KR102350093B1 - Defective spent fuel handling container - Google Patents

Abstract

The present invention relates to a container for spent nuclear fuel, and more particularly, to a container for handling defective spent nuclear fuel having means for safely handling it like general spent fuel even when handling is difficult, such as a defective spent fuel, wherein the nuclear fuel assembly comprises The body 10 having an acceptable length and volume, coupled to the upper end of the body 10, the upper coupling body 20a, 20b installed with a removable opening and closing member for opening or closing the inside of the body 10, and the body 10 A mesh that is coupled to the lower portion to seal the lower portion of the body 10; includes, and allows the release of gas while preventing the outflow of radioactive particles to the upper assemblies 20a and 20b and the lower assembly 30 It is intended to provide a defective spent fuel handling container in which a member is installed.

Description

Defective spent fuel handling container

The present invention relates to a container for spent nuclear fuel for safely handling spent nuclear fuel in a processing process for wet or dry storage. It relates to a defective spent fuel handling container having means.

The spent nuclear fuel assembly withdrawn after being burned out of the nuclear reactor contains a huge amount of radioactive material generated by the nuclear fission reaction. Because these radioactive materials can cause great harm to people and the environment, the spent fuel assembly must remain in good health (ie, defect-free) until safe disposal or disposal.

Accordingly, in accordance with Article 42 Paragraph 1 of the Enforcement Decree of the Atomic Energy Act, Article 19 of the Enforcement Rule, and Annex Table 5 of Article 120 of the Enforcement Rule, domestic nuclear power plants take out the spent nuclear fuel assembly from the nuclear reactor and inspect it during the periodic planned preventive maintenance period. The results are recorded and kept. Currently, in domestic nuclear power plants, the shape of the spent fuel assembly performed during the planned preventive maintenance period, that is, whether defects occur on the surface of the spent fuel assembly, is mainly inspected by visual and ultrasonic inspection.

Due to this risk of defective spent fuel, for dry transportation and storage, it is necessary to develop a separate transport and storage container that reflects the characteristics of a dry environment and defective spent fuel.

According to the US NRC's Interim Staff Guidance (ISG), fuel classified as damaged fuel is required to be stored in metal bins or cells designed to meet critical, shielding, thermal and structural requirements.

In particular, in the case of defective spent nuclear fuel, as a pre-treatment for dry storage, it should be possible to prevent the leakage of foreign substances in the form of fine particles while discharging the gas generated during the internal drying process. Safe handling should be possible.

However, currently, as a technology related to defective spent fuel, research is focused only on the technology to determine the presence or absence of defects in handling containers or spent fuel, and the technology for transport and handling containers that can safely handle defective spent fuel is insufficient. to be.

Patent Registration Publication No. 10-1002720 (Announcement Date: 2010. 12. 21)

Accordingly, an object of the present invention is to provide a transport and handling container capable of conveniently storing defective spent nuclear fuel so that it can be safely handled in a handling process including a transport and drying process for storage of the defective spent nuclear fuel.

The defective spent fuel handling container according to the present invention for achieving this object includes a body 10 having a length and a volume that can accommodate a nuclear fuel assembly, and is coupled to the upper end of the body 10, and the inside of the body 10 is opened or It includes an upper assembly (20a) provided with a detachable opening and closing member for sealing, and a lower assembly (30) coupled to the lower portion of the body (10) to seal the lower portion of the body (10), the upper assembly (20a, 20b) and the lower assembly ( 30) is provided with a mesh member that allows the release of gas while preventing the outflow of radioactive particles.

Here, the mesh member is formed with a width of one eye of the mesh of 1 mm or less, and consists of an upper mesh 28 installed in the upper assembly 20a, 20b and a lower mesh 32 installed in the lower assembly 30. The upper surface of the upper mesh 28 or the lower surface of the lower mesh 32, which is the surface on which the mesh member is exposed, is preferably provided with an upper perforated plate 29 and a lower perforated plate 33 each having a plurality of through-holes perforated therein. 28) is installed in contact with the upper surface or the lower surface of the lower mesh 32.

And the detachable opening/closing member is preferably a plurality of fastenings formed on the side wall 21 of the upper assembly 20a, 20b such that the rotating plate 24 is formed with a plurality of blades protruding laterally, and the plurality of blades are respectively inserted therein. It includes a slot 211 for, and when the rotating plate 24 is rotated so that a plurality of wings are inserted into the fastening slot 211, the detachable opening and closing member seals the upper end of the body 10, and the rotating plate 24 is connected to a plurality of When the blade is rotated so as to be separated from the fastening slot 211 , the detachable opening and closing member may open the upper end of the body 10 .

In this case, a fastening bolt 231 assembled to the rotating plate 24 is preferably provided at the center of the rotating plate 24, and the rotating plate 24 is rotated by rotating the fastening bolt 231 so that the plurality of blades are fastened with a slot for fastening. The rotating plate 24 may be fixed to each of the 211 .

At this time, the rotating plate 24 is disposed on the upper surface of the upper perforated plate 29, and the fastening bolt 231 is installed in a form penetrating both the center of the rotating plate 24 and the upper perforated plate 29, preferably the fastening bolt ( A lock pin 233 is fixedly connected to the lower portion of the 231), and a lock pin hole 251 into which the lock pin 233 can be inserted is formed in the upper perforated plate 29. When the fastening bolt 231 is changed downward, the lock pin 233 As the lock pin 233 is separated from the lock pin hole 251 while changing together with the fastening bolt 231 , the fastening bolt 231 and the rotating plate 24 are in a rotatable state.

Here, preferably, a clasp 232 is fixedly connected to the upper portion of the fastening bolt 231, and a clasp hole 241 into which the clasp 232 can be inserted is formed in the rotary plate 24, and the fastening bolt 231 is lowered. When variable, the latch 232 is changed downward together with the fastening bolt 231 and the latch 232 is inserted into the latch hole 241, so that the fastening bolt 231 and the rotating plate 24 are integrally rotatable together. do.

In addition, on the bottom surface of the head of the fastening bolt 231, a clasp 232 fixing plate 25 is installed along the center circumference of the fastening bolt 231, and the clasp 232 is fixedly installed on the bottom surface of the clasp 232 fixing plate 25. , Preferably, a return spring 234 is installed between the upper surface of the rotating plate 24 and the lower surface of the clasp 232 and the lower surface of the fixing plate 25 so as to surround the body of the fastening bolt 231, so that the fastening bolt 231 is the pressure of the upper part. The lock pin 233 is inserted into the lock pin hole 251 while the lock pin 233 is inserted into the lock pin hole 251, and the clasp 232 can be withdrawn from the clasp hole 241 while descending due to the lowering and the upper pressure is released. .

And, in the upper portion of the upper assembly (20a, 20b), preferably, a through hole through which equipment for lifting the upper end fixture (WHU, CEU) of the nuclear fuel assembly embedded in the body 10 can be fastened is formed, and the upper assembly ( The same slot as the fastening slot 211 is formed on the outer surface of the side wall 21 of 20a, 20b) and an external panel 213 integrally coupled to the upper part of the body 10 is installed, and the external panel 213 A sealing 212 is installed along the periphery of the fastening slot 211 between the outer surface of the side wall 21 of the upper assembly 20a, 20b, so that foreign substances from the inside of the body 10 enter the upper part through the fastening slot 211. The combination (20a, 20b) is prevented from flowing into the inside, and when the blade of the rotating plate 24 is separated from the fastening slot 211 due to the rotation of the rotating plate 24, the rotating plate 24, the perforated plate, and the upper mesh ( 28) including the upper coupling body (20a, 20b) is detachable from the body (10).

The defective spent fuel handling container according to the present invention is capable of discharging steam during the drying process while preventing foreign substances from leaking so that it can safely handle defective spent fuel that is difficult to apply to the normal post-treatment and transport process of spent nuclear fuel. Since it can be easily combined with the spent nuclear fuel, there is an effect that the transport and treatment process can be easily performed.

1 is a cross-sectional perspective view of a defective spent fuel handling container according to the present invention;
2 is a comparative view of first and second embodiments of a defective spent fuel handling container according to the present invention;
Figure 3a is a perspective view showing a first embodiment of the upper assembly;
3b is a partial enlarged view of 3a;
Fig. 3c is a plan view of Fig. 3a;
3D and 3F are real pictures of the first embodiment;
Figure 4a is a perspective view showing a second embodiment of the upper assembly;
Fig. 4b is a partially enlarged view of Fig. 4a;
Figure 5a is an enlarged cross-sectional perspective view of the lower assembly in Figure 1;
Figure 5b is a photograph showing the bottom of Figure 5a,

Specific structural or functional descriptions presented in the embodiments of the present invention are only exemplified for the purpose of describing embodiments according to the concept of the present invention, and the embodiments according to the concept of the present invention may be implemented in various forms. In addition, it should not be construed as being limited to the embodiments described herein, and it should be understood to include all modifications, equivalents and substitutes included in the spirit and scope of the present invention.

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

For reference, the defective spent nuclear fuel handling container according to the present invention can be divided into the first embodiment and the second embodiment according to the shape of the nuclear fuel assembly accommodated therein. The first embodiment is a handling container for a Westinghouse type (WH type) nuclear fuel assembly shown on the left side of FIG. 2A , and the second embodiment is a handling container for a CE type nuclear fuel assembly shown on the right side of FIG. 2A .

The spent nuclear fuel handling container according to the present invention includes a body 10 , upper assemblies 20a and 20b , and a lower assembly 30 .

As shown in FIG. 1 , the body 10 is manufactured to have an acceptable length and volume for the nuclear fuel assembly (WHF) of the first embodiment. However, the body 10 in the second embodiment and the body 10 in the first embodiment may be manufactured identically to each other.

The lower assembly 30 is a member coupled to the lower portion of the body 10 to seal the lower portion of the body 10 .

The upper assemblies 20a and 20b are detachable opening/closing members for opening or closing the interior of the body 10 by being coupled to the upper portion of the body 10 after the nuclear fuel assembly is accommodated in the body 10 . Since the upper assemblies 20a and 20b are located on the upper part of the upper fixture of the nuclear fuel assembly inserted into the body 10, the structure and shape may vary depending on the type of the upper fixture embedded in the body 10, as will be described later. Some may vary. Hereinafter, the present invention will be described by dividing it into a first embodiment and a second embodiment according to the type of the upper fixture to be built into the body 10 .

<First embodiment>

The first embodiment is an embodiment in which the upper assembly 20a manufactured in a shape corresponding to the Westinghouse type when the upper fixture of the nuclear fuel assembly embedded in the body 10 is coupled to the upper portion of the body 10 . A first embodiment is shown in detail in Figs. 3a to 3f.

However, since most of the features of the present invention described in the first embodiment overlap with the second embodiment, it can be seen that all of the features are equally applied to the second embodiment except for some features.

Both the upper assembly 20a and the lower assembly 30 coupled to the upper part of the body 10 convert the defective spent nuclear fuel assembly to normal spent nuclear fuel in a processing process for preparing the final storage of the defective spent nuclear fuel assembly. It is made to be treated like an aggregate.

Therefore, the upper mesh 28 and the lower mesh 32 are coupled to the upper assembly 20a and the lower assembly 30, respectively, so that water vapor or gas inside can be discharged when the internal vacuum drying is performed in the treatment process.

In addition, an upper perforated plate 29 and a lower perforated plate 33 are respectively coupled to the upper portion of the upper mesh 28 and the lower portion of the lower mesh 32 to support the mesh member not to be damaged in the process of discharging internal steam.

The upper perforated plate 29 is well shown in the photo of FIG. 3D and the lower perforated plate 33 is well shown in the picture of FIG. 5A and the photo of FIG. 5B . Both the upper and lower perforated plates 33 have a plurality of through-holes formed in a portion in contact with the mesh member, so that vapor or gas is easily discharged.

The upper assembly 20a corresponds to the lid of the body 10 . However, a handling container for a defective nuclear fuel assembly must satisfy the following three requirements. First, since it is a container for handling defective nuclear fuel, leakage of radioactive particles out of the container must be thoroughly prevented. Second, as described above, while the leakage of polluted particles is prevented, the discharge of gases and vapors must be made freely. Third is the ease of handling. In particular, if the sealing process and the container structure are too complicated because it is a defective nuclear fuel assembly, there may be concerns about the leakage of radioactive particles.

In order to satisfy this requirement, in the embodiment according to FIGS. 3A to 3F , the configuration of the upper assembly 20a that can be stably opened and closed by a single operation is disclosed.

3A and 3B, the detachable opening and closing member is provided with a rotating plate 24 having a plurality of wings protruding laterally, and a side wall 21 of the upper assembly 20a so that the plurality of wings are respectively inserted. When a plurality of fastening slots 211 formed in the rotating plate 24 are rotated so that the plurality of wings are inserted into the fastening slots 211, the detachable opening and closing member seals the upper end of the body 10, and the rotating plate ( 24) is rotated so that the plurality of wings are separated from the fastening slot 211 , the detachable opening and closing member is configured to open the upper end of the body 10 .

At this time, a fastening bolt 231 assembled to the rotating plate 24 is provided at the center of the rotating plate 24 as shown in FIG. 3b so that the rotation of the rotating plate 24 can be easily operated, and the fastening bolt 231 is rotated When the plurality of blades are respectively coupled to the fastening slots 211 by rotating the rotating plate 24, the rotating plate 24 is fixed after each of the plurality of wings is inserted into their respective fastening slots 211.

However, if the rotating plate 24 is rotated together whenever the fastening bolt 231 is rotated, there is a risk that the upper coupling body 20a may be opened by erroneous manipulation of the fastening bolt 231 . In order to solve this problem, in FIG. 3B , a latch 232 and a lock pin 233 that are variable together in conjunction with the fastening bolt 231 are provided.

The uppermost assembly 20a is provided with an uppermost structure 26 corresponding to the shape of the uppermost fixed body of the nuclear fuel assembly embedded in the body 10 . More specifically, as shown in FIG. 3b , the upper structure 26 and the side wall 21 formed at the bottom along the edge of the upper structure 26 on the lower surface of the upper structure 26 and the side wall 21 An upper perforated plate 29 for blocking between the inside of the body 10 and the upper structure 26 is provided at the lower portion, and an upper mesh 28 is provided on the bottom surface of the upper perforated plate 29 . For reference, the upper perforated plate 29 is not separately shown in FIGS. 3A and 3B, and the upper mesh 28 is installed in a state of being inserted into the fixing plate 25 integrally formed with the side wall as shown in FIG. 3B. have.

The rotating plate 24 is installed on the upper surface of the fixed plate 25 as shown in FIG. 3B , and the fastening bolt is installed in the center of the rotating plate 24 . At this time, the fastening bolt 231 is installed in a form penetrating both the center of the rotating plate 24 and the fixed plate 25 , and a lock pin 233 is fixedly connected to the lower portion of the fastening bolt 231 , and the lock pin is fixed to the fixed plate 25 . A lock pin hole 251 into which 233 can be inserted is formed, and when the fastening bolt 231 is changed downward, the lock pin 233 is changed together with the fastening bolt 231 and the lock pin 233 is moved from the lock pin hole 251. By being separated, the fastening bolt 231 and the rotating plate 24 are in a rotatable state.

In addition, a latch 232 is fixedly connected to the upper portion of the fastening bolt 231 , and a latch hole 241 into which the latch 232 can be inserted is formed in the rotating plate 24 , and when the fastening bolt 231 is changed downward, the latch As the 232 is changed downward together with the fastening bolt 231 , the latch 232 is inserted into the latch hole 241 , so that the fastening bolt 231 and the rotating plate 24 are integrally rotatable together.

At this time, on the bottom surface of the head of the fastening bolt 231, a latch 232 fixing plate 25 is installed along the center circumference of the fastening bolt 231, and the latch 232 is fixedly installed on the bottom surface of the latch 232 fixing plate 25. , A return spring 234 is installed between the upper surface of the rotating plate 24 and the lower surface of the clasp 232 and the lower surface of the fixing plate 25 to surround the body of the fastening bolt 231, so that the fastening bolt 231 is lowered due to the pressure of the upper part. Then, when the upper pressure is released, the lock pin 233 is inserted into the lock pin hole 251 while rising by the elastic force of the return spring 234 , and the clasp 232 is withdrawn from the clasp hole 241 .

Therefore, according to the embodiment of Fig. 3b, before the fastening bolt 231 is pressed, the rotating plate 24 is in a state in which the lock pin 233 is inserted into the lock pin hole 251, so the fastening bolt 231 cannot be rotated and is fixed, When the fastening bolt 231 is pressed, only then does the lock pin 233 descend and come out of the lock pin hole 251, and the clasp 232 is also lowered and inserted into the clasp hole 241 to enable rotation of the rotating plate 24. .

As a result, according to the embodiment of FIGS. 3A to 3F, the handling container can be opened and closed with a single pressing and rotation operation, enabling rapid and stable handling of defective spent nuclear fuel, increasing safety and further improving the processing process for storage can proceed quickly.

When the body 10 is opened due to the rotation of the rotating plate 24, the entire upper assembly 20a acts as a lid, so when the body 10 is opened by the rotation of the rotating plate 24, the upper mesh 28 and the fixed plate (25), the side plate, the rotating plate 24, and the upper structure can all be separated from the body 10 integrally.

At this time, a through hole is formed in the upper portion of the upper assembly 20a to which equipment for lifting the upper fixture of the nuclear fuel assembly embedded in the body 10 can be fastened. In particular, in the case of the first embodiment, the upper assembly 20a is formed in a shape corresponding to the upper assembly of the Westinghouse-type nuclear fuel assembly as shown in FIGS. 2A and 2B in which the upper assembly is built in. It has a structure that can be lifted with the lifting and handling mechanism shown.

Therefore, the through hole is formed to communicate with the guide hole formed in the upper fixed body of the nuclear fuel assembly. In addition, since a step is formed between the uppermost structure 26 at the top of the upper assembly 20a and the side wall 21 below it, in the handling mechanism shown on the left of FIG. The entire container can be lifted.

The same slot as the fastening slot 211 is formed on the outer surface of the side wall 21 of the upper assembly 20a, and the outer panel 213 integrally coupled to the upper part of the body 10 is installed.

Referring to FIGS. 3b and 3f between the outer panel 213 and the outer surface of the side wall 21 of the upper assembly 20a, a sealing 212 is installed along the periphery of the fastening slot 211 to the inside of the body 10 It is prevented that foreign substances are introduced into the upper assembly 20a through the fastening slot 211 from the inside. This is because, if there is no sealing 212 , foreign substances falling off from the defective spent nuclear fuel through the gap between the side wall 21 and the body 10 , at least minutely, may penetrate into the upper assembly 20a through the slot. In this case, even if the upper mesh 28 is provided in the upper assembly 20a as described above, if foreign substances penetrate through the gap between the body 10 and the side wall 21, the upper mesh 28 may become useless. .

<Second embodiment>

The configuration of the second embodiment is mostly in common with the first embodiment as shown in FIGS. 4A and 4B, and the difference is in the shape of the upper structure.

The top structure 27 of the second embodiment is manufactured to correspond to the shape of the top fixture of the CE-type nuclear fuel.

The handling mechanism (CED) of the second embodiment shown in the right drawing of FIG. 2B is a mechanism capable of lifting and transporting the nuclear fuel assembly (CEF) of the second embodiment. Looking at the nuclear fuel assembly (CEF) of the second embodiment shown below the handling mechanism (CED) of the second embodiment, an arc-shaped handling mechanism insertion hole 271 is located at the center of the flow path plate coupled to the upper portions of the four guide tubes. It can be seen that the handling mechanism (CED) of the second embodiment is arranged in a circle, and a member capable of being gripped is inserted into the handling mechanism insertion hole 271 to enable lifting and transport.

In order to be able to be lifted and transported by the handling mechanism (CED) of the second embodiment, the handling mechanism insertion hole is also formed in the upper structure 27 according to the second embodiment in a form in which circular arcs are connected to each other to correspond to the upper fixture shape. .

In the above, the first and second embodiments have been sequentially looked at, and finally, the lower assembly 30 equally applied to the first and second embodiments will be looked at.

The lower assembly 30 includes a lower plate 31 , a lower mesh 32 , and a lower perforated plate 33 as shown in FIGS. 5A and 5B . The lower plate 31 and the lower perforated plate 33 may be formed integrally with each other, or the lower perforated plate 33 may be installed in a form in which the lower surface of the lower plate 31 is padded as shown in the photo of FIG. 5B . The lower mesh 32 may be fabricated in two layers. This is because, in the vacuum drying process, due to the increase in internal pressure, if the mesh is in one layer, it may tear.

The present invention described above is not limited by the above-described embodiments and the accompanying drawings, and it is common in the technical field to which the present invention pertains that various substitutions, modifications and changes can be made within the scope without departing from the technical spirit of the present invention. It will be clear to those who have the knowledge of

CED: Handling mechanism of the second embodiment CEF: Nuclear fuel assembly of the second embodiment
CEU: upper fixture of the second embodiment WHD: handling mechanism of the first embodiment
WHF: Nuclear fuel assembly of the first embodiment WHU: Top fixture of the first embodiment
10: body 20a, 20b: upper assembly
21: side wall 24: rotating plate
25: fixed plate 26,27: upper structure
28: upper mesh 29: upper perforated plate
30: lower assembly 31: lower plate
32: lower mesh 33: lower perforated plate
211: fastening slot 212: sealing
213: outer panel 231: fastening bolt
232: latch 233: lock pin
234: return spring 235: latch fixing pin
241: latch hole 251: lock pin hole
261: guide pin hole 271: handling mechanism insertion hole

Claims (8)

a body 10 having a length and a volume capable of accommodating the nuclear fuel assembly;
The upper coupling body (20a, 20b) is coupled to the upper end of the body (10), a removable opening and closing member for opening or closing the inside of the body (10) is installed; and,
It includes; a lower assembly 30 coupled to the lower portion of the body 10 to seal the lower portion of the body 10;
The upper assembly (20a, 20b) and the lower assembly 30 are provided with a mesh member that allows the emission of gas while preventing the outflow of radioactive particles,
The mesh member is formed with a width of one eye of the mesh of 1 mm or less, and consists of an upper mesh 28 installed in the upper assembly 20a, 20b and a lower mesh 32 installed in the lower assembly 30, ,
On the upper surface of the upper mesh 28 or the lower surface of the lower mesh 32, which is the surface on which the mesh member is exposed, an upper perforated plate 29 and a lower perforated plate 33 each having a plurality of through-holes perforated therein are provided on the upper surface of the upper mesh 28. Or a defective spent nuclear fuel handling container, characterized in that it is installed in a form in contact with the bottom surface of the lower mesh (32). delete According to claim 1,
The detachable opening/closing member includes a rotating plate 24 having a plurality of wings protruding to the side, and a plurality of fastening slots 211 formed in the side wall 21 of the upper assembly 20a so that the plurality of blades are respectively inserted. includes,
When the rotating plate 24 is rotated so that the plurality of blades are inserted into the fastening slot 211, the removable opening and closing member seals the upper end of the body 10, and the rotating plate 24 is connected to the plurality of blades with the fastening slot 211. Defective spent nuclear fuel handling container, characterized in that when rotated so as to be separated from the detachable opening and closing member can open the upper end of the body (10). 4. The method of claim 3,
A fastening bolt 231 assembled to the rotating plate 24 is provided at the center of the rotating plate 24, and by rotating the fastening bolt 231, the rotating plate 24 is rotated, so that the plurality of wings are attached to the fastening slot 211. Defective spent nuclear fuel handling container, characterized in that each is coupled to the rotating plate (24) is fixed. 5. The method of claim 4,
The rotating plate 24 is disposed on the upper surface of the fixing plate 25 in which the upper mesh 28 is installed at a predetermined portion, and the fastening bolt 231 is installed in a form that penetrates both the centers of the rotating plate 24 and the fixing plate 25 . A lock pin 233 is fixedly connected to the lower portion of the fastening bolt 231, and a lock pin hole 251 into which the lock pin 233 can be inserted is formed in the fixing plate 25,
When the fastening bolt 231 is changed downward, the lock pin 233 is changed together with the fastening bolt 231 and the lock pin 233 is separated from the lock pin hole 251, so that the fastening bolt 231 and the rotating plate 24 are rotated. A container for handling defective spent fuel, characterized in that it is in a possible state. 6. The method of claim 5,
A clasp 232 is fixedly connected to the upper portion of the fastening bolt 231, and a clasp hole 241 into which the clasp 232 can be inserted is formed in the rotary plate 24,
When the fastening bolt 231 is changed downward, the latch 232 is changed downward together with the fastening bolt 231 and the latch 232 is inserted into the latch hole 241, thereby the fastening bolt 231 and the rotating plate 24. Defective spent nuclear fuel handling container, characterized in that it is integrally rotatable together. 7. The method of claim 6,
On the lower surface of the head of the fastening bolt 231, a clasp 232 fixing plate 25 is installed along the center circumference of the fastening bolt 231,
The clasp 232 is fixedly installed on the lower surface of the clasp 232 fixing plate 25,
A return spring 234 is installed between the upper surface of the rotating plate 24 and the lower surface of the clasp 232 and the lower surface of the fixing plate 25 to surround the body of the fastening bolt 231, so that the fastening bolt 231 is lowered due to the pressure of the upper part. Then, when the upper pressure is released, the lock pin 233 is inserted into the lock pin hole 251 and the latch 232 is drawn out from the latch hole 241 while rising by the elastic force of the return spring 234. Defective spent fuel handling containers. 8. The method of claim 7,
A through hole is formed in the upper portion of the upper assembly (20a, 20b) to which equipment for lifting the upper fixture of the nuclear fuel assembly embedded in the body (10) can be fastened,
The same slot as the fastening slot 211 is formed on the outer surface of the side wall 21 of the upper assembly 20a, 20b, and the external panel 213 integrally coupled with the upper part of the body 10 is installed,
Between the outer panel 213 and the outer surface of the side wall 21 of the upper assembly 20a, 20b, a sealing 212 is installed along the periphery of the fastening slot 211, so that foreign substances from the inside of the body 10 enter the fastening slot ( 211) through the upper coupling body (20a, 20b) is prevented from flowing into the inside,
When the blade of the rotating plate 24 is separated from the fastening slot 211 due to the rotation of the rotating plate 24, the rotating plate 24, the fixed plate 25, and the upper assembly 20a including the upper mesh 28, Defective spent nuclear fuel handling container, characterized in that 20b) is detachable from the body (10).

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