CN116759129A - Container barrel of radioactive waste storage and radioactive waste storage - Google Patents
Container barrel of radioactive waste storage and radioactive waste storage Download PDFInfo
- Publication number
- CN116759129A CN116759129A CN202310895685.XA CN202310895685A CN116759129A CN 116759129 A CN116759129 A CN 116759129A CN 202310895685 A CN202310895685 A CN 202310895685A CN 116759129 A CN116759129 A CN 116759129A
- Authority
- CN
- China
- Prior art keywords
- radioactive waste
- layer
- container
- shielding
- container barrel
- 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
Links
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 97
- 239000010410 layer Substances 0.000 claims abstract description 100
- 238000007789 sealing Methods 0.000 claims abstract description 35
- 239000011241 protective layer Substances 0.000 claims abstract description 30
- 239000000843 powder Substances 0.000 claims abstract description 19
- 239000011347 resin Substances 0.000 claims abstract description 17
- 229920005989 resin Polymers 0.000 claims abstract description 17
- 239000004698 Polyethylene Substances 0.000 claims description 8
- -1 polyethylene Polymers 0.000 claims description 8
- 229920000573 polyethylene Polymers 0.000 claims description 8
- 230000003014 reinforcing effect Effects 0.000 claims description 7
- 239000000805 composite resin Substances 0.000 claims description 6
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 4
- 229910000416 bismuth oxide Inorganic materials 0.000 claims description 4
- TYIXMATWDRGMPF-UHFFFAOYSA-N dibismuth;oxygen(2-) Chemical compound [O-2].[O-2].[O-2].[Bi+3].[Bi+3] TYIXMATWDRGMPF-UHFFFAOYSA-N 0.000 claims description 4
- NJLLQSBAHIKGKF-UHFFFAOYSA-N dipotassium dioxido(oxo)titanium Chemical compound [K+].[K+].[O-][Ti]([O-])=O NJLLQSBAHIKGKF-UHFFFAOYSA-N 0.000 claims description 4
- WABPQHHGFIMREM-UHFFFAOYSA-N lead(0) Chemical compound [Pb] WABPQHHGFIMREM-UHFFFAOYSA-N 0.000 claims description 4
- 239000010445 mica Substances 0.000 claims description 4
- 229910052618 mica group Inorganic materials 0.000 claims description 4
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 claims description 4
- 229920001903 high density polyethylene Polymers 0.000 abstract description 15
- 239000004700 high-density polyethylene Substances 0.000 abstract description 15
- 230000005855 radiation Effects 0.000 abstract description 12
- 239000002699 waste material Substances 0.000 description 35
- 229910000831 Steel Inorganic materials 0.000 description 6
- 239000004567 concrete Substances 0.000 description 6
- 239000010959 steel Substances 0.000 description 6
- 239000002657 fibrous material Substances 0.000 description 5
- 238000000034 method Methods 0.000 description 5
- 239000004568 cement Substances 0.000 description 4
- 230000018044 dehydration Effects 0.000 description 4
- 238000006297 dehydration reaction Methods 0.000 description 4
- 239000000835 fiber Substances 0.000 description 4
- 238000007711 solidification Methods 0.000 description 4
- 230000008023 solidification Effects 0.000 description 4
- KXGFMDJXCMQABM-UHFFFAOYSA-N 2-methoxy-6-methylphenol Chemical compound [CH]OC1=CC=CC([CH])=C1O KXGFMDJXCMQABM-UHFFFAOYSA-N 0.000 description 3
- 229920002748 Basalt fiber Polymers 0.000 description 3
- 229920000049 Carbon (fiber) Polymers 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 3
- 239000004917 carbon fiber Substances 0.000 description 3
- 239000003822 epoxy resin Substances 0.000 description 3
- 239000003365 glass fiber Substances 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 239000005011 phenolic resin Substances 0.000 description 3
- 229920001568 phenolic resin Polymers 0.000 description 3
- 229920000647 polyepoxide Polymers 0.000 description 3
- 229920005749 polyurethane resin Polymers 0.000 description 3
- 229920006305 unsaturated polyester Polymers 0.000 description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- 101150114468 TUB1 gene Proteins 0.000 description 2
- 239000006185 dispersion Substances 0.000 description 2
- 229920001684 low density polyethylene Polymers 0.000 description 2
- 239000004702 low-density polyethylene Substances 0.000 description 2
- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical compound C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 description 2
- 239000002910 solid waste Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 239000002131 composite material Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Classifications
-
- 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
-
- 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
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/12—Laminated shielding materials
- G21F1/125—Laminated shielding materials comprising metals
-
- 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
Abstract
The invention discloses a container barrel of a radioactive waste memory and the radioactive waste memory, relates to the technical field of nuclear power, and aims to solve the problem that the container barrel of a high-density polyethylene memory is poor in radiation shielding capacity and strength. The container barrel of the radioactive waste memory comprises a sealing layer, a shielding layer and a protective layer; the sealing layer, the shielding layer and the protective layer are of barrel-shaped structures with openings at one sides and are of integrated structures; the sealing layer is used for ensuring tightness; the shielding layer is sleeved outside the sealing layer and is a mixed layer of high-density shielding powder and resin; the protective layer is sleeved on the outer side of the shielding layer and is used for protecting the shielding layer and the sealing layer. The radioactive waste storage comprises the container barrel according to the technical scheme. The container barrel of the radioactive waste storage and the radioactive waste storage are used for storing medium-low radioactive waste, and are good in strength and small in quality.
Description
Technical Field
The invention relates to the technical field of nuclear power waste storage, in particular to a container barrel of a radioactive waste storage and the radioactive waste storage.
Background
In recent years, with the development of the nuclear power industry, a large amount of nuclear waste is generated, wherein the proportion of waste with low radioactivity in waste resin, activated carbon, waste filter cores, evaporated boron-containing waste liquid and the like in all the nuclear waste is up to 99%, and the waste with low radioactivity needs to be placed in a special storage container in order to avoid the influence of the waste with low radioactivity on the environment and staff.
At present, in order to facilitate the storage and transportation of the wastes with medium and low radioactivity, the storage containers for the wastes with medium and low radioactivity mainly comprise a steel structure storage container, a concrete barrel storage container and a high-density polyethylene storage container, wherein the steel structure storage container and the concrete barrel storage container are used for storing the wastes with medium and low radioactivity in a cement solidification mode, so that the wastes with medium and low radioactivity in a liquid state are converted into solid waste objects with stable physical and chemical properties and difficult dispersion, but the weight and the volume of the radioactive wastes are greatly reduced before the dehydration due to the fact that the solidification mode of adding cement can cause the weight increase and the capacity increase of the radioactive wastes, so that the steel structure storage container and the concrete storage container are used for storing the radioactive wastes with larger mass and inconvenient transportation, and therefore, the high-density polyethylene storage container is usually adopted at present, the dehydrated residual wastes are arranged in the container barrel of the high-density polyethylene storage for storage and transportation after being filtered by a filter loaded by equipment and dehydrated by a dehydration device, and the weight and the volume of the dehydrated residual wastes are greatly reduced before being dehydrated, and the storage and transportation are convenient.
However, the dehydrated residual waste still has radioactivity, but the radiation shielding capability of the high-density polyethylene is poor, so that the radiation of the dehydrated residual waste can be transmitted to the outside through the container barrel of the high-density polyethylene memory, and further the body of a worker is endangered, and in addition, the strength of the high-density polyethylene container barrel is poor.
Disclosure of Invention
The invention aims to provide a container barrel of a radioactive waste storage and the radioactive waste storage, which are used for storing dehydrated waste with medium and low radioactivity, shielding rays of the waste with medium and low radioactivity and improving the strength of the container barrel.
In order to achieve the above object, the present invention provides the following technical solutions:
a container barrel of a radioactive waste storage, comprising a sealing layer, a shielding layer and a protective layer;
the sealing layer, the shielding layer and the protective layer are of barrel-shaped structures with openings at one sides, and the sealing layer, the shielding layer and the protective layer are of integrated structures;
the sealing layer is used for guaranteeing the tightness of the container barrel;
the shielding layer is sleeved on the outer side of the sealing layer, is a mixed layer of high-density shielding powder and resin and is used for shielding rays;
the protective layer is sleeved on the outer side of the shielding layer and is used for protecting the shielding layer and the sealing layer and providing the overall structural strength of the container.
Compared with the prior art, the sealing layer in the container barrel of the radioactive waste storage can ensure that medium-low radioactive waste placed in the sealing layer cannot leak out of the container barrel of the radioactive waste storage through the container barrel; the shielding layer is a mixed layer of high-density shielding powder and resin, wherein the high-density shielding powder can shield radiation rays of medium-low radioactive wastes, and the high-density shielding powder is fixed together through the resin to form a layer structure, so that the container barrel has the capability of shielding the radiation rays; the protective layer has good strength, is arranged at the outermost side, can protect the shielding layer and the sealing layer, and improves the strength of the container barrel of the radioactive waste storage. Based on the above, the container barrel of the radioactive waste storage can store dehydrated waste with medium and low radioactivity, and compared with the container barrel of the high-density polyethylene storage, the container barrel of the radioactive waste storage can shield the radiation of the waste with medium and low radioactivity and has higher strength.
Optionally, in the container barrel of the radioactive waste storage, the sealing layer is a polyethylene layer.
Optionally, in the container barrel of the radioactive waste storage, the polyethylene layer has a thickness of 3mm to 15mm.
Optionally, in the container barrel of the radioactive waste storage, the high-density shielding powder in the shielding layer is one of lead powder, tungsten powder, iron powder, bismuth oxide, potassium titanate whisker and mica powder.
Optionally, in the container barrel of the radioactive waste storage, the thickness of the shielding layer is 2mm-10mm.
Optionally, in the container barrel of the radioactive waste storage, the protective layer is a fiber resin composite layer.
Optionally, in the container barrel of the radioactive waste storage, the fiber material in the fiber resin composite layer includes one of carbon fiber, glass fiber and basalt fiber; the resin in the fiber resin composite layer includes one of epoxy resin, polyurethane resin, phenolic resin and unsaturated polyester.
Optionally, in the container barrel of the radioactive waste storage, the thickness of the protective layer is 5mm-20mm.
The invention also provides a radioactive waste storage, comprising the container barrel of the radioactive waste storage.
Compared with the prior art, the beneficial effects of the radioactive waste storage provided by the invention are the same as those of the container barrel of the radioactive waste storage in the technical scheme, and the description is omitted here.
Optionally, in the radioactive waste storage, the radioactive waste storage further includes a container cover;
the container cover is arranged at the opening end of the container barrel of the radioactive waste storage and is connected with the container barrel of the radioactive waste storage in a threaded manner.
Optionally, in the radioactive waste storage, the radioactive waste storage further includes a reinforcing frame;
the reinforcing frame comprises an upper fixed ring, a bottom frame and a vertical frame, wherein the upper fixed ring is arranged on the top edge of the container cover in a surrounding mode, the bottom frame is arranged at the bottom of the container barrel of the radioactive waste storage in a supporting mode, the two ends of the vertical frame are respectively connected with the upper fixed ring and the bottom frame, stacking of containers is facilitated, and storage space is saved.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description serve to explain the invention and do not constitute a limitation on the invention. In the drawings:
FIG. 1 is a schematic illustration of a container bucket and container lid of a radioactive waste memory provided in an embodiment of the present invention;
FIG. 2 is an enlarged view of FIG. 1 at A;
fig. 3 is a schematic diagram of a radioactive waste storage according to an embodiment of the present invention.
Reference numerals:
1-a container barrel; 11-a sealing layer; 12-a shielding layer; 13-a protective layer; 2-a container lid; 3-reinforcing the frame; 31-fixing the ring; 32-a bottom frame; 33-mullion.
Detailed Description
In order to make the technical problems, technical schemes and beneficial effects to be solved more clear, the invention is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the invention.
It will be understood that when an element is referred to as being "mounted" or "disposed" on another element, it can be directly on the other element or be indirectly on the other element. When an element is referred to as being "connected to" another element, it can be directly connected to the other element or be indirectly connected to the other element.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include one or more such feature. In the description of the present invention, the meaning of "a plurality" is two or more, unless explicitly defined otherwise. The meaning of "a number" is one or more than one unless specifically defined otherwise.
In the description of the present invention, it should be understood that the directions or positional relationships indicated by the terms "upper", "lower", "front", "rear", "left", "right", etc., are based on the directions or positional relationships shown in the drawings, are merely for convenience of describing the present invention and simplifying the description, and do not indicate or imply that the devices or elements referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be either fixedly connected, detachably connected, or integrally connected, for example; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communicated with the inside of two elements or the interaction relationship of the two elements. The specific meaning of the above terms in the present invention can be understood by those of ordinary skill in the art according to the specific circumstances.
At present, in order to facilitate the storage and transportation of the wastes with medium and low radioactivity, the storage containers for the wastes with medium and low radioactivity mainly comprise a steel structure storage container, a concrete barrel storage container and a high-density polyethylene storage container, wherein the steel structure storage container and the concrete barrel storage container are used for storing the wastes with medium and low radioactivity in a cement solidification mode, so that the wastes with medium and low radioactivity in a liquid state are converted into solid waste objects with stable physical and chemical properties and difficult dispersion, but the weight and the volume of the radioactive wastes are greatly reduced before the dehydration due to the fact that the solidification mode of adding cement can cause the weight increase and the capacity increase of the radioactive wastes, so that the steel structure storage container and the concrete storage container are used for storing the radioactive wastes with larger mass and inconvenient transportation, and therefore, the high-density polyethylene storage container is usually adopted at present, the dehydrated residual wastes are arranged in the container barrel of the high-density polyethylene storage for storage and transportation after being filtered by a filter loaded by equipment and dehydrated by a dehydration device, and the weight and the volume of the dehydrated residual wastes are greatly reduced before being dehydrated, and the storage and transportation are convenient. However, the dehydrated residual waste still has radioactivity, but the radiation shielding capability of the high-density polyethylene is poor, so that the radiation of the dehydrated residual waste can be transmitted to the outside through the container barrel of the high-density polyethylene memory, and further the body of a worker is endangered, and in addition, the strength of the high-density polyethylene container barrel is poor.
In order to solve the above technical problems, referring to fig. 1 and 2, a container of a radioactive waste memory provided in an embodiment of the present invention includes a sealing layer 11, a shielding layer 12 and a protecting layer 13; the sealing layer 11, the shielding layer 12 and the protective layer 13 are of barrel-shaped structures with openings at one sides, and the sealing layer 11, the shielding layer 12 and the protective layer 13 are of integrated structures; the sealing layer 11 is used for guaranteeing the tightness of the container barrel of the radioactive waste storage; the shielding layer 12 is sleeved outside the sealing layer 11, and the shielding layer 12 is a mixed layer of high-density shielding powder and resin and is used for shielding rays; the protective layer 13 is sleeved outside the shielding layer 12 and is used for protecting the shielding layer 12 and the sealing layer 11.
In the preparation process, the prepared mixture of high-density shielding powder and resin is coated on the outer side of the sealing layer 11 until a certain thickness is reached to form the shielding layer 12, and then the protective layer 13 is paved on the outer side of the shielding layer 12 to form the container barrel 1 of the radioactive waste storage with an integrated structure. In a specific use process, the waste with medium and low radioactivity is filtered and dehydrated, and then the dehydrated waste with medium and low radioactivity is placed in the sealing layer 11.
According to the structure and the implementation process of the container barrel of the radioactive waste storage, the sealing layer 11 can ensure that the medium-low radioactive waste placed in the sealing layer 11 cannot leak out of the container barrel 1 of the radioactive waste storage through the container barrel 1 of the radioactive waste storage; the shielding layer 12 is a mixed layer of high-density shielding powder and resin, wherein the high-density shielding powder can shield radiation rays of medium-low radioactive wastes, and the high-density shielding powder is fixed together through the resin to form a layer structure, and it is noted that the high-density shielding powder and the resin in the scheme are simply mixed and the mixed material is not improved; the protective layer 13 has excellent strength, is provided on the outermost side, and can protect the shielding layer 12 and the sealing layer 11, thereby improving the strength of the container barrel 1 of the radioactive waste storage. Based on the above, the container barrel of the radioactive waste storage can store dehydrated waste with medium and low radioactivity, and compared with the container barrel of the high-density polyethylene storage, the container barrel 1 of the radioactive waste storage can shield the radiation of the waste with medium and low radioactivity and has higher strength.
Specifically, in some embodiments, the sealing layer 11 is a polyethylene layer; preferably, the polyethylene layer is a low density polyethylene layer. The polyethylene has better corrosion resistance, can ensure the tightness of the container barrel of the radioactive waste storage in the use process, has low cost of the low-density polyethylene layer, reduces the density of the container barrel of the radioactive waste storage and lightens the weight.
Specifically, in some embodiments, the polyethylene layer has a thickness of 3mm-15mm, illustratively 3mm, 4mm, 5mm, 6mm, 8mm, 10mm, 12mm, 14mm, 15mm, etc. So set up, when guaranteeing the leakproofness, the volume of the container bucket of radioactive waste memory is less.
In the present embodiment, the high-density shielding powder in the shielding layer 12 is one of lead powder, tungsten powder, iron powder, bismuth oxide, potassium titanate whisker, and mica powder. Lead powder, tungsten powder, iron powder, bismuth oxide, potassium titanate whisker and mica powder can well shield nuclear waste radiation rays, such as gamma rays, and ensure the capability of shielding the nuclear waste radiation rays of the container barrel of the radioactive waste storage.
Specifically, in some embodiments, the thickness of the shielding layer in the container barrel of the radioactive waste storage is 2mm-10mm; illustratively, the thickness of the shielding layer is 2mm, 2.5mm, 3mm, 4mm, 5mm, 6mm, 8mm, 10mm, etc.
In some embodiments, the protective layer 13 is a fibrous resin composite layer. The fiber-resin composite layer includes a fiber material and a resin material, the fiber material being optionally doped in the resin, and coated on the outside of the shielding layer 12 to form an integral structure. The composite material formed by the fiber material and the resin has better strength and impact resistance, and ensures the stability of the container barrel of the radioactive waste storage in the use process.
Illustratively, the fibrous material in the protective layer 13 includes one or more of carbon fibers, glass fibers, and basalt fibers; the resin in the protective layer 13 includes one of epoxy resin, polyurethane resin, phenolic resin, and unsaturated polyester. The carbon fiber, glass fiber and basalt fiber are simply mixed with epoxy resin, polyurethane resin, phenolic resin or unsaturated polyester, and different fiber layers can be stacked and coated by resin to form a protective layer 13; the protective layer 13 is disposed on the outermost layer to secure the strength of the container.
Specifically, in the above-mentioned container barrel of the radioactive waste storage, the thickness of the protective layer 13 is 5mm to 20mm. Illustratively, the thickness of the protective layer 13 may be 5mm, 6mm, 7mm, 8mm, 9mm, 10mm, 11mm, 12mm, 14mm, 16mm, 18mm, 20mm, etc. The protective layer 13 of this thickness is able to guarantee a small volume with good strength of the container tub of the radioactive waste storage.
Referring to fig. 1 and 3, an embodiment of the present invention also provides a radioactive waste memory including the container barrel 1 of the radioactive waste memory described in any of the above embodiments.
Compared with the prior art, the beneficial effects of the radioactive waste storage provided by the invention are the same as those of the container barrel of the radioactive waste storage in the technical scheme, and the description is omitted here.
As an alternative, in the radioactive waste container described above, the radioactive waste container further includes a container cover 2; the container cover 2 is provided at an open end of the container tub 1 of the radioactive waste storage and is screw-coupled with the container tub 1 of the radioactive waste storage. So arranged, the radioactive waste reservoir can be sealed by the container lid 2.
As an alternative, in the radioactive waste container described above, the radioactive waste container further includes a reinforcing frame 3; the reinforcing frame 3 comprises an upper fixing ring 31, a bottom frame 32 and a vertical frame 33, wherein the upper fixing ring 31 surrounds the top edge of the container cover 2, the bottom frame 32 supports the bottom of the container barrel 1 arranged on the radioactive waste storage, and two ends of the vertical frame 33 are respectively connected with the upper fixing ring 31 and the bottom frame 32. The number of the mullions 33 is plural, and the mullions 33 are uniformly distributed along the circumferential direction, and the number of the mullions 33 can be plural, such as two, three, four, five, six, etc., and the container cover 2 and the container barrel 1 are further fixed through the reinforcing frame 3, so that the stability of the radioactive waste storage in the storage and transportation process is enhanced.
In the description of the above embodiments, particular features, structures, materials, or characteristics may be combined in any suitable manner in any one or more embodiments or examples.
The foregoing is merely illustrative of the present invention, and the present invention is not limited thereto, and any person skilled in the art will readily recognize that variations or substitutions are within the scope of the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (10)
1. A container for a radioactive waste storage, comprising a sealing layer, a shielding layer and a protective layer;
the sealing layer, the shielding layer and the protective layer are of barrel-shaped structures with openings at one sides, and the sealing layer, the shielding layer and the protective layer are of integrated structures;
the sealing layer is used for guaranteeing the tightness of the container barrel;
the shielding layer is sleeved on the outer side of the sealing layer, is a mixed layer of high-density shielding powder and resin and is used for shielding rays;
the protective layer is sleeved on the outer side of the shielding layer and is used for protecting the shielding layer and the sealing layer.
2. The radioactive waste memory container barrel of claim 1, wherein the sealing layer is a polyethylene layer.
3. The radioactive waste memory container barrel of claim 2, wherein the polyethylene layer has a thickness of 3mm-15mm.
4. The radioactive waste memory container barrel of claim 1, wherein the high density shielding powder in the shielding layer is one of lead powder, tungsten powder, iron powder, bismuth oxide, potassium titanate whiskers, and mica powder.
5. The radioactive waste memory container barrel of claim 1, wherein the shielding layer has a thickness of 2mm-10mm.
6. The radioactive waste reservoir container barrel of claim 1, wherein the protective layer is a fibrous resin composite layer.
7. The radioactive waste memory container barrel of claim 6, wherein the protective layer has a thickness of 5mm-20mm.
8. A radioactive waste memory comprising the container barrel of the radioactive waste memory of any one of claims 1 to 7.
9. The radioactive waste memory of claim 8, wherein the radioactive waste memory further comprises a container lid;
the container cover is arranged at the opening end of the container barrel of the radioactive waste storage and is in threaded connection with the container barrel of the radioactive waste storage.
10. The radioactive waste memory of claim 9, wherein the radioactive waste memory further comprises a reinforcing frame;
the reinforcing frame comprises an upper fixed ring, a bottom frame and a vertical frame, wherein the upper fixed ring is surrounded and arranged on the top edge of the container cover, the bottom frame is supported and arranged at the bottom of the container barrel of the radioactive waste storage, and two ends of the vertical frame are respectively connected with the upper fixed ring and the bottom frame.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310895685.XA CN116759129A (en) | 2023-07-20 | 2023-07-20 | Container barrel of radioactive waste storage and radioactive waste storage |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310895685.XA CN116759129A (en) | 2023-07-20 | 2023-07-20 | Container barrel of radioactive waste storage and radioactive waste storage |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN116759129A true CN116759129A (en) | 2023-09-15 |
Family
ID=87953362
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310895685.XA Pending CN116759129A (en) | 2023-07-20 | 2023-07-20 | Container barrel of radioactive waste storage and radioactive waste storage |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN116759129A (en) |
-
2023
- 2023-07-20 CN CN202310895685.XA patent/CN116759129A/en active Pending
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