Transfer container for vertical type concrete container spent fuel dry storage system

Abstract

The invention provides a transfer container for a vertical type concrete container spent fuel dry storage system, which comprises a cylinder assembly, a top cover and a bottom plate, the cylinder assembly comprises a first shielding layer and a second shielding layer, the second shielding layer surrounds the periphery of the first shielding layer, the first shielding layer is used for shielding gamma rays, the second shielding layer is used for shielding neutron rays, and the top cover is used for covering the bottom plate. The cylinder assembly is a sealed container for loading spent fuel; the top cover is arranged at the top of the barrel assembly and connected with the barrel assembly, and a detachable lifting hole cover is arranged in the middle of the top cover; the bottom plate is arranged at the bottom of the barrel assembly and detachably connected with the barrel assembly. The barrel assembly comprises a first shielding layer and a second shielding layer, the first shielding layer and the second shielding layer meet the shielding requirement and can prevent a sealed container and spent fuel in the barrel assembly from being damaged by accidents such as falling and impact of flying objects in the transferring process, and compared with an existing steel-lead-steel composite structure, the barrel assembly has better structural integrity, and the service life of the barrel assembly is prolonged. And better structural protection performance can be provided.

Description

Technical Field

[0001] The invention relates to the technical field of spent fuel transfer in nuclear power plants, and in particular to a transfer container for a vertical concrete container spent fuel dry storage system. Background Art

[0002] Pressurized water reactor nuclear power plants use the heat generated by the fission of nuclear fuel assemblies to generate nuclear power. As the fission elements in the fuel assemblies are consumed, the reactor needs to be refueled every certain refueling cycle. The common refueling cycle is 12 to 18 months. During each refueling operation, about 1 / 3 of the fuel assemblies will be unloaded from the reactor as spent fuel and transferred to the spent fuel pool of the nuclear power unit for storage. The conventional design life of a pressurized water reactor nuclear power plant is 40 to 60 years, but the capacity of the spent fuel pool is limited and can generally only meet the spent fuel storage needs within more than 10 years. During the life of the nuclear power plant, there will inevitably be problems related to the full capacity of the spent fuel pool.

[0003] In this context, the technical measures currently developed to alleviate the problem of spent pool fullness in nuclear power plants mainly include:

[0004] 1. The storage capacity of the spent fuel pool is improved.

[0005] Specifically, it includes: using the surplus space in the spent fuel pool to add spent fuel storage racks, or replacing the existing spent fuel storage racks, replacing non-intensive storage racks with intensive storage racks, so as to achieve the purpose of storing more spent fuel assemblies per unit area.

[0006] 2. Transfer of spent fuel between units.

[0007] A nuclear power plant often has multiple nuclear power units, and each unit is often built in batches. The time for completion, commissioning and grid-connected power generation varies. The spent fuel of the old unit can be introduced into the spent fuel storage pool of the new unit to alleviate the problem of the old unit's spent fuel pool being full.

[0008] 3. Construct intermediate storage facilities.

[0009] Although the improvement of the spent fuel pool storage capacity and the transfer of spent fuel between units can alleviate the problem of spent fuel pool fullness to a certain extent, the degree of relief is limited and can only delay the time when the spent fuel pool is full but cannot completely solve the problem. In this case, the construction of intermediate storage facilities is a safe, economical, efficient and flexible option to solve the problem of spent fuel pool fullness.

[0010] At present, there are two technical routes for intermediate storage facilities, namely metal container type and sealed container with concrete module / concrete container. The safety of both are comparable, but the latter has more advantages in terms of economy. Currently, intermediate storage facilities at home and abroad generally adopt the technical route of sealed container with concrete module or concrete container. In the technical route of sealed container with concrete module or concrete container, the transfer container is an important equipment for realizing the in-plant transfer operation of sealed container loaded with spent fuel. The current transfer containers cannot meet the transfer needs and have poor safety and high cost.

[0011] Based on this, the inventor of the present application proposes a transfer container for a vertical concrete container spent fuel dry storage system, in order to solve one or more of the above-mentioned technical problems. Summary of the invention

[0012] The technical problem to be solved by the present invention is to overcome the defects of poor safety and high cost of the current transfer mechanism in the prior art and to provide a transfer container for a vertical concrete container spent fuel dry storage system.

[0013] The present invention solves the above technical problems through the following technical solutions:

[0014] The present invention provides a vertical concrete container for a spent fuel dry storage system, which is characterized by comprising:

[0015] A cylinder assembly, comprising a first shielding layer and a second shielding layer, wherein the second shielding layer is arranged around the outer periphery of the first shielding layer, the first shielding layer is used for shielding gamma rays, the second shielding layer is used for shielding neutron rays, and the cylinder assembly is used for a sealed container for loading spent fuel;

[0016] A top cover is arranged on the top of the cylinder assembly and connected to the cylinder assembly, and a detachable hanging hole cover is arranged in the middle of the top cover;

[0017] The bottom plate is arranged at the bottom of the barrel assembly and is detachably connected to the barrel assembly.

[0018] According to one embodiment of the present invention, the thickness of the middle portion of the first shielding layer is smaller than the thickness of the opposite ends;

[0019] The thickness of the middle portion of the second shielding layer is greater than the thickness of the opposite ends.

[0020] According to one embodiment of the present invention, the first shielding layer is a gamma ray shielding layer of a forged steel part, and the second shielding layer is a neutron shielding layer of a high temperature resistant boron-containing resin.

[0021] According to an embodiment of the present invention, a pair of suspension shafts are provided at the top of the first shielding layer, and a pair of turning shaft seats are provided at the bottom of the first shielding layer.

[0022] According to one embodiment of the present invention, a bottom flange is provided at the bottom of the first shielding layer, and the circumferential dimension of the bottom flange is greater than the circumferential dimension of the first shielding layer;

[0023] The bottom flange is detachably connected to the bottom plate via a threaded connector.

[0024] According to one embodiment of the present invention, the first shielding layer is internally welded with stainless steel, and a plurality of stainless steel support bars are welded on the stainless steel welded layer;

[0025] The neutron shielding layer includes a casting layer, a plurality of heat-conducting ribs and a cladding, the casting layer is located between the cladding and the first shielding layer, the heat-conducting ribs connect the first shielding layer and the cladding and are arranged radially along the first shielding layer.

[0026] According to one embodiment of the present invention, a mounting hole is provided on the top cover, and the hanging hole cover is disposed in the mounting hole;

[0027] The hanging hole cover is provided with a hanging hole cover neutron shielding layer and a first cover plate arranged outside the hanging hole cover neutron shielding layer;

[0028] The top cover is provided with a top cover neutron shielding layer circumferentially around the outer circumference of the hanging hole cover and a second cover plate arranged outside the top cover neutron shielding layer.

[0029] According to one embodiment of the present invention, the top surface of the first cover plate is flush with the top surface of the hanging hole cover;

[0030] The top surface of the second cover plate is flush with the top surface of the top cover.

[0031] According to an embodiment of the present invention, the top cover and the bottom plate are both provided with holes for an auxiliary cooling system, an auxiliary cooling system interface is inserted into the hole, and the hole is communicated with the inner side of the first shielding layer.

[0032] According to one embodiment of the present invention, a bottom plate neutron shielding layer and a third cover plate covering the outside of the bottom plate neutron shielding layer are provided on a side of the bottom plate facing away from the cylinder assembly.

[0033] According to one embodiment of the present invention, a lead shielding layer is further provided between the third cover plate and the bottom plate neutron shielding layer.

[0034] According to one embodiment of the present invention, the hanging hole cover is sealed and connected to the top cover via a sealing ring.

[0035] The positive and progressive effects of the present invention are:

[0036] The present invention discloses a transfer container for a vertical concrete container spent fuel dry storage system, wherein the cylinder assembly comprises a first shielding layer and a second shielding layer, wherein the first shielding layer and the second shielding layer not only meet the shielding requirements, but also prevent damage to the sealed container and spent fuel inside thereof caused by accidents such as falling and impact of projectiles during transportation. Compared with the existing steel-lead-steel composite structure, the complete forging structure has better structural integrity and can provide better structural protection performance. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] The above and other features, properties and advantages of the present invention will become more apparent through the following description in conjunction with the accompanying drawings and embodiments, in which:

[0038] Figure 1 It is a cross-sectional view of a transport container for a vertical concrete container spent fuel dry storage system of the present invention;

[0039] Figure 2 for Figure 1 a cross-sectional view of the middle cylinder assembly;

[0040] Figure 3 for Figure 1 A top view of the middle cylinder assembly;

[0041] Figure 4 for Figure 1 a cross-sectional view of the middle barrel assembly;

[0042] Figure 5 for Figure 1 Cross-section of the middle ceiling cover;

[0043] Figure 6 for Figure 1 A cross-sectional view of the middle top cover;

[0044] Figure 7 for Figure 1 A partial cross-sectional view of the middle top cover;

[0045] Figure 8 for Figure 1 A cross-sectional view of the midsole plate;

[0046] Fig. 9 for Figure 1 A partial cross-sectional view of the midsole plate;

[0047] Fig.10 This is a schematic diagram of the coordination between the transfer container and the storage container.

[0048] 1. Cylinder assembly; 11. First shielding layer; 111. Bottom flange; 112. Stainless steel cladding layer; 113. Stainless steel support bar; 12. Second shielding layer; 121. Casting layer; 122. Heat conducting rib plate; 123. Enclosure; 13. Suspension shaft; 14. Turnover shaft seat;

[0049] 2. Top cover; 21. Hanging hole cover; 211. Hanging hole cover neutron shielding layer; 212. First cover plate; 22. Mounting hole; 23. Top cover neutron shielding layer; 24. Second cover plate; 25. Sealing ring;

[0050] 3. Bottom plate; 31. Channel; 32. Auxiliary cooling system interface; 33. Bottom plate neutron shielding layer; 34. Third cover plate; 35. Lead shielding layer;

[0051] 4. Sealed container;

[0052] 5. Storage container. DETAILED DESCRIPTION

[0053] The present invention is further described below in conjunction with specific embodiments and drawings. More details are elaborated in the following description to facilitate a full understanding of the present invention. However, the present invention can obviously be implemented in a variety of other ways different from the description herein. Those skilled in the art can make similar generalizations and deductions based on actual application situations without violating the connotation of the present invention. Therefore, the protection scope of the present invention should not be limited by the content of this specific embodiment.

[0054] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by technicians in the technical field to which this application belongs; the terms used herein are only for the purpose of describing specific embodiments and are not intended to limit this application; the terms "including" and "having" in the specification and claims of this application and the above-mentioned figure descriptions and any variations thereof are intended to cover non-exclusive inclusions.

[0055] Please refer to Figures 1 to 10 The present invention proposes a transport container for a vertical concrete container spent fuel dry storage system, comprising a cylinder assembly 1, a top cover 2 and a bottom plate 3, the cylinder assembly 1 comprising a first shielding layer 11 and a second shielding layer 12, the second shielding layer 12 is arranged around the outer periphery of the first shielding layer 11, the first shielding layer 11 is used to shield gamma rays, and the second shielding layer 12 is used to shield neutron rays, the cylinder assembly 1 is used to load a sealed container 4 for spent fuel; the top cover 2 is arranged on the top of the cylinder assembly 1 and connected to the cylinder assembly 1, and a detachable hanging hole cover 21 is provided in the middle of the top cover 2; the bottom plate 3 is arranged at the bottom of the cylinder assembly 1 and is detachably connected to the cylinder assembly 1.

[0056] The cylinder assembly 1 has an inner cavity for accommodating a sealed container 4 for loading spent fuel. The first shielding layer 11 has no large lead-filled structure, thereby avoiding defects such as bubbles and impurities that are prone to occur in large lead-filled structures, which is beneficial to ensuring the shielding performance and structural integrity of the cylinder assembly 1.

[0057] That is, the first shielding layer 11 and the second shielding layer 12 not only meet the shielding requirements, but also prevent damage to the sealed container 4 and spent fuel inside due to accidents such as falling and projectile impact during transportation. Compared with the existing steel-lead-steel composite structure, the complete forging structure has better structural integrity and can provide better structural protection performance.

[0058] Specifically, the thickness of the middle portion of the first shielding layer 11 is smaller than the thickness of the opposite two ends; the thickness of the middle portion of the second shielding layer 12 is larger than the thickness of the opposite two ends.

[0059] That is, the first shielding layer 11 is cylindrical as a whole and is contracted in the middle, and is mainly used to shield gamma rays. The second shielding layer 12 is also cylindrical as a whole and is expanded in the middle, and is mainly used to shield neutron rays.

[0060] It can be seen that the shielding of neutrons first slows down the fast neutrons into medium-energy neutrons through the inelastic scattering of elements with higher atomic numbers, and then further slows down into thermal neutrons through elements with low atomic numbers, and then is absorbed by nuclides with high neutron capture cross-sections, that is: heavy matter + light matter slows down, and high capture cross-section matter absorbs.

[0061] Gamma ray shielding generally uses high atomic number materials to absorb through photoelectric effect, Compton scattering and electron pair effect. Traditional materials including concrete, stainless steel, water and lead have good shielding effects on neutrons and photons respectively. When used in combination in nuclear power plants, they can effectively reduce radiation levels.

[0062] Therefore, in the present invention, the first shielding layer 11 is a gamma-ray shielding layer made of forged steel, and the second shielding layer 12 is a neutron shielding layer made of a high-temperature resistant boron-containing resin.

[0063] The inner cavity of the transport container is used to place the sealed container 4, the spent fuel in which is highly radioactive, and the transport container needs to have good shielding performance. Generally speaking, the improvement of shielding performance requires more materials, which leads to heavier equipment weight.

[0064] Since the rated lifting capacity of the crane in the fuel building of a nuclear power plant is given, excessive deadweight of the transfer container equipment will limit the loading amount of the spent fuel in the sealed container 4, thereby affecting the economy of the system.

[0065] Based on this, the present invention, through detailed analysis of the distribution of spent fuel source items, determines that the upper and lower tube seats of the fuel assembly in the sealed container 4 have a high activation gamma ray dose rate, while the gamma ray dose rate in the middle area is relatively low. A variable-section shielding layer is adopted for the container cylinder, that is, the two ends of the first shielding layer 11 are made thicker to absorb more gamma rays, thereby achieving the joint optimization of the equipment's own weight and shielding performance.

[0066] Furthermore, in the barrel assembly 1 of the present invention, the first shielding layer 11 is made of a complete SA359 forging without a lead-filled layer. This structure serves as both a gamma-ray shielding layer and a structural protection layer, which can prevent damage to the sealed container 4 and spent fuel inside it due to accidents such as falling and projectile impact during operation. Compared with the traditional steel-lead-steel composite structure, the complete forging structure has better structural integrity and can provide better structural protection performance.

[0067] The transport container needs to undergo thermal safety evaluation, and the thermal safety evaluation of the neutron shielding layer is often the shortcoming of the thermal safety evaluation of the entire equipment. In the present invention, the second shielding layer 12 of the transport container uses a high-temperature resistant boron-containing resin as the neutron shielding layer. Compared with the traditional solution using water as the neutron shielding layer, it overcomes the above shortcoming and can withstand a temperature condition of nearly 200°C, while the solution using water as the neutron shielding layer can only withstand a temperature condition of nearly 100°C.

[0068] Please refer to Figures 1 to 4 , stainless steel is welded inside the first shielding layer 11, and a plurality of stainless steel support bars 113 are welded on the stainless steel welded layer 112. The neutron shielding layer includes a casting layer 121, a plurality of heat-conducting ribs 122 and a cladding 123, the casting layer 121 is located between the cladding 123 and the first shielding layer 11, and the heat-conducting ribs 122 connect the first shielding layer 11 and the cladding 123 and are arranged radially along the first shielding layer 11.

[0069] After the sealed container 4 is placed in the storage cavity of the transfer container, the spent fuel needs to be loaded into the sealed container 4 underwater, the radiation dose of the spent fuel is shielded by the water layer, and the heat of the spent fuel is cooled by the water medium. To ensure that the transfer container adapts to the underwater medium environment, a stainless steel cladding layer 112 is welded on the inner wall of the inner cavity of the transfer container, and an anti-corrosion coating is applied on the outer wall.

[0070] Then, a plurality of stainless steel support bars 113 are welded on the stainless steel cladding layer 112, which can ensure that the sealed container 4 is arranged in the center, and a gap is left between the outer wall of the sealed container 4 and the first shielding layer 11 under the action of the stainless steel support bars 113, so that a uniform flow channel is provided between the outer wall of the sealed container 4 and the first shielding layer 11 for the desalted water medium of the auxiliary cooling system to flow.

[0071] For the second shielding layer 12, a plurality of heat-conducting ribs 122 are circumferentially arranged inside the second shielding layer 12, which can serve as a thermal bridge to transfer the heat inside the transfer container to the outer surface of the container; when necessary, the transfer container can also be connected to an auxiliary cooling system using desalted water as a medium through the interfaces on the top cover 2 and the bottom plate 3 to cope with abnormal working conditions and ensure that the temperature of each component of the system equipment is below the limit temperature of the material.

[0072] In one embodiment, a pair of suspension shafts 13 are provided at the top of the first shielding layer 11 , and a pair of turning shaft seats 14 are provided at the bottom of the first shielding layer 11 .

[0073] A hanging shaft 13 is arranged on the transfer container to serve as a lifting interface of the transfer container; and a turning shaft seat 14 is arranged on the transfer container to facilitate the turning operation of the transfer container.

[0074] Specifically, the transfer container can be connected to the in-plant transfer bracket through a pair of hanging shafts 13 and a pair of turning shaft seats 14 of the transfer container, thereby facilitating the in-plant transfer operation of the transfer container.

[0075] In one embodiment, a bottom flange 111 is provided at the bottom of the first shielding layer 11 , and the circumferential dimension of the bottom flange 111 is larger than the circumferential dimension of the first shielding layer 11 ; the bottom flange 111 is detachably connected to the bottom plate 3 via a threaded connector.

[0076] The circumferential dimension of the bottom flange 111 corresponds to that of the bottom plate 3 , but both are larger than the circumferential dimension of the first shielding layer 11 , so that the first shielding layer 11 can be connected to the bottom plate 3 using the bottom flange 111 , and the disassembly and assembly of the cylinder assembly 1 and the bottom plate 3 is more convenient.

[0077] Please refer to Figures 5 to 7 For the top cover 2, a mounting hole 22 is opened on the top cover 2, and a hanging hole cover 21 is arranged in the mounting hole 22; a hanging hole cover neutron shielding layer 211 and a first cover plate 212 arranged on the outside of the hanging hole cover neutron shielding layer 211 are provided on the hanging hole cover 21; a top cover neutron shielding layer 23 and a second cover plate 24 arranged on the outside of the top cover neutron shielding layer 23 are circumferentially provided on the top cover 2 around the outer circumference of the hanging hole cover 21.

[0078] Specifically, the top surface of the first cover plate 212 is flush with the top surface of the hanging hole cover 21 ; the top surface of the second cover plate 24 is flush with the top surface of the top cover 2 .

[0079] Please refer to Figure 8 and Fig. 9 A bottom plate neutron shielding layer 33 and a third cover plate 34 covering the outside of the bottom plate neutron shielding layer 33 are provided on the side of the bottom plate 3 facing away from the cylinder assembly 1 .

[0080] It can be seen that a lead shielding layer 35 is further provided between the third cover plate 34 and the bottom plate neutron shielding layer 33 .

[0081] In the present invention, forged steel is provided as a gamma ray shielding layer, and high temperature resistant boron-containing resin is provided as a neutron shielding layer in the top cover 2, the hanging hole cover 21, and the cylinder assembly 1, and forged steel and lead shielding layer 35 is provided as a gamma ray shielding layer, and high temperature resistant boron-containing resin is provided as a neutron shielding layer on the bottom plate 3. Thus, the sealed container 4 and its contents inside the transport container storage cavity are provided with gamma ray radiation protection and neutron radiation protection in the top side and bottom all-round.

[0082] That is, the sealed container 4 loaded with spent fuel is placed in the storage cavity of the transfer container, and a top cover 2, a cylinder assembly 1 and a bottom plate 3 are provided on the top, side and bottom of the container respectively. The above structures all include forged steel parts with a certain thickness, which can provide good structural protection to avoid damage to the sealed container 4 and its contents caused by accidents such as falling and impact of missiles during transportation.

[0083] Reference Fig.10 , the following is the transport process of the sealed container 4 of the present invention:

[0084] After the transfer container transfers the sealed container 4 from the fuel plant to the storage site in the plant, the bottom plate 3 of the transfer container needs to be replaced with a connector to create conditions for the subsequent operation of introducing the sealed container 4 into the storage container 5. At this time, the lifting hole cover 21 can be opened first, and the transfer container can be lifted through the lifting shaft 13 with the help of the transfer container lifting device, and the sealed container 4 can be lifted through the opening of the lifting hole cover 21 with a lifting belt, so as to facilitate the replacement operation of the bottom plate 3.

[0085] After the bottom plate 3 is replaced, the sealed container 4 can be introduced into the vertical concrete container (storage container 5). After the bottom plate 3 is replaced with the connector, the sealed container 4 inside the transfer container needs to be introduced into the vertical concrete container (storage container 5). At this time, the top cover 2 of the storage container 5 can be opened, and the transfer container can be stacked on the storage container 5, and the connector and the storage container 5 can be securely fixed.

[0086] Then open the lifting hole cover 21 of the transfer container, connect the sling with the top cover 2 of the sealed container 4, lift the sealed container 4 through the sling, then open the opening and closing bottom plate 3 of the connector to make room for the sealed container 4 to go down, and lower the sealed container into the storage cavity of the storage container 5 through the sling to complete the transfer and storage of the sealed container 4.

[0087] In one embodiment, both the top cover 2 and the bottom plate 3 are provided with a hole 31 for the auxiliary cooling system, an auxiliary cooling system interface 32 is inserted into the hole 31 , and the hole 31 is communicated with the inner side of the first shielding layer 11 .

[0088] Specifically, bolts are used to connect the hanging hole cover 21 and the top cover 2, the top cover 2 and the top surface of the cylinder assembly 1, and the flange of the first shielding layer 11 and the bottom plate 3. Sealing rings 25 are provided between the joint surfaces to form a complete water-tight boundary.

[0089] The bottom plate 3 and the top cover 2 are provided with interfaces connected to the water-cooled auxiliary cooling system. When necessary, the transfer container can be connected to the water-cooled auxiliary cooling system through a water pipe, thereby assisting in removing heat from the contents and keeping the material temperature of each component of the system equipment below the limit.

[0090] In summary, in the vertical concrete container spent fuel dry storage system transfer container of the present invention, the cylinder assembly 1 includes a first shielding layer 11 and a second shielding layer 12. The first shielding layer 11 and the second shielding layer 12 not only meet the shielding requirements, but also prevent the sealed container 4 and the spent fuel inside from being damaged by accidents such as falling and projectile impact during transportation. Compared with the existing steel-lead-steel composite structure, the complete forging structure has better structural integrity and can provide better structural protection performance.

[0091] In the description of the embodiments of the present application, unless otherwise clearly specified and limited, technical terms such as "install", "connect", "connect", "fixed" and the like should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integral connection; it can also be a mechanical connection. For ordinary technicians in this field, the specific meanings of the above terms in the embodiments of the present application can be understood according to the specific circumstances.

[0092] The present application uses specific words to describe the embodiments of the present application. For example, "one embodiment", "an embodiment", and / or "some embodiments" refer to a certain feature, structure or characteristic related to at least one embodiment of the present application. Therefore, it should be emphasized and noted that "one embodiment" or "an embodiment" or "an alternative embodiment" mentioned twice or multiple times in different positions in this specification does not necessarily refer to the same embodiment. In addition, some features, structures or characteristics in one or more embodiments of the present application can be appropriately combined.

[0093] Although the present invention is disclosed as above with preferred embodiments, it is not intended to limit the present invention. Any person skilled in the art may make possible changes and modifications without departing from the spirit and scope of the present invention. Therefore, any modification, equivalent change and modification made to the above embodiments according to the technical essence of the present invention without departing from the content of the technical solution of the present invention shall fall within the protection scope defined by the claims of the present invention.

Claims

1. A vertical concrete container transport container for spent fuel dry storage system, characterized in that: include: A cylinder assembly, comprising a first shielding layer and a second shielding layer, wherein the second shielding layer is arranged around the outer periphery of the first shielding layer, the first shielding layer is used for shielding gamma rays, the second shielding layer is used for shielding neutron rays, and the cylinder assembly is used for a sealed container for loading spent fuel; A top cover is arranged on the top of the cylinder assembly and connected to the cylinder assembly, and a detachable hanging hole cover is arranged in the middle of the top cover; The bottom plate is arranged at the bottom of the barrel assembly and is detachably connected to the barrel assembly.

2. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: The thickness of the middle portion of the first shielding layer is smaller than the thickness of the opposite ends; The thickness of the middle portion of the second shielding layer is greater than the thickness of the opposite ends.

3. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: The first shielding layer is a gamma ray shielding layer of a forged steel part, and the second shielding layer is a neutron shielding layer of a high temperature resistant boron-containing resin.

4. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: A pair of suspension shafts are arranged on the top of the first shielding layer, and a pair of turning shaft seats are arranged on the bottom of the first shielding layer.

5. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: A bottom flange is provided at the bottom of the first shielding layer, and the circumferential dimension of the bottom flange is larger than the circumferential dimension of the first shielding layer; The bottom flange is detachably connected to the bottom plate via a threaded connector.

6. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: The first shielding layer is internally welded with stainless steel, and a plurality of stainless steel support bars are welded on the stainless steel welded layer; The neutron shielding layer includes a casting layer, a plurality of heat-conducting ribs and a cladding, the casting layer is located between the cladding and the first shielding layer, the heat-conducting ribs connect the first shielding layer and the cladding and are arranged radially along the first shielding layer.

7. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: The top cover is provided with a mounting hole, and the hanging hole cover is arranged in the mounting hole; The hanging hole cover is provided with a hanging hole cover neutron shielding layer and a first cover plate arranged outside the hanging hole cover neutron shielding layer; The top cover is provided with a top cover neutron shielding layer circumferentially around the outer circumference of the hanging hole cover and a second cover plate arranged outside the top cover neutron shielding layer.

8. The vertical concrete container spent fuel dry storage system transfer container according to claim 7, characterized in that: The top surface of the first cover plate is flush with the top surface of the hanging hole cover; The top surface of the second cover plate is flush with the top surface of the top cover.

9. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: The top cover and the bottom plate are both provided with holes for the auxiliary cooling system, an auxiliary cooling system interface is inserted into the hole, and the hole is communicated with the inner side of the first shielding layer.

10. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: A bottom plate neutron shielding layer and a third cover plate covering the outer side of the bottom plate neutron shielding layer are provided on the side of the bottom plate facing away from the cylinder assembly.

11. The vertical concrete container spent fuel dry storage system transfer container according to claim 10, characterized in that: A lead shielding layer is also provided between the third cover plate and the bottom plate neutron shielding layer.

12. The vertical concrete container spent fuel dry storage system transfer container according to claim 1, characterized in that: The hanging hole cover is sealed and connected to the top cover via a sealing ring.

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