 420 separated by the same radioactivity level. . As a result, the controller 60 may match the sample container 420 and the waste drum 50 in a one-to-one manner.

The control unit 60 may be provided to control the crusher 10, the transfer unit 20, the level measurement unit 30, and the sample collection unit 40. To this end, the control unit 60 may be formed of, for example, a small built-in computer, and may include a data processing unit including a program, a memory, and a CPU. Such a program may include the above-described level selection algorithm and other algorithms for controlling each part. In addition, such a program can be stored in a memory such as a computer storage medium such as a flexible disk, a compact disk, a hard disk, or a magneto-optical disk (MO), and can be installed in the controller 60.

In the following, the radioactive waste leveling device 1 having the above-described configuration will be described for level selection, representative sample collection, and processing of radioactive waste. The process described later may be performed by being automatically controlled by the controller 60.

Referring to FIG. 10, in the radioactive waste treatment method using the radioactive waste treatment apparatus 1 according to the present embodiment, the radioactive waste introduced into the pulverization unit 10 from the outside is pulverized and introduced into the transfer container 230. First step (S10), the second step (S20) for measuring the radioactive level of the radioactive waste contained in the transport container 230 in the level measuring unit 30, the radioactive waste from which the radioactive level is measured is collected from the transport container (230) Injected into the hopper 400, the sampling unit 40 is collected from the transfer container 230 by the sampling unit 40 on the upper side of the collection hopper 400 as a representative sample, and the waste drum from the collection hopper 400 The method may include a third step S30 of introducing the radioactive waste into the 50 and a fourth step S40 of moving the plurality of transfer containers 230 one by one.

In this case, the first to third steps S10, S20, and S30 may be simultaneously performed, and the respective steps may be performed on different transfer containers 230 among the plurality of transfer containers 230. . In addition, the fourth step S40 is performed after all of the first to third steps S10, S20, and S30 are performed.

First, when radioactive waste is introduced from the outside in the first step (S10) through the input hopper 110 of the crushing unit 10, the control unit 60 operates the grinder 120 to crush the radioactive waste into the form of particles. . The crushed radioactive waste may be introduced into the transfer container 230 adjacent to the discharge guide 130 through the discharge guide 130. In this case, for convenience of description, the transfer container 230 into which the radioactive waste crushed in the crushing unit 10 is introduced is referred to as a first transfer container.

At the same time, in the second step (S20), the radioactive level of the radioactive waste contained in the transport container 230 covered by the stationary body 310 and the door body 320 of the level measuring unit 30 is measured. In this case, the measured radioactivity level may be measured using a level selection algorithm stored in the controller 60. The information on the radioactivity level measured in this way is matched with the ID information of the transfer container 230 and stored in the control unit 60. The ID information and the radioactivity level matching information of the transfer container 230 may be used to perform a representative sampling and waste input process for the sample container 420 and the waste drum 50 which are divided into the corresponding radioactivity level. have. For convenience of description, the transfer container 230 in which the radioactivity level is measured by the level measurement unit 30 is called a second transfer container.

In addition, in the third step (S30), the radioactive waste contained in the transfer container 230 is collected in the transfer container 230 for the sample container 420 and the waste drum 50, which are divided in the same manner as the measured radioactivity level of the transfer container 230. The process to be input to 400 may be performed (S310). To this end, the transfer container 230 is rotated so that the upper surface is directed downward by the rotating member 220. At this time, a portion of the radioactive waste introduced from the transfer container 230 is collected in the collecting pocket 414 while the collecting pocket 414 of the sample collecting unit 40 is located above the collection hopper 400. . The radioactive waste thus collected is collected after the pocket 414 is revolved about the rotating body 412 and positioned above the sample container 420, and the pocket connecting bar 416 rotates to collect the pocket 414. ) May be introduced into the sample container 420 as it rotates (S320). The radioactive waste passing through the collection hopper 400 is introduced into the waste drum 50 located below (S330). For convenience of explanation, the third container transfers the transfer container 230 which is rotated by the rotating member 220 and the radioactive waste therein is introduced into the collection hopper 400 and the representative sample is collected by the sample collection unit 40. Called courage.

Subsequently, after all of the first to third steps S10, S20, and S30 described above are completed in the fourth step S40, the controller 60 controls the container transfer line 200 by an interval between the respective transfer containers 230. The transfer container 230 can be moved one space by driving (). When the movement of the transfer vessels 230 is completed, driving of the vessel transfer line 200 again stops, and the first to third steps S10 described above with respect to the transfer vessels positioned immediately before the first to third transfer vessels (S10). , S20 and S30 may be performed.

The above-described steps will be described in time series with reference to FIGS. 11 to 14. Here, for convenience of description, a total of ten transfer containers 230 are provided, and each transfer container 230 will be described with an example in which IDs are sequentially assigned to A to J. In addition, the radioactivity level to be selected is set to a total of four (self-disposal level, ultra-low level, low level and medium level), accordingly four total collection hopper 400 is also provided, each corresponding to four radiation levels The case will be described as an example. In addition, it will be described by taking an example in which four lines for each level of the sample transfer line 430 and the waste transfer line 500 are also provided so as to correspond to the respective radiation levels to correspond to the collection hopper 400. However, this is merely illustrative for convenience of description, and the spirit of the present invention is not limited by this configuration.

Referring to FIG. 11, the transfer containers 230 corresponding to A to J may be spaced apart from each other by a predetermined distance. In this state, the first to third steps S10, S20, and S30 may be performed. At this time, as shown in FIG. 12, the radioactive waste crushed from the crushing unit 10 is introduced into the J transport container 230, the radioactive level of the H transport container 230 is measured, and at the same time A and C transport containers ( Representative sampling of 230 and radioactive waste input to the waste drum 50 can be made. In other words, in FIG. 12, the J transport container 230 is the first transport container, the H transport container 230 is the second transport container, and the A and C transport containers 230 are the third transport container. In addition, the reason why only the A and C transfer containers 230 of the A to D transfer containers 230 are introduced into the collection hopper 400 is because the radioactive level measurement of the A transfer container 230 results in self-disposal levels. This is because it is sorted and selected as a low level as a result of the radioactive level measurement of the C transfer container 230. In addition, since the radioactivity level of the B transport container 230 is not a very low level, and the radioactivity level of the D transport container 230 is not a medium level, the input of waste and representative sampling are not performed.

Thereafter, as shown in FIG. 13, the transfer container 230 moves by one space while the container transfer line 200 is driven. At this time, the door body 320 of the level measuring unit 30 is retracted downward before the driving of the container transfer line 200 is started to release the interference on the transfer path of the transfer container 230.

When driving of the container transfer line 200 is completed, as shown in FIG. 14, the first to third steps S10, S20, and S30 may be performed again. In this case, in FIG. 14, the A transport container 230 is the first transport container, the I transport container 230 is the second transport container, and the D transport container 230 is the third transport container. In addition, since the radioactive level of the D transport container 230 is selected at a low level, only the D transport container 230 may inject waste.

According to the radioactive waste treatment apparatus 1 according to the embodiment of the present invention as described above, it is possible to take a sample that can be clearly demonstrated representative from each radioactive waste packaging unit for reliable radionuclide concentration evaluation. At the same time, there is an effect that the radioactive waste can be sorted and treated efficiently in terms of cost and time.

Although the embodiments of the present invention have been described as specific embodiments, these are only examples, and the present invention is not limited thereto and should be construed as having the broadest scope in accordance with the basic idea disclosed herein. Those skilled in the art can combine / substitute the disclosed embodiments to implement a pattern of a timeless shape, but this also does not depart from the scope of the present invention. In addition, those skilled in the art can easily change or modify the disclosed embodiments based on the present specification, it is obvious that such changes or modifications belong to the scope of the present invention.

Radioactive waste treatment device (1) Crushing unit (10)
Grinding chamber 100 input hopper 110
Grinder 120 Discharge Guide 130
Transfer section 20 Container transfer line 200
Connecting member 210, rotating member 220
Transport container 230 level measurement unit 30
Shield member 302 Detector 304
Fixed body 310, door body 320
Door drive member 330 sampler 40
Collection Hopper (400) Harvester (410)
Rotating Body (412) Harvesting Pocket (414)
Pocket Connection Bars (416) Sample Containers (420)
Sample Transfer Line (430) Waste Drum (50)
Waste Transfer Line 500 Control Unit 60

Claims (16)

Grinding unit for grinding the radioactive waste introduced from the outside;
A transfer unit including a plurality of transfer containers accommodating the radioactive waste crushed in the grinding unit, and transferring the transfer container along a predetermined transfer path;
A level measurement unit provided on the transport path of the transport container and measuring a radioactivity level of the radioactive waste contained in the transport container;
A plurality of waste drums receiving and receiving the radioactive waste from which the radioactivity level measurement is completed, received from the transfer container, and separated by radioactivity levels;
A sample collecting unit provided on the transfer path of the transfer container and collecting a portion of the radioactive waste introduced into the waste drum from the transfer container as a representative sample; And
A control unit for receiving the level measurement result of the radioactive waste from the level measuring unit and controlling the transfer unit to input the radioactive waste contained in the transfer container to the waste drum corresponding to the result;
The transfer unit,
A container transfer line formed along the transfer path;
A connection member connecting the vessel transfer line and the transfer vessel; And
A rotating member provided to rotate the transfer container with respect to the connecting member,
Radioactive waste disposal device. delete According to claim 1,
The container transfer line is formed in a loop so that the transfer path forms a circulation path.
Radioactive waste disposal device. According to claim 1,
The level measuring unit,
A fixed body fixed to a position not interfering with the transfer path and covering a part of the side surface of the transfer container; And
A door body provided to open and close the transfer path selectively to interfere with the transfer path, and cover a remaining portion of the side of the transfer container not covered by the fixing body when the transfer path is closed; And
A door driving member for opening and closing the door body;
Radioactive waste disposal device. The method of claim 4, wherein
The fixture is,
A shielding member having a radiation shielding ability; And
A detector installed on the shielding member so as to face the transfer container;
Radioactive waste disposal device. The method according to claim 4 or 5,
The door body,
A shielding member having a radiation shielding ability; And
A detector installed on the shielding member so as to face the transfer container;
Radioactive waste disposal device. According to claim 1,
The sample collection unit,
A collection hopper into which the radioactive waste discharged from the transfer container is put;
A harvester for collecting a portion of the radioactive waste introduced into the collection hopper as a sample; And
It includes a sample container for receiving the sample collected by the harvester,
The radioactive waste discharged downwardly from the collection hopper is received in the waste drum,
Radioactive waste disposal device. The method of claim 7, wherein
A waste conveying line disposed below the collecting hopper and conveying the waste drum,
Radioactive waste disposal device. The method of claim 7, wherein
The sample collection unit,
It is disposed below the collector, and further comprising a sample transfer line for transferring the sample container,
Radioactive waste disposal device. The method of claim 7, wherein
The harvester,
A rotating body rotatably provided about a central axis;
A collecting pocket connected to the rotating body; And
It includes a pocket connecting bar (bar) for connecting the rotating body and the collecting pocket,
Radioactive waste disposal device. The method of claim 10,
The collecting pocket is revolved around the rotating body by the rotation of the rotary body, and is provided to be capable of rotating the pocket connecting bar about the axis by the rotation of the pocket connecting bar,
Radioactive waste disposal device. The method of claim 10,
The ratio of the capacity of the waste drum to the capacity of the transfer container is set equal to the ratio of the sample capacity to the capacity of the collecting pocket.
Radioactive waste disposal device. The method of claim 7, wherein
The control unit to match the sample container and the waste drum in a one-to-one,
Radioactive waste disposal device. A first step of pulverizing the radioactive waste introduced into the pulverization unit from the outside and injecting it into the first transfer container;
A second step of measuring the radioactive level of the radioactive waste contained in the second transfer container by a level measuring unit;
The radioactive waste of which the radioactivity level was measured is introduced into the collection hopper from the third transfer container, and a portion of the radioactive waste introduced from the third transfer container is collected as a representative sample from the sampling unit at the upper side of the collection hopper, Injecting the radioactive waste from a collection hopper into a waste drum; And
Including a fourth step of moving the transfer containers one by one,
Radioactive Waste Disposal Method. The method of claim 14,
The first to third steps are performed at the same time, and the fourth step is performed after all of the first to third steps are performed.
Radioactive waste disposal method. The method of claim 14,
In the third step,
The waste drums are provided separately for each radioactivity level, and the radioactive wastes are introduced into the waste drums corresponding to the measurement results of the radioactive wastes measured in the second step.
Radioactive Waste Disposal Method.

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