CA1170845A - Container for long-term storage of radioactive waste - Google Patents
Container for long-term storage of radioactive wasteInfo
- Publication number
- CA1170845A CA1170845A CA000409706A CA409706A CA1170845A CA 1170845 A CA1170845 A CA 1170845A CA 000409706 A CA000409706 A CA 000409706A CA 409706 A CA409706 A CA 409706A CA 1170845 A CA1170845 A CA 1170845A
- Authority
- CA
- Canada
- Prior art keywords
- container
- long
- term storage
- protective layer
- plastic material
- 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.)
- Expired
Links
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
- 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
-
- 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
- G21F1/02—Selection of uniform shielding materials
- G21F1/10—Organic substances; Dispersions in organic carriers
Landscapes
- Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Dispersion Chemistry (AREA)
- Chemical & Material Sciences (AREA)
- Environmental & Geological Engineering (AREA)
- Laminated Bodies (AREA)
- Processing Of Solid Wastes (AREA)
- Details Of Rigid Or Semi-Rigid Containers (AREA)
- Wrappers (AREA)
- Packages (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
Abstract
ABSTRACT OF THE DISCLOSURE
For the long-term storage of radioactive waste, particularly burned-out fuel elements, containers are required which provide as high as possible protection against corrosion damage and leakage of fission products with mechanical damage.
For this purpose the basic body of the container is covered with a protective layer consisting of a readily adhesive plastic material, preferably polyurethane in which there is embedded a filler which is capable of swelling, capable of ion exchange and has adsorptive properties in the presence of water.
For the long-term storage of radioactive waste, particularly burned-out fuel elements, containers are required which provide as high as possible protection against corrosion damage and leakage of fission products with mechanical damage.
For this purpose the basic body of the container is covered with a protective layer consisting of a readily adhesive plastic material, preferably polyurethane in which there is embedded a filler which is capable of swelling, capable of ion exchange and has adsorptive properties in the presence of water.
Description
1 17~84S
The present invention relates to a container for long-term storage of radioactive waste, particularly burned-out fuel elements, in suitable geological formations, comprising a container body and a protective layer applied to the external surface thereof.
Irradiated burned-out fuel elements are processed after intermediate storage in a water tank either immediately or after further limited in~ermediate storage. The nuclear fuels and fertile materials are separated from the fission products and returned to the fuel cycle. The fission products are conditioned by means of conventional processes, usually using large quantities of valuable materials, as for example, lead and copper, and finally so stored in suitable geological formations that they can no longer be removed.
Furthermore, it has been proposed (Berichte des Kernforschungszentrum Karlsruhe KFK 2535 and 2650) that the irradiated fuel elements should not be processed within a reasonable period of time and that the fuels and fertile materials contained therein should be given up for the time ~eing and after an adequate decay time in storage depots intended for this purpose they shou:Ld be so put in final storage such that they can be removed again when required. The storage times can extend over several generations up to several thousand years while the danger potential of the stored radioactive material is very substantially reduced during this time corresponding to its composition, following the known physical laws.
Because of the indefinite storage time containers suitable for long-term storage and having an operating time which is a multiple of that of conventional -transport and storage containers must satisfy special requirements. The fact that the container depots must be difficult to access and that the possibilities of monitoring thus are limited is an I 1 7~8~5 additional difficulty.
Some very expensive concepts are known, for example, to store the irradiated fuels elements by means of containers of metal or concrete in salt, sand or in rock caverns.
Containers of alloyed and unalloyed steel, of copper and corundum have been proposed as the packing material.
The containers of steel are either not sufficiently resistant to corrosion or like those of copper too costly. Containers of corundum are fundamentally suitable but the experience required for their production is lacking. Furthermore, the fuel elements would have to be divided in order to pack them in corundum containers, which are small for reasons of their productionO This causes substantial expenditure. These con-tainers satisfy the conditions of long-term storage, such as tight enclosure at the occurring pressures and temperatures and corrosion due to brine, only to some extent or they must have very thick walls. Furthermore, they are not simultaneously suitable as transport containersso that the wastes must be reloaded from the transport container to the final storage container. This causes substantial expenditure.
Final storage containersfor burned fuel elements which consist of alloyed or unalloyed steel with galvanic protective layers selected according to the electrochemical series have also been proposed. These conventional externally applied protective layers often are sensitive to mechanical stresses. They can be partially destroyed and in case of disturbance the corrosion can spread from these damaged spots.
Therefore, the present invention provides a contain~r for long-term storage of radioactive waste, particularly burned-out fuel elements, in geological formations, comprising acontainer body and a protective layer applied to the external surface thereof. Said external protective layer is suitable ~ 1 7~ 5 for any container body, which should be as inexpensive as possible, has a resistance to corrosion as high as possible and against mechanical damage and also prevents fission products from leaking from the final storage container.
According to the present invention the protective layer consists of a readily adhesive plastic material, in which there is embedded a filler that is capable of swelling, capable of ion exchange and has adsorptive properties in the presence of water. Particularly layered silicates of the montmorillonite type have been found to be suitable as the filler. ~entonite is preferably used for this purpose while it has been found that polyurethane is particularly suitable as the plastic component. However, e.g., polytetrafluoro ethylene, polycarbonate, epoxide resins, phenol-formaldehyde resins or acrylate rubber can also be used as the plastic component.
For example, a polyurethane layer having a thickness of 1 to 3 cm is applied to the external surface of the closed final storage container,which contains burned-out fuel elements or even individual rods. The two-component system contains bentonite as the filler in one component.
After the two components are completely reacted on the surface of the final storaae container, said container has a readily adhesive and impervious coating, which contains bentonite in homogeneous distribution.
The coating has a surprisingly high mechanical resistance to pressure and shock and thus reliably prevents damage to the container body. At the same time this coating of polyurethane with the filler contained thereinis absolutely resistant to corrosion due to brine, as would be encountered in thecase of disturbance in the final storage formations provided in Germany.
~ ~ 7~845 The bentonite preferably contained in the polyurethane as the filler provides additional protection and forms a second barrier. In case of damage to the plastic layer, for example, by a crack, the filler is exposed. In the presence of water the filler swells to 4 to 7 times its volume and thus seals the crack.
The layered-silicate filler provides additional protection against leakage of fission products from a damaged final storage container. ~entonite has adsorptive and ion-exchanging properties. Fission products leaking from the final storage container would thus be bound to the bentonite by both adsorption and ion exchange and prevented from entering the biosphere.
The protective layer according to the present invention thus provides a multiple protection and substantially increases the safety of the final storage of burned-out fuel elements.
A preferred embodiment of the container according to the present invention is shown diagrammatically in the single Figure of the accompanying drawing.
Referring to the Figure a protective layer (2) consisting of a readily adhesive plastic material and a filler capable of swelling has been applied to the container body (1).
The present invention relates to a container for long-term storage of radioactive waste, particularly burned-out fuel elements, in suitable geological formations, comprising a container body and a protective layer applied to the external surface thereof.
Irradiated burned-out fuel elements are processed after intermediate storage in a water tank either immediately or after further limited in~ermediate storage. The nuclear fuels and fertile materials are separated from the fission products and returned to the fuel cycle. The fission products are conditioned by means of conventional processes, usually using large quantities of valuable materials, as for example, lead and copper, and finally so stored in suitable geological formations that they can no longer be removed.
Furthermore, it has been proposed (Berichte des Kernforschungszentrum Karlsruhe KFK 2535 and 2650) that the irradiated fuel elements should not be processed within a reasonable period of time and that the fuels and fertile materials contained therein should be given up for the time ~eing and after an adequate decay time in storage depots intended for this purpose they shou:Ld be so put in final storage such that they can be removed again when required. The storage times can extend over several generations up to several thousand years while the danger potential of the stored radioactive material is very substantially reduced during this time corresponding to its composition, following the known physical laws.
Because of the indefinite storage time containers suitable for long-term storage and having an operating time which is a multiple of that of conventional -transport and storage containers must satisfy special requirements. The fact that the container depots must be difficult to access and that the possibilities of monitoring thus are limited is an I 1 7~8~5 additional difficulty.
Some very expensive concepts are known, for example, to store the irradiated fuels elements by means of containers of metal or concrete in salt, sand or in rock caverns.
Containers of alloyed and unalloyed steel, of copper and corundum have been proposed as the packing material.
The containers of steel are either not sufficiently resistant to corrosion or like those of copper too costly. Containers of corundum are fundamentally suitable but the experience required for their production is lacking. Furthermore, the fuel elements would have to be divided in order to pack them in corundum containers, which are small for reasons of their productionO This causes substantial expenditure. These con-tainers satisfy the conditions of long-term storage, such as tight enclosure at the occurring pressures and temperatures and corrosion due to brine, only to some extent or they must have very thick walls. Furthermore, they are not simultaneously suitable as transport containersso that the wastes must be reloaded from the transport container to the final storage container. This causes substantial expenditure.
Final storage containersfor burned fuel elements which consist of alloyed or unalloyed steel with galvanic protective layers selected according to the electrochemical series have also been proposed. These conventional externally applied protective layers often are sensitive to mechanical stresses. They can be partially destroyed and in case of disturbance the corrosion can spread from these damaged spots.
Therefore, the present invention provides a contain~r for long-term storage of radioactive waste, particularly burned-out fuel elements, in geological formations, comprising acontainer body and a protective layer applied to the external surface thereof. Said external protective layer is suitable ~ 1 7~ 5 for any container body, which should be as inexpensive as possible, has a resistance to corrosion as high as possible and against mechanical damage and also prevents fission products from leaking from the final storage container.
According to the present invention the protective layer consists of a readily adhesive plastic material, in which there is embedded a filler that is capable of swelling, capable of ion exchange and has adsorptive properties in the presence of water. Particularly layered silicates of the montmorillonite type have been found to be suitable as the filler. ~entonite is preferably used for this purpose while it has been found that polyurethane is particularly suitable as the plastic component. However, e.g., polytetrafluoro ethylene, polycarbonate, epoxide resins, phenol-formaldehyde resins or acrylate rubber can also be used as the plastic component.
For example, a polyurethane layer having a thickness of 1 to 3 cm is applied to the external surface of the closed final storage container,which contains burned-out fuel elements or even individual rods. The two-component system contains bentonite as the filler in one component.
After the two components are completely reacted on the surface of the final storaae container, said container has a readily adhesive and impervious coating, which contains bentonite in homogeneous distribution.
The coating has a surprisingly high mechanical resistance to pressure and shock and thus reliably prevents damage to the container body. At the same time this coating of polyurethane with the filler contained thereinis absolutely resistant to corrosion due to brine, as would be encountered in thecase of disturbance in the final storage formations provided in Germany.
~ ~ 7~845 The bentonite preferably contained in the polyurethane as the filler provides additional protection and forms a second barrier. In case of damage to the plastic layer, for example, by a crack, the filler is exposed. In the presence of water the filler swells to 4 to 7 times its volume and thus seals the crack.
The layered-silicate filler provides additional protection against leakage of fission products from a damaged final storage container. ~entonite has adsorptive and ion-exchanging properties. Fission products leaking from the final storage container would thus be bound to the bentonite by both adsorption and ion exchange and prevented from entering the biosphere.
The protective layer according to the present invention thus provides a multiple protection and substantially increases the safety of the final storage of burned-out fuel elements.
A preferred embodiment of the container according to the present invention is shown diagrammatically in the single Figure of the accompanying drawing.
Referring to the Figure a protective layer (2) consisting of a readily adhesive plastic material and a filler capable of swelling has been applied to the container body (1).
Claims (4)
PROPERTY OR PRIVILEGE IS CLAIMED ARE DEFINED AS FOLLOWS:
1. A container for long-term storage of radioactive wastes in suitable geological formations, comprising a container body and a protective layer coated on the external surface of said body, said protective layer consisting of a readily ad-hesive plastic material, having a filler which is capable of swelling, capable of ion-exchange and has adsorptive properties in the presence of water embedded therein.
2. A container according to claim 1, in which a layered silicate of the montmorillonite type is embedded in the plastic material.
3. A container according to claim 2, in which bento-nite is used as the layered silicate.
4. A container according to claim 1, 2 or 3, in which polyurethane is used as the plastic material.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE3132704A DE3132704C2 (en) | 1981-08-19 | 1981-08-19 | Container for long-term storage of radioactive waste |
| DEP3132704.4 | 1981-08-19 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1170845A true CA1170845A (en) | 1984-07-17 |
Family
ID=6139600
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA000409706A Expired CA1170845A (en) | 1981-08-19 | 1982-08-18 | Container for long-term storage of radioactive waste |
Country Status (6)
| Country | Link |
|---|---|
| EP (1) | EP0072429B1 (en) |
| JP (1) | JPS5840000A (en) |
| BR (1) | BR8204782A (en) |
| CA (1) | CA1170845A (en) |
| DE (2) | DE3132704C2 (en) |
| ES (1) | ES280865Y (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR3030864A1 (en) * | 2014-12-22 | 2016-06-24 | Tn Int | USE OF AN ELASTOMERIC COMPOSITION CHARGED FOR THE MANUFACTURE OF A JOINT FOR PACKAGING OF RADIOACTIVE MATERIAL, JOINT AND PACKAGING THEREFOR |
Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| HU191255B (en) * | 1984-03-05 | 1987-01-28 | Eroemue- Es Halozattervezoe Vallalat,Hu | Container for transporting radioactive matters |
| JPS6190995U (en) * | 1984-11-19 | 1986-06-13 | ||
| DE3447278A1 (en) * | 1984-12-22 | 1986-06-26 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | LONG-TERM CORROSION PROTECTION COVER FOR TIGHTLY CLOSED CONTAINERS WITH HIGH RADIOACTIVE CONTENT |
| DE3520450A1 (en) * | 1985-06-07 | 1986-12-11 | Gattys Technique S.A., Freiburg/Fribourg | RADIATION PROTECTION CONTAINER FOR TRANSPORTING AND STORING RADIOACTIVE MATERIALS AND METHOD FOR THE PRODUCTION THEREOF |
| GB2176925A (en) * | 1985-06-19 | 1987-01-07 | Us Energy | Waste disposal package |
| GB2217631A (en) * | 1988-03-31 | 1989-11-01 | Westinghouse Electric Corp | Method for attenuating gas diffusion through a structure |
| DE3927815C2 (en) * | 1989-08-23 | 1999-12-23 | Sipra Patent Beteiligung | Plush or pile knitwear and circular knitting machine for their manufacture |
| EP1124234A1 (en) * | 2000-02-11 | 2001-08-16 | Jesse Yang | Method for sealing and packing toxic wastes |
| DE10329170A1 (en) * | 2003-06-27 | 2005-01-13 | Polybern Gmbh | Improved process for the inclusion of hazardous waste |
| DE102011051991A1 (en) * | 2011-07-20 | 2013-01-24 | Siempelkamp Nukleartechnik Gmbh | Method for upgrading waste container for transport and storage of radioactive waste, particularly for disposal, involves providing waste container which is already loaded with radioactive waste and subsequently closed by cover |
| DE102011085480A1 (en) | 2011-10-28 | 2013-05-02 | Volkmar Gräf | CONTAINER SYSTEM FOR THE END STORAGE OF RADIOACTIVE WASTE AND / OR POISONOIL |
| DE102014002390B3 (en) * | 2014-02-24 | 2015-05-13 | Cura Ingenieurgesellschaft Mbh | Container for storage of radioactive waste |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1350579A (en) * | 1963-03-18 | 1964-01-24 | Sorbent substance and its manufacturing process | |
| DE2065863B2 (en) * | 1969-08-13 | 1981-07-16 | Transnucléaire, Société pour les Transports de l'Industrie Nucléaire, Paris | Containers for the storage and transport of radioactive materials |
| FR2199479A1 (en) * | 1972-09-15 | 1974-04-12 | Peabody Gci | Absorbent/filter for gas or liquid - with powder absorber sandwiched between fibrous or open-cellular sheets, esp. used as continuous band |
| GB1443545A (en) * | 1972-12-30 | 1976-07-21 | Toyo Jozo Kk | Molecular sieving particleland preparation thereof |
| US3935467A (en) * | 1973-11-09 | 1976-01-27 | Nuclear Engineering Co., Inc. | Repository for fissile materials |
| FR2473213B1 (en) * | 1980-01-07 | 1986-03-21 | Ecopo | LONG-TERM CONTAINMENT DEVICE FOR RADIOACTIVE OR TOXIC WASTE AND ITS MANUFACTURING METHOD |
-
1981
- 1981-08-19 DE DE3132704A patent/DE3132704C2/en not_active Expired
-
1982
- 1982-06-30 ES ES1982280865U patent/ES280865Y/en not_active Expired
- 1982-07-10 DE DE8282106184T patent/DE3263122D1/en not_active Expired
- 1982-07-10 EP EP82106184A patent/EP0072429B1/en not_active Expired
- 1982-08-12 JP JP57139260A patent/JPS5840000A/en active Pending
- 1982-08-16 BR BR8204782A patent/BR8204782A/en unknown
- 1982-08-18 CA CA000409706A patent/CA1170845A/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR3030864A1 (en) * | 2014-12-22 | 2016-06-24 | Tn Int | USE OF AN ELASTOMERIC COMPOSITION CHARGED FOR THE MANUFACTURE OF A JOINT FOR PACKAGING OF RADIOACTIVE MATERIAL, JOINT AND PACKAGING THEREFOR |
Also Published As
| Publication number | Publication date |
|---|---|
| ES280865U (en) | 1985-02-01 |
| DE3132704C2 (en) | 1985-12-19 |
| EP0072429B1 (en) | 1985-04-17 |
| DE3263122D1 (en) | 1985-05-23 |
| ES280865Y (en) | 1985-08-01 |
| EP0072429A1 (en) | 1983-02-23 |
| BR8204782A (en) | 1983-08-02 |
| JPS5840000A (en) | 1983-03-08 |
| DE3132704A1 (en) | 1983-03-10 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| MKEC | Expiry (correction) | ||
| MKEX | Expiry |