CN113948233A - Fast reactor spent fuel transport container structure - Google Patents

Fast reactor spent fuel transport container structure Download PDF

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Publication number
CN113948233A
CN113948233A CN202111229816.8A CN202111229816A CN113948233A CN 113948233 A CN113948233 A CN 113948233A CN 202111229816 A CN202111229816 A CN 202111229816A CN 113948233 A CN113948233 A CN 113948233A
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CN
China
Prior art keywords
spent fuel
barrel
transport container
fast reactor
container structure
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN202111229816.8A
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Chinese (zh)
Inventor
刘兆阳
孙帅
赵立勋
邓夏
李晓轩
汪军
薄涛
曹攀
张强
刘光耀
王明政
谷继品
艾长军
孟雷
范占国
甘谛
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China Institute of Atomic of Energy
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China Institute of Atomic of Energy
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China Institute of Atomic of Energy filed Critical China Institute of Atomic of Energy
Priority to CN202111229816.8A priority Critical patent/CN113948233A/en
Publication of CN113948233A publication Critical patent/CN113948233A/en
Pending legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/06—Details of, or accessories to, the containers
    • G21F5/14—Devices for handling containers or shipping-casks, e.g. transporting devices loading and unloading, filling of containers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/06—Details of, or accessories to, the containers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/06—Details of, or accessories to, the containers
    • G21F5/12—Closures for containers; Sealing arrangements

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The utility model provides a fast reactor spent fuel transport container structure, includes: the barrel subassembly for having multilayer barrel structure, wherein, the barrel subassembly includes: the inner barrel, the middle barrel and the outer barrel are sleeved from inside to outside in sequence, and the barrel assembly comprises a first end and a second end; an end cap portion sealingly connected to the first end of the cartridge assembly; the spent fuel storage barrel penetrates through the barrel assembly, and the spent fuel storage barrel is coaxially and hermetically connected with the second end of the barrel assembly through a positioning boss.

Description

Fast reactor spent fuel transport container structure
Technical Field
The utility model relates to a reactor technical field especially relates to a fast reactor spent fuel transport container structure.
Background
The transport container required by the fast reactor spent fuel outward transportation needs to be matched with a spent fuel process transport system, the safe transportation of the spent fuel from a reactor spent fuel pool to the transport container is realized, and the radiation protection and the centering in the transportation process are key points of the transportation process.
Disclosure of Invention
In one aspect, a fast reactor spent fuel transport container structure is provided, including: the barrel subassembly for having multilayer barrel structure, wherein, the barrel subassembly includes: the inner barrel, the middle barrel and the outer barrel are sleeved from inside to outside in sequence, and the barrel assembly comprises a first end and a second end; an end cap portion sealingly connected to the first end of the cartridge assembly; the spent fuel storage barrel penetrates through the barrel assembly, and the spent fuel storage barrel is coaxially and hermetically connected with the second end of the barrel assembly through a positioning boss.
Drawings
Other objects and advantages of the present disclosure will become apparent from the following description of the disclosure, which is made with reference to the accompanying drawings, and can assist in a comprehensive understanding of the disclosure.
Fig. 1 is a schematic structural view of a fast reactor spent fuel transport container according to some exemplary embodiments of the present disclosure.
Fig. 2 is a sectional view taken along the plane a-a of fig. 1.
Fig. 3 is a side view of the first endcap of fig. 1.
Fig. 4a is a front view of the spent fuel storage cask of fig. 1.
Fig. 4b is a side view of the spent fuel storage cask of fig. 1.
Fig. 5 is a schematic structural diagram of a fast reactor spent fuel transport container in some exemplary embodiments of the present disclosure.
Fig. 6a is a front cross-sectional view of the damper of fig. 5.
Figure 6B is a cross-sectional view of the bumper of figure 6a taken along plane B-B.
[ reference numerals ] of the drawings
100-inner cylinder;
200-middle cylinder;
300-outer cylinder;
400-first layer end cap;
500-a second layer of end caps;
600-spent fuel storage barrel;
700-a radiation protection shield;
800-gas displacement piping;
900-second rib plate;
110-a heat sink;
120-a buffer;
130-trunnion;
140-positioning the boss;
150-guiding means.
It is noted that, for the sake of clarity, in the drawings used to describe embodiments of the present disclosure, structures or regions may be enlarged or reduced in size, i.e., the drawings are not drawn to actual scale.
Detailed Description
In order to make the objects, technical solutions and advantages of the embodiments of the present disclosure more apparent, the technical solutions of the embodiments of the present disclosure will be described clearly and completely with reference to the drawings of the embodiments of the present disclosure. It is to be understood that the described embodiments are only a few embodiments of the present disclosure, and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the disclosure without any inventive step, are within the scope of protection of the disclosure.
Unless otherwise defined, technical or scientific terms used herein shall have the ordinary meaning as understood by one of ordinary skill in the art. The use of "first," "second," and similar terms in this disclosure is not intended to indicate any order, quantity, or importance, but rather is used to distinguish one element from another. The word "comprising" or "comprises", and the like, means that the element or item listed before the word covers the element or item listed after the word and its equivalents, but does not exclude other elements or items.
In this document, unless specifically stated otherwise, directional terms such as "upper", "lower", "left", "right", "inside", "outside", and the like are used to indicate orientations or positional relationships based on the orientation shown in the drawings, merely for convenience in describing the present disclosure, and do not indicate or imply that the referenced device, element, or component must have a particular orientation, be constructed or operated in a particular orientation. It should be understood that when the absolute positions of the described objects are changed, the relative positional relationships they represent may also change accordingly. Accordingly, these directional terms should not be construed as limiting the present disclosure.
The embodiment of the present disclosure provides a fast reactor spent fuel transport container structure, including: the device comprises a cylinder body assembly, an end cover part and a spent fuel storage barrel. The barrel subassembly is multilayer tubular structure, and the barrel subassembly overlaps in order from inside to outside and establishes and include: an inner barrel, a middle barrel and an outer barrel; the end cover part is hermetically connected with the first end of the cylinder component; the spent fuel storage barrel penetrates through the barrel assembly, and the spent fuel storage barrel is coaxially and hermetically connected with the second end of the barrel assembly through the positioning boss 140.
The guiding and positioning structure provided by the embodiment of the disclosure can be well adapted to a spent fuel process transportation system, so that the whole transfer process is smooth and safe. That is to say, in the embodiment of the present disclosure, the positioning and centering structure of the fast reactor spent fuel transport container structure makes the spent fuel process transportation flow smooth and safe, and safely transports the spent fuel assembly from the spent fuel pool into the spent fuel transport container.
Fig. 1 is a schematic structural view of a fast reactor spent fuel transport container according to some exemplary embodiments of the present disclosure. Fig. 2 is a sectional view taken along the plane a-a of fig. 1. As shown in fig. 1 and 2, the fast reactor spent fuel transport container structure includes: a barrel assembly, an end cap portion and a spent fuel storage barrel 600. The barrel subassembly is multilayer barrel structure, and the barrel subassembly includes: an inner barrel 100, a middle barrel 200 and an outer barrel 300 which are sleeved from inside to outside in sequence; the end cover part is connected with the first end of the cylinder component in a sealing way; the spent fuel storage barrel 600 is arranged in the barrel assembly in a penetrating manner, and the spent fuel storage barrel 600 is coaxially and hermetically connected with the second end of the barrel assembly through the positioning boss 140. The cylinder assembly and the end cover form a double containment boundary of the spent fuel transport container. The spent fuel storage cask 600 constitutes a critical safety boundary of the spent fuel transport container.
Specific reference to the cartridge assembly is as follows.
The cartridge assembly includes: the inner cylinder 100, the middle cylinder 200, the radiation protection shielding layer 700 and the outer cylinder 300 are sleeved in sequence from inside to outside. The radiation protection shield 700 includes: an inner lead shielding layer, an inner steel cylinder, a heat shielding layer, an outer steel cylinder and an outer lead shielding layer are sequentially sleeved from inside to outside.
In some exemplary embodiments, the cartridge assembly of the spent fuel transport container includes an inner cartridge 100, a middle cartridge 200, and an outer cartridge 300. The inner cylinder 100 is a first layer containing boundary, and the inner cylinder 100 and the middle cylinder 200 are connected together through a plurality of first rib plates in the circumferential direction.
In some exemplary embodiments, between the middle barrel 200 and the outer barrel 300 is a radiation protection shield 700. The inboard of radiation protection shielding layer 700 is lead shielding layer, and the outside is heat shielding layer, and heat shielding layer specifically can select the neutron shielding layer that contains boron-containing silicone, separates through interior steel cylinder between neutron shielding layer and the lead shielding layer. The neutron shielding layer is separated from the cylindrical cavity between the inner steel cylinder and the outer steel cylinder by the second rib plate 900, and the cylindrical cavity is filled with the heat shielding layer.
In order to reduce the weakening of neutron shielding at the rib plate position and improve the neutron shielding performance, the rib plate adopts a mode of arranging the inclined rib plates.
In the embodiment of the disclosure, the radiation protection shielding layer is made of boron-containing silicone resin neutron shielding material and lead shielding material, and the shielding property and the heat transfer property of the transportation container are realized through a sandwich structure of steel-lead-steel-boron-containing silicone resin-steel.
In some exemplary embodiments, the heat dissipation plate 110 is welded to the outer portion of the outer barrel 300, and particularly, heat dissipation fins are selected. The heat exchange surface area of the cylinder component is increased, and the heat dissipation of the surface of the cylinder component is facilitated.
In some exemplary embodiments, a trunnion 130 is further provided and welded to the outer wall of the fast reactor spent fuel transport vessel structure. Specifically, in order to facilitate the turning of the fast reactor spent fuel transport container structure during the process of lifting the fast reactor spent fuel transport container structure to the tie-down device, the trunnion 130 at the lower part of the fast reactor spent fuel transport container structure is arranged in a biased arrangement.
Fig. 3 is a side view of the first endcap of fig. 1. As shown in fig. 1 and 3, in some exemplary embodiments, the end cap portion is a double-layer end cap structure. The method specifically comprises the following steps: a first layer end cap 400 and a second layer end cap 500. The first end cap 400 is sealingly connected to the first end of the inner barrel 100 by a metal seal ring to form a radioactive first containment boundary. The second layer end cap 500 is hermetically connected with the first end of the middle tube 200 by a metal sealing ring to form a reflective second layer containing boundary. In the embodiment of the disclosure, a double-layer end cover structure is arranged, and a radioactive two-layer containing boundary is formed between the end cover part and the cylinder assembly, so that the sealing performance of the cylinder structure is favorably improved.
In some exemplary embodiments, the inner wall of the inner cylinder 100 is provided with a gas replacement pipe 800, the opening in the first-layer end cover 400 is connected with the gas replacement pipe 800, and a replacement gas valve is arranged in the first-layer end cover 400 and hidden in the first-layer end cover 400 and sealed by a sealing flange cover.
Fig. 4a is a front view of the spent fuel storage cask of fig. 1. Fig. 4b is a side view of the spent fuel storage cask of fig. 1. As shown in fig. 4a and 4b, in some exemplary embodiments, a guide device 150 is disposed at a side of the spent fuel storage barrel 600. The spent fuel storage cask 600 is loaded in a predetermined orientation as it is being lifted into the cartridge assembly. The bottom of the fast reactor spent fuel transport container structure is provided with a positioning boss 140, and the positioning boss 140 is matched with a hole at the bottom of the spent fuel storage barrel 600 to realize circumferential positioning. Namely, in the embodiment of the disclosure, the positioning boss is arranged to be matched with the hole at the bottom of the spent fuel storage barrel, so as to realize circumferential positioning.
In some exemplary embodiments, the spent fuel storage barrel 600 welds the spent fuel storage channels together by means of a plurality of circular plates. It should be understood that the circular plate here may also be a positioning plate in other forms, that is, in the embodiment of the present disclosure, the spent fuel storage barrel includes: a plurality of spent fuel storage channels; and the positioning plate is connected with the two adjacent spent fuel storage channels.
In some exemplary embodiments, the top of the spent fuel storage channel is provided with a spring element for limiting circumferential rotation of the spent fuel assembly. The spring element may alternatively be a leaf spring, and other resilient elements may be suitable to achieve the same effect, which is not illustrated here.
In some exemplary embodiments, during the hoisting of the end cover portion of the fast reactor spent fuel transport container structure into position, in order to ensure that the bolt holes are aligned with the bolt holes on the barrel assembly, the guide rods mounted on the bolt holes on the barrel assembly are used for ensuring the bolt hole centering and reducing the irradiation dose during operation.
Optionally, the flange of the containment boundary of the first layer is concealed within the cartridge assembly to protect containment of the containment boundary of the first layer during a fall.
In some embodiments of the present disclosure, a fast reactor spent fuel transport container structure is provided. Fig. 5 is a schematic structural diagram of a fast reactor spent fuel transport container in some exemplary embodiments of the present disclosure. Fig. 6a is a front cross-sectional view of the damper of fig. 5. Figure 6B is a cross-sectional view of the bumper of figure 6a taken along plane B-B. As shown in fig. 5, 6a and 6b, the structure of the fast reactor spent fuel transportation container differs from that shown in fig. 1 in that: a buffer 120 is also included. The buffer 120 is made of thin stainless steel plate coated with foamed aluminum and fixed to the cylinder assembly by bolts. The bolts are also hidden inside the bumper 120. In order to prevent the buffer 120 from falling off in the falling process, the buffer 120 is clamped on the cylinder assembly, and the bearing area of the connecting part is increased. In the embodiment of the disclosure, the buffer can be made of a foamed aluminum buffer material and used as a buffer in the falling process of the spent fuel transport container to absorb energy and realize the containment of the transport container.
Through safety analysis such as critical safety, shielding, thermotechnical, containment and the like, all the performances can meet the requirements of GB11806-2019 'safety transport regulations for radioactive products'.
In some embodiments of the present disclosure, all welds on the cartridge assembly are required to be welded through. The following describes details of the present embodiment related to welding.
Before formal welding of the structure of the spent fuel transport container, the welding process is evaluated, formal welding can be performed after the evaluation is qualified, and the welding is performed by strictly complying with the requirements of welding process regulations. Welding is required to meet corresponding requirements, welding defects such as cracks, air holes, arc pits and the like cannot exist in the welding seam, and the welding seam is polished after welding. Wherein all full penetration butt joints should be subjected to 100% ray detection; if the ray detection cannot be carried out under the influence of the welding seam condition, layered liquid penetration can be used for replacing (pressure-bearing butt joints cannot be used for replacing). And performing 100% liquid penetration detection on all welding seams and the surfaces of adjacent parent metals, performing liquid penetration detection on welding seam grooves, and performing 100% ray detection on all full-penetration butt joints according to the penetration detection requirement.
Providing a fast reactor spent fuel shipping container structure in some exemplary embodiments of the present disclosure may involve the following performance test tests.
(1) And (3) air tightness test:
the test medium of the air pressure test is dry and clean air, the test pressure is 0.3MPa, the test pressure is slowly increased, and the test pressure is kept for 30min after reaching the specified pressure. The pressure should not drop during the whole pressure maintaining period.
(2) Static load test:
after the fast reactor spent fuel transport container structure is assembled, a static load test is carried out, and a cargo bag is hoisted by a hoisting lug for 1.25 times of weight load and is slowly lifted. After static load test, the transport container has no obvious plastic deformation, and after the test, the bearing parts and the welding lines are used for liquid permeation detection.
(3) Dynamic load test:
the fast reactor spent fuel transport container structure is subjected to a dynamic load test after a static load test, the test load is 1.1 times of the weight of the transport container, and a crane performs lifting and descending motions 3 times at the speed of 0.7m/min, so that the fast reactor spent fuel transport container structure is required to run stably. After the dynamic load test, the fast reactor spent fuel transport container structure has no obvious plastic deformation.
Although a few embodiments of the present general inventive concept have been shown and described, it would be appreciated by those skilled in the art that changes may be made in these embodiments without departing from the principles and spirit of the general inventive concept, the scope of which is defined in the claims and their equivalents.

Claims (12)

1. A fast reactor spent fuel transport container structure is characterized by comprising:
a cartridge assembly having a multi-layered cartridge structure, wherein the cartridge assembly comprises: the inner barrel, the middle barrel and the outer barrel are sleeved from inside to outside in sequence, and the barrel assembly comprises a first end and a second end;
an end cap portion sealingly connected to the first end of the cartridge assembly;
the spent fuel storage barrel penetrates through the barrel assembly, and the spent fuel storage barrel is coaxially and hermetically connected with the second end of the barrel assembly through a positioning boss.
2. The fast reactor spent fuel shipping container structure according to claim 1, wherein said end cap portion comprises:
the first layer of end cover is hermetically connected with the first end of the inner cylinder;
the diameter of the second layer end cover is larger than that of the first layer end cover, and the second layer end cover is connected with the first end of the middle cylinder in a sealing mode.
3. The fast reactor spent fuel transport container structure according to claim 1, further comprising a radiation protection shielding layer disposed between the middle barrel and the outer barrel, wherein the radiation protection shielding layer comprises: an inner lead shielding layer, an inner steel cylinder, a heat shielding layer, an outer steel cylinder and an outer lead shielding layer are sequentially sleeved from inside to outside.
4. The fast reactor spent fuel transport container structure according to claim 3, wherein the radiation protection shield further comprises:
the second rib plate is arranged between the inner steel cylinder and the outer steel cylinder, two ends of the second rib plate are respectively connected with the inner steel cylinder and the outer steel cylinder, and the heat shield layer is filled between the adjacent second rib plates.
5. The fast reactor spent fuel transport container structure according to claim 1, wherein the cartridge assembly further comprises:
the first rib plate is arranged between the inner cylinder and the middle cylinder, and two ends of the first rib plate are respectively connected with the inner cylinder and the middle cylinder.
6. The fast reactor spent fuel transport container structure according to claim 1, further comprising:
and the heat dissipation plate is connected with the outer wall of the outer barrel.
7. The fast reactor spent fuel transport container structure according to claim 2, further comprising:
the gas replacement pipeline is arranged on the inner wall of the inner barrel and communicated with the first layer of end cover;
and the replacement gas valve is embedded in the first layer of end cover.
8. The fast reactor spent fuel transport container structure according to claim 1, wherein the spent fuel storage barrel comprises:
a plurality of spent fuel storage channels;
and the positioning plate is connected with the two adjacent spent fuel storage channels.
9. The fast reactor spent fuel transport container structure according to claim 8, wherein the spent fuel storage barrel further comprises:
and the guide device is arranged on the outer wall of the spent fuel storage barrel and is matched and connected with the inner wall of the barrel assembly.
10. The fast reactor spent fuel transport container structure according to claim 8, wherein the spent fuel storage barrel further comprises:
an elastic element connected with the first end of the spent fuel storage barrel, the elastic element being configured to limit circumferential rotation of the spent fuel storage channel.
11. The fast reactor spent fuel transport container structure according to any one of claims 1 to 10, further comprising:
and the buffer is covered on the end cover part and is fixedly connected with the first end of the cylinder component.
12. The fast reactor spent fuel transport container structure according to any one of claims 1 to 10, further comprising: the end cover part is connected with the first end of the cylinder assembly in a sealing mode through the connecting assembly; the connecting assembly includes:
the bolt hole is arranged on the barrel assembly;
a bolt disposed in the bolt hole connecting the first end of the barrel assembly and the end cap portion;
and the guide rod is arranged in the bolt hole in a penetrating manner.
CN202111229816.8A 2021-10-22 2021-10-22 Fast reactor spent fuel transport container structure Pending CN113948233A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202111229816.8A CN113948233A (en) 2021-10-22 2021-10-22 Fast reactor spent fuel transport container structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202111229816.8A CN113948233A (en) 2021-10-22 2021-10-22 Fast reactor spent fuel transport container structure

Publications (1)

Publication Number Publication Date
CN113948233A true CN113948233A (en) 2022-01-18

Family

ID=79332081

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202111229816.8A Pending CN113948233A (en) 2021-10-22 2021-10-22 Fast reactor spent fuel transport container structure

Country Status (1)

Country Link
CN (1) CN113948233A (en)

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