KR20230081858A - Radioactive waste sorting device, nuclear facilities decommissioning waste sorting system and nuclear facilities decommissioning waste history management system including the same - Google Patents

Abstract

The present invention relates to a radioactive waste sorting apparatus, a nuclear facilities decommissioning waste sorting system, and a nuclear facilities decommissioning waste history management system including the same. The nuclear facilities decommissioning waste history management system can comprise: a location determination apparatus determining a location of an electronic tag attached to a measuring container with a subject contained; a first inspection module measuring radioactivity emitted by the subject; a transport crane storing the subject in a first storage region or a second storage region in accordance with the measurement result of the first inspection module; and a management server storing the location of the subject stored by the transport crane as well as the measurement result of the first inspection module for each identification number attached to the electronic tag. Therefore, the radioactive waste sorting speed can be improved.

Description

Radioactive waste sorting device, nuclear facility decommissioning waste classification system, and nuclear facility decommissioning waste history management system including the same

The present invention relates to a radioactive waste classification device, a nuclear facility dismantling waste classification system, and a nuclear facility dismantling waste history management system including the same.

In general, nuclear facility dismantling projects generate radioactive waste that emits various radioactive materials. Various types of radioactive waste generated during the dismantling process are generated in large quantities in a short period of time, so it is very important to manage them efficiently.

In Korea, according to Nuclear Safety and Security Commission Notification No. 2020-6 'Regulations on Radioactive Waste Classification and Self-disposal Criteria', radioactive wastes that satisfy the allowable concentration and dose for self-disposal can be self-disposable, and these self-disposal targets Wastes must be separated and stored to prevent mixing with other wastes.

Conventionally, whether or not radioactive waste satisfies the permissible concentration and dose for self-disposal was determined by performing a single inspection. That is, it is determined whether all radioactive waste satisfies the permissible concentration and dose for self-disposal through one detailed inspection, and since this detailed inspection takes a long time, there is a problem in that the overall radioactive waste classification speed is slowed down.

In addition, conventionally, radioactive waste is transported by a conveyor belt method, and whether or not the radioactive waste satisfies the allowable concentration and dose for self-disposal is measured. Such a conventional conveyor belt method has a problem in that it is difficult to precisely measure radioactive waste because it is impossible to finely adjust the position of the radioactive waste.

An object of the present invention is to provide a radioactive waste sorting device with improved radioactive waste sorting speed and a nuclear facility dismantling waste sorting system including the same.

In addition, an object of the present invention is to provide a radioactive waste sorting device capable of fine position control of radioactive waste and a nuclear facility dismantling waste sorting system including the same.

In addition, the object of the present invention can provide a basis for ensuring a radiologically acceptable level of safety for dismantling waste generated during dismantling and history management for the entire cycle of dismantling waste from the generation site to disposal.

In one example, the radioactive waste sorting device is provided to measure whether or not the radioactivity emitted by the test object is less than or equal to a predetermined first reference amount while the test object moves along a first direction, which is a direction orthogonal to the vertical direction. When the radiation emitted by the test object measured by the first test module and the first test module is equal to or less than the first reference amount, the test object is re-examined and the radiation emitted by the test object is less than the first reference amount. It may include a second inspection module provided to measure whether or not it is below.

In another example, the first inspection module may include a first module body including a first inspection passage extending along the first direction and provided to allow the inspection object to pass therein, and the first module body of the first inspection passage. Located on the direction side may include a first sensor unit provided to measure the radioactivity emitted by the test object.

In another example, the first sensor unit may include a plurality of first sensor members arranged along a vertical direction and a second direction that is one direction orthogonal to the first direction.

In another example, the first sensor unit may include a 1-1 sensor member and a 1-2 sensor member having higher energy resolution than the 1-1 sensor member.

In another example, the first inspection module may further include a first shielding portion provided to cover the first module body to block external radiation from being introduced into the first module body.

In another example, the second test module may place the test object in a second reference area inside the second test module for a reference time to determine whether the radiation emitted by the test object for the reference time is equal to or less than the second reference amount. It can be arranged to measure whether or not.

In another example, the radioactive waste sorting device may further include a pallet on which the test object is seated and a rail unit on which the pallet is movably seated.

In another example, the radioactive waste sorting device further includes a motor coupled to the pallet and provided to move the pallet, wherein the motor unit moves the pallet or the test object seated on the pallet inside the first test module. Before being located in the first reference area, the pallet is moved at a first moving speed, and when the pallet or the inspection target seated on the pallet is located in the first reference area, the pallet is moved at a speed higher than the first moving speed. It can be moved at a slow second movement speed.

In another example, the rail part may include a first rail extending in the first direction and coupled to the first inspection module, and a second rail extending from an end of the first rail in the first direction along the first direction. A third rail extending from an end of the second rail in the first direction in a vertical direction and along a second direction, which is one direction orthogonal to the first direction, from an end of the third rail in the second direction A fourth rail extending in a direction opposite to the first direction and extending in a direction opposite to the second direction from an end of the fourth rail in the opposite direction to the first direction, and the first rail of the first rail It is connected to the direction-side end and may include a fifth rail to which the second inspection module is coupled.

In another example, the radioactive waste sorting device is located at a side of the third rail in the first direction to be spaced apart from the third rail, and a storage unit provided to store a test object for which radioactivity measurement has been completed, and the third rail It is disposed between the storage units and may further include a transfer crane provided to transfer an object to be tested seated on a pallet located on the third rail to the storage unit.

In another example, the storage unit stores a first storage area in which a test object having a radioactivity of the test object exceeding the second reference amount is stored, and a test object having a radioactivity emitted of the test object of which the second reference amount or less is stored. It may include a second storage area provided to be.

In another example, when the radiation emitted by the test object seated on the pallet measured by the first test module when the pallet passes the first rail exceeds the first reference amount, the test object is on the pallet After being seated and passing the second rail, it can be stored in the first storage area through the transfer crane.

In another example, when the radiation emitted by the test object seated on the pallet measured by the first test module when the pallet passes the first rail is less than the first reference amount, the test object is seated on the pallet and passes through the second rail, the third rail, the fourth rail, and the fifth rail, and the second inspection module determines that the radiation emitted by the inspection object when the inspection object passes the fifth rail It is possible to measure whether or not the amount is equal to or less than the second reference amount.

In another example, when the radiation emitted by the test object measured by the second test module exceeds the second reference amount, the test object is seated on the pallet, passes through the second rail, and then passes through the transfer crane. It may be stored in the first storage area.

In another example, when the radiation emitted by the test object measured by the second test module is less than or equal to the second reference amount, the test object is seated on the pallet and passes through the second rail, and then the transfer crane It may be stored in the second storage area.

In another example, the rail unit may include a sixth rail extending in a direction opposite to the first direction from an end of the fourth rail in the direction opposite to the first direction, and a direction opposite to the first direction of the sixth rail A pallet that extends from the side end in a direction opposite to the second direction and further includes a seventh rail connected to the first rail, and the pallet delivering the inspection object to the transfer crane, the fourth rail, the sixth It may be moved to the first rail through the rail and the seventh rail.

In another example, the radioactive waste sorting device may further include a decontamination unit provided to decontaminate the inspection object seated on the pallet by being coupled to the rail unit.

For example, a nuclear facility dismantling waste classification system measures the radioactivity of nuclear facility dismantling waste, which is waste generated by dismantling a nuclear facility, and classifies the nuclear facility dismantling waste according to a predetermined standard. A control unit provided to control a waste sorting device, wherein the radioactive waste sorting device includes: a first inspection module provided to measure whether radioactivity emitted from the nuclear facility dismantling waste is equal to or less than a predetermined first reference amount; 1 When the radioactivity emitted from the nuclear facility dismantling waste measured by the inspection module is equal to or less than the first reference amount, the nuclear facility dismantling waste is re-inspected so that the radioactivity emitted from the nuclear facility dismantling waste is less than the first reference amount. and a storage unit provided to classify and store the nuclear facility dismantling waste based on the test results of the first test module and the second test module and a second test module provided to measure whether or not the waste is below or below.

In one example, the nuclear facility dismantling waste history management system includes a position determination device for determining the location of an electronic tag attached to a measuring container containing an object to be inspected, a first inspection module for measuring radioactivity emitted by the object to be inspected, and the first Transfer cranes that store the inspection object in the first storage area or the second storage area according to the measurement result of the first inspection module and the transfer crane for each identification number assigned to the electronic tag according to the measurement result of the first inspection module and the transfer crane It may include a management server that stores the location where the test object is stored.

In another example, the first inspection module may determine whether the radiation emitted from the inspection target is equal to or less than a first reference amount.

In another example, if the radioactivity emitted by the test object is less than the first reference amount, a second test module for determining whether the radioactivity emitted by the test object is less than the second reference amount may be further included.

In another example, the management server may store the measurement result of the second test module together with the measurement result of the first test module and the location where the test object is stored for each identification number assigned to the electronic tag.

In another example, the transfer crane may store the test object in the second storage area when the radioactivity measured by the second test module is less than the second reference amount.

In another example, the transfer crane, the test object when the radioactivity measured by the first test module exceeds the first reference amount or the radioactivity measured by the second test module exceeds the second reference amount may be stored in the first storage area.

In another example, the management server may store measurement results of the first inspection module provided after the inspection target reaches the location of the first inspection module for each identification number.

In another example, the management server may store measurement results of the second inspection module provided after the inspection target reaches the location of the second inspection module for each identification number.

In another example, the management server may store the dismantling time of the test object for each identification number, the generation source, the waste type, the sample radioactivity information, and the sample radioactivity measurement time.

In one example, a nuclear facility dismantling waste history management method includes attaching an electronic tag to a measuring container containing an object to be inspected, and managing the source of the object to be inspected, the type of waste, and the radioactivity information of the sample for each identification number assigned to the electronic tag. storing in a server, storing the measured radioactivity information of the test object from the first test module in the management server when the location of the electronic tag reaches the location of the first test module, Storing the measured radioactivity information of the test target from the second test module in the management server when the location of the second test module is reached, and when the location of the electronic tag reaches the first storage area or the second storage area It may include storing the location where the test object is stored in the management server.

In another example, the management server may store radioactivity information measured from the first and second inspection modules for each identification number of the electronic tag and a location where the object to be inspected is stored.

In another example, a position determining device for determining the position of the electronic tag may be included.

According to the present invention, since a high-speed inspection is primarily performed and a detailed inspection is secondarily performed based on a result of the high-speed inspection, the radioactive waste sorting speed can be improved.

In addition, according to the present invention, since the radioactive waste is moved using a linear motor method, it is possible to finely adjust the position of the radioactive waste and thus perform precise measurement.

In addition, according to the present invention, by providing a basis for ensuring the radiologically acceptable level of safety for the history management of nuclear power plant dismantling waste and the radiologically acceptable level of dismantling waste, the management reliability of nuclear power plant dismantling waste is improved, social anxiety is resolved, and public confidence in the nuclear energy business is improved. can improve

1 is a diagram conceptually illustrating a process in which radioactive waste is treated through a radioactive waste sorting device according to an embodiment of the present invention.
2 is a perspective view of a radioactive waste sorting device according to an embodiment of the present invention.
3 is a top view of a radioactive waste sorting device according to an embodiment of the present invention.
4 is a perspective view of a first inspection module;
5 is a top view of the first inspection module.
6 is a perspective view of a second inspection module;
7 is a top view of the second inspection module.
8 is a perspective view showing a roller.
9 is a diagram illustrating a case where an object to be inspected is not located in a first reference area.
10 is a diagram illustrating a case where an object to be inspected is in a first reference region.
11 is a diagram illustrating a movement path of a pallet when the radioactivity of an object to be tested exceeds a first reference amount.
12 is a diagram illustrating a movement path of a pallet when the radioactivity of an object to be tested is less than or equal to a first reference amount.
13 is a diagram illustrating a movement path of a pallet when the radioactivity of an object to be tested exceeds a second reference amount.
14 is a diagram illustrating a movement path of a pallet when the radioactivity of an object to be tested is less than or equal to a second reference amount.
15 is a diagram illustrating a movement path of a pallet after storage of an object to be inspected is finished.
16 is a diagram conceptually showing the configuration of a nuclear facility dismantling waste history management system according to an embodiment of the present invention.
17 is a diagram for explaining the operation of the nuclear facility dismantling waste history management system according to an embodiment of the present invention.

Hereinafter, some embodiments of the present invention will be described in detail through exemplary drawings. In adding reference numerals to components of each drawing, the same components are to have the same numerals as much as possible even if they are displayed in different drawings. In addition, in describing an embodiment of the present invention, if it is determined that a detailed description of a related known configuration or function hinders understanding of the embodiment of the present invention, the detailed description thereof will be omitted.

Radioactive waste sorting device

1 is a diagram conceptually illustrating a process in which radioactive waste is treated through a radioactive waste sorting device according to an embodiment of the present invention. 2 is a perspective view of a radioactive waste sorting device according to an embodiment of the present invention. 3 is a top view of a radioactive waste sorting device according to an embodiment of the present invention.

A radioactive waste classification device according to an embodiment of the present invention may be a device that classifies radioactive waste based on a radiation dose of the radioactive waste. As an example, the radioactive waste may be nuclear facility dismantling waste.

Nuclear facility decommissioning waste may include concrete and soil. In the case of concrete, since the particle size is large, it may be crushed to a certain size through a crusher and then put into a measuring container through a discharger. In the case of soil, it can be dipped into a measuring container through a dispenser.

Hereinafter, the radioactive waste contained in the measuring container is defined as the inspection target (T).

First inspection module 10, second inspection module 20

As shown in FIG. 2 , the radioactive waste classification device may include a first inspection module 10 and a second inspection module 20 . The first inspection module 10 may be provided to measure whether or not the radiation emitted from the inspection target object T is equal to or less than a predetermined first reference amount. The first direction D1 may be one direction orthogonal to the up and down directions. For example, the first reference amount may be 1 becquerel (Bq/g).

For example, the first inspection module 10 may be provided to measure whether the radiation emitted by the inspection object T is less than or equal to a first reference amount while the inspection object T moves along the first direction D1. there is. This method can be understood as a method for relatively high-speed inspection. However, it is not necessarily limited thereto, and it may be possible to apply the inspection method of the second inspection module 20 to be described later to the first inspection module 10 .

The second inspection module 20 re-inspects the inspection object T when the radiation emitted by the inspection object T measured by the first inspection module 10 is equal to or less than the first reference amount, so that the inspection object T emits It may be arranged to measure whether the radioactivity is less than or equal to the second reference amount. The second reference amount may have a smaller value than the first reference amount. For example, the second reference amount may be 0.1 becquerel (Bq/g).

For example, the second inspection module 20 places the inspection object T in the second reference area inside the second inspection module 20 for a reference time, and the radiation emitted by the inspection object T for the reference time. It may be provided to measure whether or not the second reference amount is less. For example, the reference time may be 10 minutes. This method can be understood as a method for a relatively precise inspection. However, it is not necessarily limited thereto, and it may be possible to apply the above-described inspection method of the first inspection module 10 to the second inspection module 20 .

4 is a perspective view of a first inspection module; 5 is a top view of the first inspection module. 6 is a perspective view of a second inspection module; 7 is a top view of the second inspection module. Hereinafter, the first inspection module 10 and the second inspection module 20 will be described in detail with reference to FIGS. 4 to 7 .

The first inspection module 10 may include a first module body 11 and a first sensor unit 12 . The first module body 11 may include a first inspection passage 13 . The first inspection passage 13 extends along the first direction D1, and an inspection object T may pass therein.

The first sensor unit 12 may be positioned on the first direction D1 side of the first inspection passage 13 to measure radiation emitted from the inspection target object T.

For example, the first sensor unit 12 may include a plurality of first sensor members. In this case, radionuclides measured by each of the first sensor members may be the same in order to measure radioactivity. For example, the first sensor member may measure the radioactivity of at least one of Cs-137 and Co-60.

The plurality of first sensor members may be arranged along a vertical direction and a second direction D2 , which is a direction orthogonal to the first direction D1 . When measuring the radiation dose, there is a possibility that the radiation dose will be detected less if the object to be inspected is further away from the first sensor member. When the first sensor member is provided in plurality, the maximum separation distance between one first sensor member and the object T to be inspected is reduced, so reliability of measurement may be increased.

As another example, the first sensor unit 12 may include a 1-1 sensor member 12a and a 1-2 sensor member 12b. For example, the 1-1st sensor member 12a may be a NaI(Tl) scintillation detector. The 1-2 sensor member 12b may have higher energy resolution than the 1-1 sensor member 12a.

Hereinafter, effects obtained as the first sensor unit 12 includes the 1-1 sensor member 12a and the 1-2 sensor member 12b will be described in detail.

The NaI(Tl) scintillation detector emits up to 55,000 photons, has high luminous efficiency, and has a fast extinction time of about 250 ns, so it is suitable for measuring and analyzing signals such as gamma ray measurement. Since it has been used since the 1950s and has been used by many researchers in various fields, its reliability has been proven, so it is used as the most basic equipment in the field of measuring and analyzing radiation.

However, the disadvantage of the NaI(Tl) scintillation detector is its low energy resolution. The resolution at 661.66 keV emitted from Cs-137 is about 7%, which is quite low compared to other scintillation materials. Low energy resolution means that a relatively wide background (environmental radiation) region is included, and errors in measurement and analysis may increase.

For example, when trying to measure the radioactivity of 661.66 keV emitted by Cs-137 in a certain soil sample, it can be assumed that the sample contains Bi-214. Since Bi-214 emits energy of 609 keV, when measured using NaI(Tl), which has low energy resolution, the 609 keV energy of Bi-214 and the 661.66 keV energy of Cs-137 cannot be distinguished and one peak ( peak) can be formed. Since values to be distinguished by forming each energy peak are added together to form one peak, a serious error in counting may occur.

At this time, if another detector with higher gamma ray detection efficiency and improved energy resolution than the NaI(Tl) scintillation detector is used in parallel, the error in counting can be reduced.

The first inspection module 10 may further include a first shielding unit 14 . The first shielding unit 14 may be provided to cover the first module body 11 to block external radiation from being introduced into the first module body 11 . Natural radiation may also exist outside the first inspection module 10 . At this time, when natural radiation is introduced into the first inspection module 10, reliability of the value measured by the first inspection module 10 may have a problem. can be shielded.

The second inspection module 20 may include a second module body 21 and a second sensor unit 22 . The second module body 21 may include a second inspection passage 23 . The second inspection passage 23 extends along the second direction D2, and an inspection object T may pass therein. At this time, the test object T may pass along the opposite direction of the second direction D2.

The second sensor unit 22 may be positioned at the center side of the second inspection passage 23 to measure radiation emitted from the inspection target object T. The second sensor unit 22 may be a high-purity germanium (HPGe) detector with a built-in cooling device.

The second inspection module 20 may further include a second shielding unit 24 . The second shielding unit 24 may be provided to cover the second module body 21 to block external radiation from being introduced into the second module body 21 .

Hereinafter, the remaining components of the radioactive waste sorting device according to an embodiment of the present invention will be described in detail.

pallet(30)

The radioactive waste sorting device according to an embodiment of the present invention may further include a pallet 30 . The pallet 30 may be provided so that the inspection object (T) is seated. Although only one pallet 30 is shown in FIG. 3 for convenience of explanation, a plurality of pallets 30 may be provided as needed.

For example, the pallet 30 may include a pallet body having a rectangular plate shape. In addition, a plurality of rollers 31 are provided at the lower portion of the pallet body to move along a rail unit 40 to be described later. The roller 31 may be rotatable about an imaginary axis extending in a vertical direction. Also, the roller 31 may be able to move forward and backward.

8 is a perspective view showing a roller. As shown in FIG. 8, the roller 31 includes a housing head 32, a housing rotation shaft 33, a housing bulkhead 34, a travel rotation shaft 35, a roller wheel 36, and a travel guide 37. can do.

The housing head 32 may be positioned below the pallet body and formed in a circular shape. The housing head 32 may rotate about the housing rotation axis 33 . The housing rotation shaft 33 extends in the vertical direction and passes through the housing head 32 to be coupled to the lower portion of the pallet body. The housing bulkhead 34 may extend downward to provide a space in which the roller wheels 36 are accommodated. Both ends of the traveling rotation shaft 35 may be coupled to the housing partition wall 34 so that the roller wheels 36 can rotate between the housing partition walls 34 . The traveling guide 37 may extend downward and be partially inserted into a rail unit 40 to be described later. As a part of the driving guide 37 is inserted into the rail unit 40, the pallet 30 may be guided to move according to the shape of the rail unit 40.

Rail part (40)

The radioactive waste sorting device according to an embodiment of the present invention may further include a rail unit 40 . The rail unit 40 may be seated so that the pallet 30 is movable. For example, the pallet 30 may slide along the rail unit 40 .

The rail unit 40 may include first to fifth rails 41 , 42 , 43 , 44 , and 45 . The first to fifth rails 41, 42, 43, 44, and 45 described here are names given by dividing the entire rail part 40 for the path of movement, and only when each is formed separately and combined with each other. It doesn't mean

The first rail 41 may be a rail extending in the first direction D1 and to which the first inspection module 10 is coupled. Here, the first inspection module 10 is coupled so that the inspection target T seated on the pallet 30 moving along the first rail 41 can be inspected by the first inspection module 10 When viewed from above, it may mean that there is an overlapping area between the first rail 41 and the first inspection module 10 .

The second rail 42 may refer to a rail extending from an end of the first rail 41 in the first direction D1 along the first direction D1 .

The third rail 43 may extend along the second direction D2 from an end of the second rail 42 in the first direction D1 .

The fourth rail 44 may extend from an end of the third rail 43 in the second direction D2 in a direction opposite to the first direction D1 .

The fifth rail 45 may extend from an end of the fourth rail 44 in a direction opposite to the first direction D1 in a direction opposite to the second direction D2 . In addition, the fifth rail 45 is connected to an end of the first rail 41 in the first direction D1, and the second inspection module 20 may be coupled thereto. Here, the second inspection module 20 is coupled so that the inspection target T seated on the pallet 30 moving along the fifth rail 45 can be inspected by the second inspection module 20 When viewed from the top, it may mean that there is an overlapping area between the fifth rail 45 and the second inspection module 20 .

Also, the rail unit 40 may include sixth and seventh rails 46 and 47 . The sixth rail 46 may extend in a direction opposite to the first direction D1 from an end of the fourth rail 44 in the direction opposite to the first direction D1 . The seventh rail 47 extends from the end of the sixth rail 46 in the opposite direction to the first direction D1 and extends in the opposite direction to the second direction D2, and may be connected to the first rail 41. . Overall, the shape of the rail unit 40 may be similar to a shape obtained by rotating the shape of a blade by 90 degrees.

motor part

The radioactive waste sorting device according to an embodiment of the present invention may include a motor unit (not shown) provided to move the pallet 30 by being coupled with the pallet 30 . For example, the motor unit may be a linear motor.

The motor unit may be disposed on the motor rail. The motor rail may be spaced apart from the rail unit 40 at regular intervals and have a lattice structure. A plurality of motor units may be disposed on the motor rail to generate a driving force for transporting the pallets 30 .

More specifically, the plurality of motor units are further provided with linear motor coils for reacting with reaction members mounted on the pallets 30 and shock-proof substrates disposed in pairs at the front and rear to prevent impact between adjacent pallets 30. can In addition, a Hall sensor for detecting the position of the pallet 30 may be formed on one or more of the plurality of motor units and motor rails.

The motor unit may be a linear synchronous motor. At this time, the pallet 30 may move in a long stator manner. In more detail, a coil part corresponding to the stator of the rotary synchronous motor is installed on the motor rail and a magnet part corresponding to the rotor is installed on the pallet 30 side to generate driving force by repelling force.

but. It is not limited thereto, and the motor unit may be a linear induction motor.

9 is a diagram illustrating a case where an object to be inspected is not located in a first reference area. 10 is a diagram illustrating a case where an object to be inspected is in a first reference region.

The motor unit moves the pallet 30 at a first moving speed before the pallet 30 or the inspection object T seated on the pallet 30 is located in the first reference area inside the first inspection module 10 can make it The first reference area may refer to a position where the pallet 30 or the object T to be tested seated on the pallet 30 overlaps the sensing area of the first sensor unit 12 .

For example, the first reference area is the pallet ( 30) or the first sensor unit 12 and the pallet 30 or inspection seated on the pallet 30 from the end of the opposite direction of the first reference direction D1 of the test object T seated on the pallet 30 It may refer to the pallet 30 at the end of the overlapping of the objects T or an area up to the end of the first reference direction D1 side of the object T seated on the pallet 30 .

However, this is only an example, and the first reference area may be set within various ranges in consideration of the size of the sensing area of the first sensor unit 12 and the like.

In addition, the motor unit may move the pallet 30 at a second moving speed when the pallet 30 or the object T seated on the pallet 30 is located in the first reference area. The first moving speed may be higher than the second moving speed. This means that when the pallet 30 passes an area not related to inspection, the motor unit moves the pallet 30 at a relatively high speed, and when the pallet 30 passes an area related to inspection, the motor unit moves the pallet 30 relatively It can mean moving at a low speed.

It is necessary to move the pallet 30 at high speed for rapid inspection, but since sufficient speed for detecting radiation dose may be required during inspection, when the pallet 30 passes through an area unrelated to inspection, the motor unit The pallet 30 can be moved at a relatively high speed, and the motor unit can move the pallet 30 at a relatively low speed when the pallet 30 passes through an area related to inspection. Then, after the pallet 30 passes the first inspection module 10, the motor unit may move the pallet 30 again at the first moving speed.

Storage unit 50, transfer crane 60

As shown in FIG. 2 , the radioactive waste sorting apparatus according to an embodiment of the present invention may further include a storage unit 50 and a transfer crane 60. The storage unit 50 may be located on the side of the third rail 43 in the first direction D1 and spaced apart from the third rail 43 to store the test object T for which radioactivity measurement has been completed.

The transfer crane 60 is disposed between the third rail 43 and the storage unit 50, and the inspection target object T seated on the pallet 30 located on the third rail 43 is stored in the storage unit 50 It can be arranged to be transported to. The transfer crane 60 may move along the second direction D2 and the opposite direction. For example, the transfer crane 60 may be slidably seated on a transfer rail 61 extending in the second direction D2.

In addition, the transfer crane 60 may move the inspection target object (T) up and down. As the transfer crane 60 is movable along the second direction D2 and the opposite direction, and is formed to move the inspection object T up and down, the inspection object is placed in a predetermined position of the storage unit 50 ( T) can be stored.

Meanwhile, the storage unit 50 may include a first storage area 51 and a second storage area 52 . The first storage area 51 may be a region in which a test object T having a radioactivity emitted from the test object T exceeds a second reference amount is stored. The first storage area 51 may be an area for storing radioactive waste that cannot be self-disposable.

The second storage area 52 may be a region in which a test object T having a radioactivity emitted from the test object T is less than or equal to a second reference amount is stored. The second storage area 52 may be an area for storing radioactive waste subject to self-disposal.

Operation of a radioactive waste sorting device

Hereinafter, the operation of the radioactive waste classification device will be described in detail. 11 is a diagram illustrating a movement path of a pallet when the radioactivity of an object to be tested exceeds a first reference amount. 12 is a diagram illustrating a movement path of a pallet when the radioactivity of an object to be tested is less than or equal to a first reference amount. 13 is a diagram illustrating a movement path of a pallet when the radioactivity of an object to be tested exceeds a second reference amount. 14 is a diagram illustrating a movement path of a pallet when the radioactivity of an object to be tested is less than or equal to a second reference amount. 15 is a diagram illustrating a movement path of a pallet after storage of an object to be inspected is finished.

As shown in FIG. 11, when the pallet 30 passes the first rail 41, the radiation emitted by the test object T seated on the pallet 30 measured by the first inspection module 10 is the first If the reference amount is exceeded, the inspection object (T) may be stored in the first storage area 51 through the transfer crane 60 after being seated on the pallet 30 and passing the second rail 42 . Since the first reference amount is greater than the second reference amount, when the radioactivity emitted by the test object T exceeds the first reference amount, it can be determined that the radioactive waste is non-self-disposable radioactive waste without the need to go through the second inspection module 20. there is. In this case, the inspection target object T may be stored in the first storage area 51 through the transfer crane 60 via the second rail 42 . At this time, the inspection object (T) may pass through a portion of the third rail (43) as needed.

As shown in FIG. 12, when the pallet 30 passes the first rail 41, the radiation emitted by the test object T seated on the pallet 30 measured by the first inspection module 10 is the first If it is less than the reference amount, the test object (T) may be seated on the pallet 30 and pass through the second rail 42, the third rail 43, the fourth rail 44 and the fifth rail 45. This may mean that it is necessary to precisely inspect the inspection object T.

The second inspection module 20 may measure whether the radiation emitted by the inspection object T is equal to or less than the second reference amount when the inspection object T passes the fifth rail 45 . As shown in FIG. 13, when the radiation emitted by the test object T measured by the second test module 20 is greater than the second reference amount, the test object T is seated on the pallet 30 and placed on the second rail After passing through (42), it can be stored in the first storage area (51) through the transfer crane (60). In this case, since the inspection target object T is radioactive waste that cannot be disposed of itself, it can be stored in the first storage area 51 . At this time, the inspection object (T) may pass through a portion of the third rail (43) as needed.

As shown in FIG. 14, when the radiation emitted by the test object T measured by the second test module 20 is less than the second reference amount, the test object T is seated on the pallet 30 and the second After passing the rail 42, it can be stored in the second storage area 52 through the transfer crane 60. At this time, the inspection object (T) may pass through a portion of the third rail (43) as needed.

On the other hand, as shown in FIG. 15, the pallet 30 that delivered the inspection object T to the transfer crane 60 passes through the fourth rail 44, the sixth rail 46 and the seventh rail 47, It can be moved to the first rail 41 . Through this process, it can be seen that the pallet 30 is ready to transport another test object (T).

The radioactive waste classification device according to an embodiment of the present invention may further include a decontamination unit (not shown). The decontamination unit is coupled to the rail unit 40 and may be provided to decontaminate the inspection object T seated on the pallet 30 . The decontamination unit may use at least one of acid washing, water washing, and electrolytic polishing.

For example, the decontamination unit is coupled to the second rail 42, and when the radioactivity detected by the second inspection module 20 slightly exceeds the second reference amount, decontamination of the inspection object T is performed to inspect the inspection object. The radioactivity emitted by (T) can fall below the second reference amount.

As another example, the decontamination unit is coupled to the second rail 42, and when the radioactivity detected by the first inspection module 10 slightly exceeds the first reference amount, the inspection object T is decontaminated and inspected. The radioactivity emitted by the object T may be dropped below the first standard amount.

As another example, the decontamination unit may be coupled to the second rail 42 to reduce the radioactivity emitted by the test object T by repeating the decontamination of the test object T to the second reference amount.

Nuclear Facility Decommissioning Waste Sorting System

Hereinafter, a nuclear facility dismantling waste classification system including the radioactive waste classification device described above based on the above descriptions and drawings will be described in detail. Since the contents of the radioactive waste classification device have been described above, a detailed description thereof will be omitted.

The nuclear facility dismantling waste classification system may include a radioactive waste classification device and a control unit 70 (FIG. 2).

The radioactive waste classification device may be provided to measure the radioactivity of the nuclear facility dismantling waste, which is waste generated by dismantling the nuclear facility, and classify the nuclear facility dismantling waste according to a predetermined standard.

The control unit 70 may be provided to control the radioactive waste sorting device. For example, the control unit 70 may be provided to control the inspection of the first inspection module 10 . As another example, the controller 70 may be provided to control the inspection of the second inspection module 20 . As another example, the control unit 70 may be provided to control the movement of the pallet 30 by controlling the motor unit.

The control unit 70 may include a processor 71 and a memory 72. The processor 71 may include a microprocessor such as a Field Programmable Gate Array (FPGA), an Application Specific Integrated Circuit (ASIC), or a Central Processing Unit (CPU). The memory 72 may store control instructions (instructions) that are the basis for generating in the processor 71 instructions for determining whether to operate the radioactive waste classification device. The memory 72 may be a data store such as a hard disk drive (HDD), solid state drive (SSD), volatile media, or non-volatile media.

The radioactive waste classification device may include a first inspection module 10 , a second inspection module 20 and a storage unit 50 . The first inspection module 10 may be provided to measure whether radioactivity emitted from nuclear facility dismantling waste is equal to or less than a predetermined first reference amount.

The second inspection module 20 re-inspects the nuclear facility dismantling waste when the radioactivity measured by the first inspection module 10 and emitted from the nuclear facility dismantling waste is equal to or less than the first reference amount, and determines that the radioactivity emitted from the nuclear facility dismantling waste is the first. It may be provided to measure whether it is less than or equal to a second reference amount smaller than the reference amount.

The storage unit 50 may be provided to classify and store nuclear facility dismantling waste based on the test results of the first test module 10 and the second test module 20 .

Nuclear Facility Dismantling Waste History Management System

16 is a diagram conceptually showing the configuration of a nuclear facility dismantling waste history management system according to an embodiment of the present invention. 17 is a diagram for explaining the operation of the nuclear facility dismantling waste history management system according to an embodiment of the present invention.

Referring to FIG. 16, the nuclear facility dismantling waste history management system according to an embodiment of the present invention includes a first inspection module 10, a second inspection module 20, a transfer crane 60, a control unit 70, It may include an electronic tag 81, a location determination device 82, a terminal 84, and a management server 84.

The first inspection module 10 may be the inspection module 10 shown in FIGS. 1 and 2, and the inspection object T emits while the inspection object T moves along the first direction D1. Whether the radioactivity is less than or equal to the first reference amount can be measured.

In this case, the first inspection module 10 may provide the measured radiation information to at least one of the control unit 70 and the management server 84 through a network.

The second inspection module 20 may be the inspection module 20 shown in FIGS. 1 and 2, and when the radiation emitted from the inspection object T measured by the first inspection module 10 is equal to or less than the first reference amount. , It is possible to measure whether or not the radioactivity emitted by the test object T is equal to or less than the second reference amount by re-examining the test object T. The second reference amount may have a smaller value than the first reference amount.

At this time, the second inspection module 20 may provide the measured radioactivity information to at least one of the control unit 70 and the management server 84 through a network.

The control unit 70 may be the control unit 70 shown in FIG. 2, and includes the first inspection module 10, the second inspection module 20, the storage unit 50, and the transfer crane 60 for radioactive waste. The sorting device can be controlled.

For example, the control unit 70 can control the inspection of the first and second inspection modules 10 and 20, and can control the movement of the pallet 30 and the transfer crane 60 by controlling the motor unit. there is.

In addition, the controller 70 classifies the test object T according to the measured radioactivity information provided from the first and second test modules 10 and 20, and stores the classified test object T in the storage unit 50. can be stored in

For example, the controller 70 may transfer the test object T by controlling the movement of the pallet 30 according to the measured radioactivity information provided from the first and second test modules 10 and 20 . In addition, the controller 70 classifies the test object T according to the measured radioactivity information of the first and second test modules 10 and 20, and controls the transfer crane 60 to store the test object T. It may be classified and stored in the first storage area 51 or the second storage area 52 of the unit 50 .

The storage unit 50 may include a first storage area 51 for storing non-self-disposable radioactive waste and a second storage area 52 for storing radioactive waste subject to self-disposal.

At this time, the control unit 70 may provide information on the stored location (eg, the first storage area 51 or the second storage area 52) of the test object T to the management server 84 through the network. there is.

The electronic tag 81 may be configured to enable location tracking based on Global Positioning System (GPS) and Ultra Wide Band (UWB), and to be attached to a measuring container in which radioactive waste may be contained.

At this time, the electronic tag 81 may be assigned an identification number, and may provide location information of the electronic tag 81 to the location determining device 82 through a network.

The location determining device 82 can determine the location of the electronic tag 81 based on the identification number of the electronic tag 81, and transmits the determined location information of the electronic tag 81 to the control unit 70 and the controller 70 through a network. At least one of the management servers 84 may be provided.

The terminal 83 may be connected to the management server 84 through a network, and may provide radioactive waste information to the management server 84 or receive radioactive waste information stored in the management server 84 .

For example, the terminal 83 can determine the identification number assigned to the electronic tag 81, the name of the dismantled power plant, the dismantling time (date, time), the name of the building, the type of dismantled waste, sample radioactivity information, and sample radioactivity. Radioactive waste information such as the measurement time (date, time) and the determined identification number may be provided to the management server 84.

In addition, the terminal 83 can determine the identification number assigned to the electronic tag 81, and the radioactive waste information according to the identified identification number among the radioactive waste information stored in the management server 84 is transmitted from the management server 84. can be provided. At this time, the radioactive waste information provided by the terminal 83 from the management server 84 includes first and second inspection information in addition to generation source information such as dismantling time, power plant name, building name, dismantling waste type, sample radioactivity information, and sample radioactivity measurement time. It may further include radioactivity information measured by the modules 10 and 20 and location information stored in the storage area 50 .

The management server 84 transmits radioactivity measurement information from the first and second inspection modules 10 and 20 through a network, location information from the location determination device 82, radioactive waste storage location information from the control unit 70, and radioactive waste information including hatch time (date, time) from the terminal 83, power plant name, building name, dismantling waste type and sample radioactivity information, and sample radioactivity measurement time (date, time) can be classified and stored by identification number. there is.

In addition, the management server 84 may provide radioactive waste information corresponding to an identification number among stored radioactive waste information to the terminal 83 through a network.

16, the first inspection module 10, the second inspection module 20, the transfer crane 60, the control unit 70, the electronic tag 81, the position determination device 82, the terminal 84, and The operation of the nuclear facility dismantling waste history management system including the management server 84 will be described with reference to FIG. 17 .

As shown in FIG. 17, the operation of the nuclear facility dismantling waste history management system according to an embodiment of the present invention includes a measurement sample preprocessing process (S1), a measurement sample contamination evaluation and classification process (S2), and a transportation storage process (S3). ) can be explained separately.

Nuclear facility decommissioning waste may include concrete and soil.

Since concrete (C) has a large particle size, it can be crushed into a certain size through a crusher and then put into the measuring containers (C1, C2, ..., Cn) through a discharger.

In the case of the soil (S), it may be contained in the measuring container (S1, S2, ..., Sn) through the discharger.

An electronic tag 81 to which an identification number is assigned may be attached to a measuring container containing concrete C and soil.

As described above, the measurement sample preprocessing process (S1) includes the process of shredding nuclear facility dismantling waste through a crusher so that it can be put in a measuring container, and putting the waste shredded to a certain size into a measuring container, and identifying the waste in the measuring container. A process of attaching the numbered electronic tag 81 may be included.

The measurement sample preprocessing process S1 may include a preprocessing process (eg, drying preprocessing) in which nuclear facility dismantling waste is treated before being put into a measuring container to which the electronic tag 81 is attached.

In addition, when the electronic tag 81 is attached to the measuring container in the measurement sample preprocessing process (S1), the dismantling time (date and time) of the nuclear facility dismantling waste generated through the terminal 83, the name of the power plant, the building name, and the dismantling waste Information on the source, such as type, sample radioactivity information, and sample radioactivity measurement time (date, time), may be transmitted to the management server 84 and stored for each identification number.

The measurement sample contamination evaluation and classification process (S2) may include a process in which the waste contained in the measurement container in the measurement sample pretreatment process (S1) is transferred to a radioactive waste classification device, and contamination is assessed and classified by the radioactive waste classification device. .

The measurement sample contamination evaluation and classification process (S2) may include a high-speed mode contamination evaluation and classification process (S2-1) and a precise mode contamination evaluation and classification process (S2-2). At this time, the measurement sample contamination evaluation and classification process (S2) may further include a decontamination process (S2-3).

In the high-speed mode contamination evaluation and classification process (S2-1), the radioactivity of the waste contained in the measurement container, that is, the inspection object T, is measured by the first inspection module 10, and classified according to the measurement result, and precision mode contamination evaluation and A sorting process (S2-2) or a transportation storage process (S3) may be performed.

For example, in the high-speed mode contamination evaluation and classification process (S2-1), precise mode contamination evaluation and classification are performed according to whether or not the radioactivity of the test object T measured by the first inspection module 10 is less than or equal to the first reference amount. Step S2-2 may be performed, or transport storage step S3 may be performed.

In more detail, for example, when the radioactivity of the test object T measured by the first test module 10 in the high-speed mode contamination evaluation and classification process (S2-1) is less than the first reference amount, for the test object T A precise mode contamination evaluation and classification process (S2-2) can be performed.

On the other hand, when the radioactivity of the test object T measured by the first inspection module 10 in the high-speed mode contamination evaluation and classification process (S2-1) exceeds the first reference amount, the test object T is self-disposal. A transport storage process (S3) of being classified as impossible radioactive waste and stored in the first storage area 51 of the storage unit 50 may be performed.

In the high-speed mode contamination evaluation and classification process (S2-1), the location of the electronic tag 81 determined by the location determination device 82, that is, the location of the test object T is the location of the first test module 10 and If matched, the radioactivity of the test object T is measured by the first test module 10, and the measured result may further include a process of transmitting to the management server 84.

In the precise mode contamination evaluation and classification process (S2-2), the radioactivity of the inspection object T is measured through the second inspection module 20 after the high-speed mode contamination evaluation and classification process (S2-1), and according to the measurement result A transport storage process 3 in which the inspection object T is stored in the first storage area 51 or the second storage area 52 may be performed.

For example, when the radioactivity of the test object T measured by the second test module 20 in the precise mode contamination evaluation and classification process (S2-2) exceeds the second reference amount, the test object T itself A transport storage process (S3) in which the radioactive waste is classified as non-disposable radioactive waste and stored in the first storage area 51 of the storage unit 50 may be performed.

On the other hand, if the radioactivity of the test object T measured by the second test module 20 in the precise mode contamination evaluation and classification process (S2-2) is less than the second reference amount, it is classified as self-disposable radioactive waste and stored A transport storage process (S3) to be stored in the second storage area 52 of the unit 50 may be performed.

In the precision mode contamination evaluation and classification process (S2-2), the location of the electronic tag 81 determined by the location determination device 82, that is, the location of the test object T is determined by the location of the second test module 20 and If matched, the radioactivity of the test object T is measured by the second test module 20, and the measured result may further include a process of transmitting to the management server 84.

If the radioactivity of the test object (T) measured in the high-speed mode contamination evaluation and classification process (S2-1) and the precision mode contamination evaluation and classification process (S2-2) is exceeded within the fine range set based on the reference amount, the inspection target (T) may be subjected to a decontamination treatment process (S2-3) for decontamination.

For example, in the high-speed mode contamination evaluation and classification process (S2-1), if the measured radioactivity of the test object (T) exceeds the first standard amount, but the excess radioactivity is within the set fine range, acid washing, water washing, electrolysis A decontamination treatment process ( S2 - 3 ) of decontamination of the inspection object T may be performed by at least one method during polishing. Thereafter, a high-speed mode contamination evaluation and classification process (S2-1) may be performed again on the decontaminated inspection object T.

In addition, in the precision mode contamination evaluation and classification process (S2-2), the measured radioactivity of the test object (T) exceeds the second standard amount, but the excess radioactivity is within the set fine range during acid washing, water washing, and electrolytic polishing A decontamination treatment process ( S2 - 3 ) of decontamination of the test object (T) in at least one method may be performed. Thereafter, a precise mode contamination evaluation and classification process (S2-2) may be performed again on the decontaminated inspection object T.

Transport storage process (S3) is the first and second inspection module (10, 20) according to the measurement result of the radiation of the test object (T) measured by the test object (T) in the first storage area 51 or the second A process of storing in the storage area 52 may be included.

In the transportation storage process (S3), when the radioactivity of the inspection object T measured by the first inspection module 10 exceeds the first reference amount, the inspection object T is stored in an area for storing non-self-disposable waste, that is, A process of storing in the first storage area 51 may be included.

In the transport storage process (S3), when the radioactivity of the inspection object T measured by the second inspection module 10 exceeds the second reference amount, the inspection object T is stored in an area for storing non-self-disposable waste, that is, A process of storing in the first storage area 51 may be included. At this time, the test object T stored in the first storage area 51 means that it is finally classified as radioactive waste, and the first storage area 51 may be a temporary storage for radioactive waste.

In the transport storage process (S3), when the radiation capacity of the test object (T) measured by the second test module 10 is less than the second reference amount, the test object (T) is stored in an area for storing self-disposable waste, that is, the second A process of storing in the storage area 52 may be included. At this time, the test object T stored in the second storage area 52 means that it is finally classified as a self-disposal object, and the second storage area 52 may be a self-disposal warehouse.

In the transportation and storage process (S3), the inspection object (T) is classified as a self-disposal object or radioactive waste and stored in the first storage area 51 or the second storage area 52 by the transfer crane 60, and the inspection object (T) may further include a process of transmitting the stored location information to the management server 84.

The management server 84 determines the measurement results of the first and second inspection modules 10 and 20 and the inspection object (for each identification number of the electronic tag 84 attached to the inspection object T, that is, the measuring container containing the waste). The storage location of T) can be stored.

Therefore, the management server 84 may store the inspection object T for each identification number, that is, the source of dismantling waste, the type of radioactivity, the measured amount of radioactivity, and the storage location. In addition, when the terminal 83 comes into contact with the electronic tag 81, the terminal 83 stores stored information matched with the identification number of the contacted electronic tag 81 from the management server 84 (source of radiation, type of radiation, measured amount of radiation, storage location), and may be transmitted to the user as at least one of visual information and auditory information.

In addition, the user may be provided with information about nuclear power plant dismantling waste stored in the management server 84 by accessing the management server 84 through a network using devices other than the terminal 83. In addition, the present invention In the nuclear facility dismantling waste history management system according to an embodiment, the location of nuclear power plant dismantling waste is detected in real time by an electronic tag and a location determination device, the detected location information can be stored in a management server, and the user can The location of dismantled waste can be provided in real time.

For example, when the object T to be inspected does not reach the position of the first inspection module 10, the user may be provided with information that the object T to be inspected is being transported for contamination evaluation in a high-speed mode.

When the object T to be inspected reaches the position of the first inspection module 10, the user may be provided with information indicating that the object T to be inspected is being evaluated for contamination in a high-speed mode.

When the object to be inspected T1 moves to the position of the second inspection module 20 via the first inspection module 10, the user may be provided with information indicating that it is being transported for precision mode contamination evaluation.

When the inspection object T reaches the position of the second inspection module 20, the user may be provided with information indicating that the inspection object T is being evaluated for contamination in a precise mode.

When the inspection object T reaches the position of the transfer crane 60, the user receives information that the radioactivity measurement of the inspection object is completed and is being stored in one of the first and second storage areas 51 and 52. can be provided.

When the inspection target object T is completely stored in any one of the first and second storage areas 51 and 52, the user may be provided with information on the storage area where the inspection object T is stored.

As described above, the nuclear facility dismantling waste history management system according to an embodiment of the present invention provides a basis for managing the history of nuclear power plant dismantling waste and ensuring a radiologically acceptable level of safety for the dismantling waste, It can improve the reliability of waste management, solve social anxiety, and improve public confidence in nuclear power projects.

The above description is merely an example of the technical idea of the present invention, and various modifications and variations can be made to those skilled in the art without departing from the essential characteristics of the present invention. Therefore, the embodiments disclosed in the present invention are not intended to limit the technical spirit of the present invention, but to explain, and the scope of the technical spirit of the present invention is not limited by these embodiments. The protection scope of the present invention should be construed according to the claims below, and all technical ideas within the equivalent range should be construed as being included in the scope of the present invention.

10: first inspection module
11: first inspection module body
12: first sensor unit
12a: 1-1 sensor member
12b: 1-2 sensor member
13: first inspection passage
14: first shielding unit
20: second inspection module
21: second inspection module body
22: second sensor unit
23: second inspection passage
24: second shielding unit
30: pallet
31: roller
32: housing head
33: housing rotation axis
34: housing bulkhead
35: driving rotation axis
36: roller wheel
37: driving guide
40: rail part
41: first rail
42: second rail
43: third rail
44: fourth rail
45: fifth rail
46: 6th rail
47: seventh rail
50: storage unit
51: first storage area
52: second storage area
60: transfer crane
61: transport rail
70: control unit
71: processor
72: memory
D1: first direction
D2: second direction
T: Inspection object

Claims (12)

a position determination device for determining a position of an electronic tag attached to a measuring container containing an object to be inspected;
A first test module for measuring the radioactivity emitted by the test object;
a transfer crane storing the inspection object in a first storage area or a second storage area according to the measurement result of the first inspection module; and
a management server that stores a measurement result of the first inspection module for each identification number assigned to the electronic tag and a location where the inspection object is stored by the transfer crane;
A nuclear facility dismantling waste history management system comprising a. The method of claim 1,
The first inspection module,
Nuclear facility dismantling waste history management system, characterized in that for determining whether the radioactivity emitted by the inspection object is less than a first reference amount. The method of claim 2,
When the radioactivity emitted by the test object is less than the first reference amount, the nuclear facility dismantling waste history management system further comprising a second inspection module for determining whether the radioactivity emitted by the test object is less than the second reference amount . The method of claim 3,
The management server,
The nuclear facility dismantling waste history management system, characterized in that for storing the measurement result of the first inspection module and the measurement result of the second inspection module together with the location where the inspection object is stored for each identification number assigned to the electronic tag. The method of claim 3,
The transfer crane,
The nuclear facility dismantling waste history management system, characterized in that for storing the inspection object in the second storage area when the radioactivity measured by the second inspection module is less than the second reference amount. The method of claim 3,
The transfer crane,
Storing the test object in the first storage area when the radioactivity measured by the first inspection module exceeds the first reference amount or the radioactivity measured by the second inspection module exceeds the second reference amount Dismantling waste history management system for nuclear facilities. The method of claim 1,
The management server,
The nuclear facility dismantling waste history management system, characterized in that for storing the measurement results of the first inspection module provided after the inspection object reaches the location of the first inspection module for each identification number. The method of claim 4,
The management server,
The nuclear facility dismantling waste history management system, characterized in that for storing the measurement results of the second inspection module provided after the inspection object reaches the location of the second inspection module for each identification number. The method of claim 1,
The management server,
The nuclear facility dismantling waste history management system, characterized in that for storing the hatch time, generation source, waste type, sample radioactivity information, and sample radioactivity measurement time of the inspection object for each identification number. attaching an electronic tag to a measuring container containing an object to be inspected;
Storing source, waste type, and sample radioactivity information of the test target for each identification number assigned to the electronic tag in a management server;
storing the measured radioactivity information of the test object from the first test module in the management server when the location of the electronic tag reaches the location of the first test module;
storing the measured radioactivity information of the test object from the second test module in the management server when the location of the electronic tag reaches the location of the second test module;
and storing the location where the inspection object is stored in the management server when the location of the electronic tag reaches the first storage area or the second storage area. The method of claim 10,
The management server,
The radioactivity information measured from the first and second inspection modules for each identification number of the electronic tag and the location where the inspection object is stored are stored. The method of claim 10,
A method for managing records of dismantled wastes from nuclear facilities, comprising a position determination device for determining the position of the electronic tag.

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