CN111430057B - High radioactive nuclear waste container - Google Patents
High radioactive nuclear waste container Download PDFInfo
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- CN111430057B CN111430057B CN202010190468.7A CN202010190468A CN111430057B CN 111430057 B CN111430057 B CN 111430057B CN 202010190468 A CN202010190468 A CN 202010190468A CN 111430057 B CN111430057 B CN 111430057B
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- powder
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- waste container
- ceramsite
- buffer layer
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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
- G21F5/08—Shock-absorbers, e.g. impact buffers for containers
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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
- G21F5/002—Containers for fluid radioactive wastes
-
- 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
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
- G21F9/22—Disposal of liquid waste by storage in a tank or other container
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
Abstract
The invention relates to a high-radioactive nuclear waste container, comprising: the high-radioactivity nuclear fuel packaging structure comprises a metal shell, a buffer layer and a packaging body, wherein high-radioactivity spent nuclear fuel is arranged in the packaging body, the packaging body and the buffer layer are both arranged in the metal shell, and the buffer layer is located between the metal shell and the packaging body; the buffer layer is made of a mixture of skeleton particles, desiccant powder and neutron absorber powder, the particle size of the skeleton particles is larger than that of the desiccant powder, and the particle size of the skeleton particles is larger than that of the neutron absorber powder. When the high-radioactive nuclear waste container is extruded, the framework particles, the desiccant powder and the neutron absorber powder in the buffer layer can form corresponding shape changes at the extruded part while the metal shell deforms, so that the high-radioactive nuclear waste container cannot be cracked due to extrusion to cause nuclear leakage.
Description
Technical Field
The invention relates to the field of high-risk radiation protection, in particular to a high-radioactive nuclear waste container.
Background
With the rapid development of the nuclear industry, a large amount of nuclear waste is generated. According to the intensity of radioactivity, nuclear waste comprises low-level radioactive nuclear waste, middle-level radioactive nuclear waste and high-level radioactive nuclear waste, wherein the low-level radioactive nuclear waste and the middle-level radioactive nuclear waste mainly refer to pollution equipment, detection equipment, a hydration system during operation, exchange resin, waste water, waste liquid, gloves and other labor protection supplies of a nuclear power station, the high-level radioactive nuclear waste refers to a burnt nuclear fuel rod which is replaced from a reactor core of the nuclear power station, the burnt nuclear fuel rod still has extremely strong radioactivity, and the half life of the burnt nuclear fuel rod is thousands of years, tens of thousands of years or even tens of thousands of years.
The international atomic energy organization has strict requirements on treatment and disposal of nuclear waste, adopts the modes of dilution, concentration and recovery for medium-level and low-level radioactive nuclear waste to recover about 93 percent of nuclear raw materials, reduces nuclear radiation damage to the minimum, cannot treat high-level radioactive nuclear waste, and only can carry out permanent deep-burying disposal, wherein the permanent disposal means that the nuclear raw materials can be deeply sealed and stored for tens of thousands of years or even tens of thousands of years and cannot be leaked.
Permanent disposal entails two problems: firstly, the nuclear waste is required to be safely and permanently sealed in a container, and the radioactivity is ensured not to be leaked out within tens of thousands of years; second, a safe and permanent site for nuclear waste is sought.
Both marine and terrestrial methods are commonly used internationally to permanently dispose of high levels of radioactive nuclear waste. The nuclear waste is made into vitrified solid, and is filled into a metal tank capable of shielding radiation, and then the metal tank filled with the nuclear waste is thrown into the seabed of a selected sea area below 4000 meters, or is deeply buried in a nuclear waste disposal warehouse built in an underground super-thick rock stratum.
When the metal tank containing the nuclear waste is deeply buried in an underground nuclear waste disposal warehouse, because the metal container needs to be deeply buried for tens of thousands of years, under a large time scale, the rock can be deformed to extrude the nuclear waste metal container, and the nuclear waste metal container can be broken due to extrusion to cause nuclear leakage, thereby polluting soil.
Disclosure of Invention
In view of this, there is a need to provide a high radionuclide waste container that does not rupture upon squeezing, resulting in nuclear leakage.
A high radionuclide waste container comprising: the high-radioactivity nuclear fuel packaging structure comprises a metal shell, a buffer layer and a packaging body, wherein high-radioactivity spent nuclear fuel is arranged in the packaging body, the packaging body and the buffer layer are both arranged in the metal shell, and the buffer layer is located between the metal shell and the packaging body;
the buffer layer is made of a mixture of skeleton particles, desiccant powder and neutron absorber powder, the particle size of the skeleton particles is larger than that of the desiccant powder, and the particle size of the skeleton particles is larger than that of the neutron absorber powder.
The buffer layer is arranged between the metal shell and the packaging body of the high-radioactive nuclear waste container, the buffer layer is made of a mixture formed by the skeleton particles, the desiccant powder and the neutron absorber powder, when the high-radioactive nuclear waste container is extruded, the metal shell deforms, and meanwhile, the skeleton particles, the desiccant powder and the neutron absorber powder in the buffer layer can form corresponding shape changes at the extruded part, so that the high-radioactive nuclear waste container cannot be cracked due to extrusion to cause nuclear leakage.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
Wherein:
fig. 1 is a perspective view of a high radionuclide waste container according to an embodiment.
Fig. 2 is a schematic cross-sectional view of the high radionuclide waste container shown in fig. 1.
Detailed Description
In order that the invention may be more fully understood, reference will now be made to the following description taken in conjunction with the accompanying drawings. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs. The terminology used in the description of the invention herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention.
One embodiment of a high radionuclide waste container 100, as shown in fig. 1 and 2, includes: the high-radioactivity nuclear fuel cell comprises a metal shell 10, a buffer layer 20 and a packaging body 30, wherein high-radioactivity spent nuclear fuel 36 is arranged in the packaging body 30, the packaging body 30 and the buffer layer 20 are both arranged in the metal shell 10, and the buffer layer 20 is located between the metal shell 10 and the packaging body 30.
The material of the buffer layer 20 is a mixture of skeleton particles, desiccant powder and neutron absorber powder. The particle size of the skeletal particles is greater than the particle size of the desiccant powder, and the particle size of the skeletal particles is greater than the particle size of the neutron absorber powder.
The buffer layer 20 is arranged between the metal shell 10 and the packaging body 30 of the high-radioactive nuclear waste container 100, the buffer layer 20 comprises skeleton particles and filling powder, when the high-radioactive nuclear waste container 100 is extruded, the skeleton particles, the drying agent powder and the neutron absorber in the buffer layer 20 can form corresponding shape changes at the extruded part while the metal shell 10 deforms, and therefore the high-radioactive nuclear waste container 100 cannot be cracked due to extrusion to cause nuclear leakage.
The particle size of skeleton granule is greater than the particle size of drier powder to the particle size of skeleton granule is greater than the particle size of neutron absorbent powder, makes buffer layer 20 more take place deformation through the combination of the skeleton granule of different particle sizes, drier powder and neutron absorbent powder when receiving the extrusion on the one hand, and on the other hand the combination of the skeleton granule of different particle sizes, drier powder and neutron absorbent powder also makes buffer layer 20 can form better protection to packaging body 30, avoids packaging body 30 broken.
Specifically, the skeleton particles function as a support skeleton, and the desiccant powder and the neutron absorber powder are filled in gaps between the skeleton particles to function as similar lubrication.
The desiccant powder also serves to absorb moisture and prevent minute amounts of water vapor from penetrating into the package 30 during a ten thousand year disposal period. Therefore, on one hand, the container is prevented from being corroded by moisture, and on the other hand, the container is prevented from being expanded or exploded due to the fact that the moisture absorbs radiation and is expanded into water vapor in a closed space.
The neutron absorber powder can absorb a small amount of radiation leaked from the interior of the package 30, reduce radiation pollution to rocks, geology and soil, and play a better role in protection.
Mixing the skeleton particles and the filling powder according to a proper proportion. Preferably, the volume ratio of the skeleton particles to the desiccant powder to the neutron absorber powder is 4-12: 1-9: 11 to 35.
Preferably, the buffer layer 20 has a thickness of 100mm to 200 mm.
Preferably, the particle size of the skeleton particle is 1mm to 10mm, the particle size of the desiccant powder is 23 μm to 75 μm, and the particle size of the neutron absorber powder is 1 μm to 100 μm.
The particle size of the framework particles is 1-10 mm, so that a reasonable supporting effect can be achieved, the particle size of the drying agent powder is 23-75 mu m, and the particle size of the neutron absorber powder is 1-100 mu m, so that the two kinds of powder can be filled in gaps of the framework particles, and a similar lubricating effect can be achieved.
More preferably, the particle size of the skeletal particles is 1mm to 3 mm.
Preferably, the skeleton particles are ceramsite and/or foam metal particles.
In order to improve the density of the buffer layer 20 and avoid the layering phenomenon caused by different gravity of each component in the transmission process, the framework particles are preferably porous particles, so that the desiccant powder and the neutron absorber powder can be filled in the surface pores of the porous particles and filled in the gaps among the porous particles, the filling is more compact, the supporting force is larger, the framework particles can be uniformly distributed in the transportation process, and the layering is avoided.
Preferably, the skeleton particles are ceramsite and/or foam metal particles.
The ceramsite is granular solid with pores inside and made of fired clay, is a product processed at high temperature, has stable physical and chemical properties and low price, and cannot have performance change even if being in an environment deep in the ground for a long time. The ceramsite has certain hardness and can play a role in supporting, when the ceramsite is extruded, the granular structure of the ceramsite is rearranged to absorb deformation, and pores in the ceramsite can also absorb air and moisture.
Specifically, the ceramsite can be one, two or more than three of rare earth ceramsite, attapulgite ceramsite, kaolin ceramsite, montmorillonite ceramsite, vermiculite ceramsite, illite ceramsite and allophane ceramsite.
In particular, the attapulgite ceramsite has the comprehensive properties of unique dispersion, high temperature resistance, saline-alkali resistance and the like, such as good colloidal properties and the like, has the highest strength, and also has the best heat insulation property, water absorption property, air permeability and stability.
In particular, the kaolin ceramsite has the highest strength, and the comprehensive properties of heat insulation, water absorption, air permeability, stability and the like are optimal.
The foam metal is a special metal material containing foam pores, and the foam metal not only has certain hardness, but also can absorb deformation.
Specifically, the foamed metal particles are selected from one, two or more than three of foamed aluminum particles, foamed nickel particles, foamed copper particles and foamed metal alloy particles.
The neutron absorber powder is one, two or more selected from lead powder, ferrosteel powder, silicon dioxide powder, borax, boron carbide powder, boron steel powder, amorphous carbon powder, carbon nano-tubes, carbon nano-cages and graphite powder.
The neutron absorber powder is preferably selected from lead powder, silicon dioxide powder and graphite powder, the lead powder can effectively absorb neutrons, the graphite powder is a neutron moderator, meanwhile, the graphite powder also has lubricity and can enhance the fluidity of each component in the buffer layer 20, the silicon dioxide powder is a main component of glass and has the main function of resisting rays and can be heated and melted to re-solidify and seal leaked nuclear waste under extreme conditions (such as nuclear waste leakage caused by corrosion or stress damage). Thus, the radiation protective composition of the present invention can satisfy the response to corrosion, external compressive stress and nuclear leakage over an ultra-long time span.
Preferably, the desiccant powder is a neutral desiccant powder. The neutral desiccant powder can prevent the desiccant powder from generating acidity or alkalinity after absorbing moisture, thereby causing corrosion to a package or a metal shell.
The neutral desiccant powder is one, two or more selected from anhydrous calcium chloride powder, molecular sieve powder, silica gel powder, attapulgite powder, calcium sulfate powder, aluminum oxide powder and sodium sulfate powder.
In view of the combination of cost, water absorption, high temperature stability and radiation resistance, the neutral desiccant powder is most preferably attapulgite powder because the salt, adsorption and colloid resistance of attapulgite is higher than other desiccant powders.
In a specific embodiment, the buffer layer 20 is made of, by volume: 4 to 12 portions of kaolin ceramsite, 1 to 9 portions of attapulgite powder, 6 to 14 portions of lead powder, 4 to 12 portions of silicon dioxide powder and 1 to 9 portions of graphite powder.
In a particularly preferred embodiment, the buffer layer 20 is made of, in parts by volume: 7 to 9 portions of kaolin ceramsite, 3 to 7 portions of attapulgite powder, 7 to 9 portions of lead powder, 6 to 10 portions of silicon dioxide powder and 3 to 7 portions of graphite powder.
Referring to the drawings, in the present embodiment, the package 30 includes a waterproof housing 32, an inner liner 34 and a high-radioactivity spent nuclear fuel 36 in sequence from outside to inside, and the inner liner 34 is located between the waterproof housing 32 and the high-radioactivity spent nuclear fuel 36.
The number of packages 30 contained within the high radionuclide waste container 100 may be set according to practical needs. In the present embodiment, the number of the highly radioactive spent nuclear fuel 36 is 1. In other embodiments, the number of packages 30 may also be 2, 3, 4, 5, 6, 7, 8, 9, 10, or even more.
In the present embodiment, the waterproof case 32 is a stainless steel case. The stainless steel shell can play a good waterproof role, and meanwhile, the stainless steel shell also has good mechanical properties, so that the high-radioactivity spent nuclear fuel 36 in the stainless steel shell can be well protected.
In the present embodiment, the liner layer 34 is a lead liner layer. The lead lining layer may absorb the radiation of the highly radioactive spent nuclear fuel 36.
In the present embodiment, the highly radioactive spent nuclear fuel 36 is a highly radioactive spent nuclear fuel rod wrapped in a solidified glass body.
In the present embodiment, the metal case 10 is made of a copper-manganese alloy. The copper-manganese alloy has excellent corrosion resistance, and combined with the three-star heap bronze ware made of the copper-manganese alloy unearthed in China, the history of the three-star heap bronze ware is 5000 years ago, and the detection shows that the surface of the copper-manganese alloy is only slightly corroded and the metallicity of the copper-manganese alloy is still good although the copper-manganese alloy is deeply buried for thousands of years. Therefore, the metal case 10 is preferably a copper-manganese alloy.
In the present embodiment, with reference to the drawings, the periphery of the high-level radioactive nuclear waste container 100 is provided with a plurality of guide structures 12 which are distributed in a central symmetry manner. The guide structure 12 may be used to cooperate with a guide rail to achieve guiding movement of the high radionuclide waste container 100, so that the high radionuclide waste container 100 can be smoothly transferred to a destination position.
Specifically, the guide structure 12 is a guide groove 12, and the extending direction of the guide groove 12 is parallel to the axial direction of the high radionuclide waste container 100.
The above-mentioned embodiments only express several embodiments of the present invention, and the description thereof is more specific and detailed, but not construed as limiting the claims. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the inventive concept, which falls within the scope of the present invention. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (9)
1. A high radionuclide waste container, comprising: the high-radioactivity nuclear fuel packaging structure comprises a metal shell, a buffer layer and a packaging body, wherein high-radioactivity spent nuclear fuel is arranged in the packaging body, the packaging body and the buffer layer are both arranged in the metal shell, and the buffer layer is located between the metal shell and the packaging body;
the material of the buffer layer is a mixture formed by skeleton particles, desiccant powder and neutron absorber powder, the particle size of the skeleton particles is larger than that of the desiccant powder, and the particle size of the skeleton particles is larger than that of the neutron absorber powder;
the particle size of the skeleton particles is 1-10 mm;
in the buffer layer, the volume ratio of the skeleton particles to the drying agent powder to the neutron absorber powder is 4-12: 1-9: 11 to 35;
the skeleton granule plays the effect of supporting the skeleton, the drier powder with the neutron absorber powder is filled in the gap between the skeleton granule, plays similar lubricated effect.
2. The high radionuclide waste container according to claim 1, wherein the buffer layer has a thickness of 50 to 500 mm;
the particle size of the drying agent powder is 23-75 mu m, and the particle size of the neutron absorber powder is 1-100 mu m.
3. The high radionuclide waste container according to any of claims 1-2, characterized in that the skeletal particles are porous particles.
4. The high radionuclide waste container according to claim 3, wherein the skeletal particles are ceramsite and/or foam metal particles and the desiccant powder is a neutral desiccant powder.
5. The high radionuclide waste container according to claim 4, wherein the ceramsite is one, two or more selected from the group consisting of rare earth ceramsite, attapulgite ceramsite, kaolin ceramsite, montmorillonite ceramsite, vermiculite ceramsite, illite ceramsite and allophane ceramsite;
the foam metal particles are selected from one, two or more than three of foam aluminum particles, foam nickel particles, foam copper particles and foam metal alloy particles;
the neutral desiccant powder is one, two or more than three of anhydrous calcium chloride powder, molecular sieve powder, silica gel powder, attapulgite powder, calcium sulfate powder, aluminum oxide powder and sodium sulfate powder;
the neutron absorber powder is selected from one, two or more of lead powder, ferrosteel powder, silicon dioxide powder, borax, boron carbide powder, boron steel powder, amorphous carbon powder, carbon nano tubes, carbon nano cages and graphite powder.
6. The high radionuclide waste container according to claim 5, wherein the buffer layer is made of: 4 to 12 portions of kaolin ceramsite, 1 to 9 portions of attapulgite powder, 6 to 14 portions of lead powder, 4 to 12 portions of silicon dioxide powder and 1 to 9 portions of graphite.
7. The high radioactive nuclear waste container of claim 3, wherein the enclosure includes, in order from outside to inside, a waterproof enclosure, an inner liner, and the high radioactive spent nuclear fuel, the inner liner being located between the waterproof enclosure and the high radioactive spent nuclear fuel.
8. The high radioactive nuclear waste container of claim 7, wherein the high radioactive spent nuclear fuel is a solidified vitreous wrapped high radioactive spent nuclear fuel rod, the inner liner is a lead liner, and the water resistant housing is a stainless steel housing; the metal shell is made of copper-manganese alloy.
9. The high radionuclide waste container according to claim 7, characterized in that the periphery of the high radionuclide waste container is provided with a number of guide structures distributed centrosymmetrically, the extension direction of the guide structures being parallel to the axial direction of the high radionuclide waste container.
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| CN202010190468.7A CN111430057B (en) | 2020-03-18 | 2020-03-18 | High radioactive nuclear waste container |
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| CN202010190468.7A CN111430057B (en) | 2020-03-18 | 2020-03-18 | High radioactive nuclear waste container |
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| CN111430057B true CN111430057B (en) | 2021-06-08 |
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| CN113223742B (en) * | 2021-04-19 | 2022-09-23 | 中广核工程有限公司 | Radiation shielding and insulating device |
| CN114743706B (en) * | 2022-04-11 | 2024-01-30 | 江苏西顿科技有限公司 | Nuclear waste container |
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