EP0072429B1 - Container for long-term storage of radioactive waste - Google Patents
Container for long-term storage of radioactive waste Download PDFInfo
- Publication number
- EP0072429B1 EP0072429B1 EP82106184A EP82106184A EP0072429B1 EP 0072429 B1 EP0072429 B1 EP 0072429B1 EP 82106184 A EP82106184 A EP 82106184A EP 82106184 A EP82106184 A EP 82106184A EP 0072429 B1 EP0072429 B1 EP 0072429B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- container
- protective layer
- long
- term storage
- radioactive waste
- 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
- 238000003860 storage Methods 0.000 title claims description 17
- 230000007774 longterm Effects 0.000 title claims description 6
- 239000002901 radioactive waste Substances 0.000 title claims description 5
- 239000011241 protective layer Substances 0.000 claims description 12
- 239000000945 filler Substances 0.000 claims description 9
- 229920002635 polyurethane Polymers 0.000 claims description 8
- 239000004814 polyurethane Substances 0.000 claims description 8
- 229910000278 bentonite Inorganic materials 0.000 claims description 7
- 239000000440 bentonite Substances 0.000 claims description 7
- SVPXDRXYRYOSEX-UHFFFAOYSA-N bentoquatam Chemical compound O.O=[Si]=O.O=[Al]O[Al]=O SVPXDRXYRYOSEX-UHFFFAOYSA-N 0.000 claims description 7
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 7
- 229920003023 plastic Polymers 0.000 claims description 6
- 239000004033 plastic Substances 0.000 claims description 6
- 230000015572 biosynthetic process Effects 0.000 claims description 5
- 238000005755 formation reaction Methods 0.000 claims description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 230000000274 adsorptive effect Effects 0.000 claims description 3
- 239000003822 epoxy resin Substances 0.000 claims description 3
- LNEPOXFFQSENCJ-UHFFFAOYSA-N haloperidol Chemical compound C1CC(O)(C=2C=CC(Cl)=CC=2)CCN1CCCC(=O)C1=CC=C(F)C=C1 LNEPOXFFQSENCJ-UHFFFAOYSA-N 0.000 claims description 3
- 229920001568 phenolic resin Polymers 0.000 claims description 3
- 229920000515 polycarbonate Polymers 0.000 claims description 3
- 239000004417 polycarbonate Substances 0.000 claims description 3
- 229920000647 polyepoxide Polymers 0.000 claims description 3
- -1 polytetrafluoroethylene Polymers 0.000 claims description 3
- 239000004810 polytetrafluoroethylene Substances 0.000 claims description 3
- 229920001343 polytetrafluoroethylene Polymers 0.000 claims description 3
- NIXOWILDQLNWCW-UHFFFAOYSA-M Acrylate Chemical compound [O-]C(=O)C=C NIXOWILDQLNWCW-UHFFFAOYSA-M 0.000 claims description 2
- BPQQTUXANYXVAA-UHFFFAOYSA-N Orthosilicate Chemical group [O-][Si]([O-])([O-])[O-] BPQQTUXANYXVAA-UHFFFAOYSA-N 0.000 claims description 2
- GUJOJGAPFQRJSV-UHFFFAOYSA-N dialuminum;dioxosilane;oxygen(2-);hydrate Chemical compound O.[O-2].[O-2].[O-2].[Al+3].[Al+3].O=[Si]=O.O=[Si]=O.O=[Si]=O.O=[Si]=O GUJOJGAPFQRJSV-UHFFFAOYSA-N 0.000 claims description 2
- 229920001971 elastomer Polymers 0.000 claims description 2
- 239000000463 material Substances 0.000 claims description 2
- 229910052901 montmorillonite Inorganic materials 0.000 claims description 2
- 150000004760 silicates Chemical class 0.000 claims description 2
- 230000007797 corrosion Effects 0.000 description 7
- 238000005260 corrosion Methods 0.000 description 7
- 239000000446 fuel Substances 0.000 description 7
- 230000004992 fission Effects 0.000 description 4
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 3
- 229910000831 Steel Inorganic materials 0.000 description 3
- 229910052802 copper Inorganic materials 0.000 description 3
- 239000010949 copper Substances 0.000 description 3
- 229910052593 corundum Inorganic materials 0.000 description 3
- 239000010431 corundum Substances 0.000 description 3
- 238000005342 ion exchange Methods 0.000 description 3
- 239000010959 steel Substances 0.000 description 3
- 229920005830 Polyurethane Foam Polymers 0.000 description 2
- 239000012267 brine Substances 0.000 description 2
- 239000011248 coating agent Substances 0.000 description 2
- 238000000576 coating method Methods 0.000 description 2
- 239000010410 layer Substances 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000004806 packaging method and process Methods 0.000 description 2
- 239000011496 polyurethane foam Substances 0.000 description 2
- HPALAKNZSZLMCH-UHFFFAOYSA-M sodium;chloride;hydrate Chemical compound O.[Na+].[Cl-] HPALAKNZSZLMCH-UHFFFAOYSA-M 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 229920000800 acrylic rubber Polymers 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 244000144987 brood Species 0.000 description 1
- 238000003776 cleavage reaction Methods 0.000 description 1
- 230000001143 conditioned effect Effects 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 230000002401 inhibitory effect Effects 0.000 description 1
- 230000014759 maintenance of location Effects 0.000 description 1
- 230000007257 malfunction Effects 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000005293 physical law Methods 0.000 description 1
- 229920000058 polyacrylate Polymers 0.000 description 1
- 239000011527 polyurethane coating Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000011435 rock Substances 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 230000007017 scission Effects 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
Images
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
Definitions
- the invention relates to a container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of a container body and a protective layer applied to the outer surface, the protective layer being made of a plastic from the group consisting of polyurethane, polytetrafluoroethylene, polycarbonate, Epoxy resins, phenol formaldehyde resins and acrylate rubber.
- Irradiated, spent fuel elements are processed either immediately after temporary storage in the water basin or after a limited further interim storage.
- the nuclear fuels and broods are separated from the fission products and returned to the fuel cycle.
- the cleavage products are by known methods, usually using large amounts of valuable materials, such as. B. lead and copper, conditioned and in suitable geological formations practically no longer removable.
- Very complex concepts are known in some cases for storing the irradiated fuel elements in metal, concrete in salt, sand or in rock caverns.
- Containers made of alloyed and unexposed steel, copper and corundum are proposed as packaging for radioactive materials and irradiated fuel elements.
- the steel containers are either not sufficiently corrosion-resistant or, like copper, are very expensive.
- Corundum containers are generally suitable, but the experience required for their manufacture is lacking.
- the fuel elements for packaging would have to be disassembled into small corundum containers for manufacturing reasons, which is associated with considerable effort.
- Such containers only partially meet the conditions of long-term storage, such as tight containment at the pressures and temperatures that occur, and corrosion against brine, or they must be made very thick-walled.
- they are usually not suitable as a transport container at the same time, so that the waste must be reloaded from the transport container into the final storage container at considerable expense.
- Repository containers for spent fuel elements have also been proposed, which consist of alloyed and unalloyed steels with galvanic protective layers selected according to the electrochemical voltage series. These known externally applied protective layers are often sensitive to mechanical loads, they can be partially destroyed and, in the event of a malfunction, corrosion can proceed from these damaged areas.
- a storage concept for radioactive waste is known from US-A-3935467, in which a large number of smaller containers containing the waste are accommodated in a larger, corrosion-resistant container. The spaces between these containers are filled with a shock-absorbing polyurethane foam. This polyurethane foam cannot perform corrosion-inhibiting and fission product retention functions.
- the invention was therefore based on the object of providing a container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of a container base body and a protective layer applied to the outer surface, the outer protective layer being made of a plastic from the Group of polyurethanes, polytetrafluoroethylene, polycarbonate, epoxy resins, phenol formaldehyde resins and acrylic rubber and is suitable for any cheap basic container body, has the highest possible protection against corrosion and offers protection against mechanical damage, and prevents leakage products from escaping from the repository.
- the object is achieved in that a filler which has swellable, ion-exchange and adsorptive properties in the presence of water is incorporated in the protective layer.
- Layered silicates of the montmorillonite type have proven particularly useful as fillers. Bentonite is preferably used for this, while polyurethane has proven to be particularly suitable as the plastic component.
- the two-component system of the polyurethane contains bentonite as a filler in one component.
- the two components of the polyurethane system After the two components of the polyurethane system have reacted on the surface of the repository, the latter has a well-adhering and dense coating that contains bentonite in a homogeneous distribution.
- the coating has a surprisingly high mechanical resistance to pressure and shock and thus reliably prevents damage to the body of the container.
- this polyurethane coating with the filler it contains against brine as it would be present in the repository formations intended in Germany in the event of a fault, is absolutely corrosion-resistant.
- the bentonite preferably contained in the polyurethane as a filler offers additional protection and forms a second barrier. If the plastic layer is damaged, e.g. B. a crack, the filler is exposed. This swells in the presence of water to 4 to 7 times its volume and thus seals the crack that has formed.
- the layered silicate filling offers protection against the discharge of fission products from a damaged repository.
- Bentonite has both adsorptive and ion exchange properties. Fission products emerging from the final storage container would thus be bound to the bentonite both by adsorption and by ion exchange and be prevented from entering the biosphere.
- the protective layer according to the invention offers multiple protection and significantly increases the safety of the final storage of spent fuel elements.
- the figure shows schematically an exemplary embodiment of the container according to the invention.
- a protective layer (2) consisting of a well-adhering plastic and a swellable filler is applied to the container body (1).
Landscapes
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Physics & Mathematics (AREA)
- Environmental & Geological Engineering (AREA)
- Dispersion Chemistry (AREA)
- Chemical & Material Sciences (AREA)
- Laminated Bodies (AREA)
- Processing Of Solid Wastes (AREA)
- Packages (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
- Details Of Rigid Or Semi-Rigid Containers (AREA)
- Wrappers (AREA)
Description
Gegenstand der Erfindung ist ein Behälter zur Langzeitlagerung von radioaktiven Abfällen, insbesondere von abgebrannten Brennelementen, in geeigneten geologischen Formationen, bestehend aus einem Behältergrundkörper und einer auf der äußeren Oberfläche aufgebrachten Schutzschicht, wobei die Schutzschicht aus einem Kunststoff aus der Gruppe Polyurethan, Polytetrafluoräthylen, Polycarbonat, Epoxyharze, Phenolformaldehydharze und Acrylatkautschuk besteht.The invention relates to a container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of a container body and a protective layer applied to the outer surface, the protective layer being made of a plastic from the group consisting of polyurethane, polytetrafluoroethylene, polycarbonate, Epoxy resins, phenol formaldehyde resins and acrylate rubber.
Bestrahlte, abgebrannte Brennelemente werden nach einer vorübergehenden Aufbewahrung im Wasserbecken entweder sofort oder nach einer begrenzten weiteren Zwischenlagerung aufgearbeitet. Dabei werden die nuklearen Brenn-und Brutstoffe von den Spaltprodukten abgetrennt und wieder dem Brennstoffkreislauf zugeführt. Die Spaltprodukte werden nach bekannten Verfahren, meist unter Verwendung großer Mengen Wertstoffe, wie z. B. Blei und Kupfer, konditioniert und in geeigneten geologischen Formationen praktisch nicht mehr entnehmbar endgelagert.Irradiated, spent fuel elements are processed either immediately after temporary storage in the water basin or after a limited further interim storage. The nuclear fuels and broods are separated from the fission products and returned to the fuel cycle. The cleavage products are by known methods, usually using large amounts of valuable materials, such as. B. lead and copper, conditioned and in suitable geological formations practically no longer removable.
Darüber hinaus wird vorgeschlagen (Berichte des Kernforschungszentrums Karlsruhe KFK 2535 und 2650), die bestrahlten Brennelemente in absehbarer Zeit nicht aufzuarbeiten, auf die in ihnen vorhandenen Brenn- Brutstoffe zunächst zu verzichten und die Brennelementenach einer angemessenen Abklingzeit in dafür vorgesehene Lagern- gegebenenfalls wieder entnehmbar endzulagern. Die Lagerzeiten können mehrere Generationen bis zu mehreren tausend Jahren betragen, wobei sich das Gefährdungspotential des radioaktiven Inventars in dieser Zeit, den bekannten physikalischen Gesetzen folgend, entsprechend seiner Zusammensetzung außerordentlich stark verringert.In addition, it is proposed (reports from the Kernforschungszentrum Karlsruhe KFK 2535 and 2650) not to reprocess the irradiated fuel elements in the foreseeable future, to initially dispense with the fuel they contain and, after a reasonable decay time, to store the fuel elements in the storage facilities provided for this purpose, which can then be removed if necessary . The storage times can be several generations up to several thousand years, whereby the risk potential of the radioactive inventory during this time, following the known physical laws, is reduced extraordinarily according to its composition.
Wegen der unbestimmten Lagerdauer werden an derartige, für die Langzeitlagerung geeignete Behälter, die gegenüber bekannten Transport-und Lagerbehälter eine mehrfache Betriebszeit aufweisen müssen, besondere Anforderungen gestellt. Erschwerend kommt hinzu, daß die Behälterlager schwer zugänglich sein müssen und folglich den Überwachungsmöglichkeiten Grenzen gesetzt sind.Because of the indefinite storage period, special requirements are placed on such containers which are suitable for long-term storage and which have to have a multiple operating time compared to known transport and storage containers. To make matters worse, the container storage must be difficult to access and the monitoring options are therefore limited.
Es sind teilweise sehr aufwendige Konzepte bekannt, die bestrahlten Brennelemente mittels Behältern aus Metall oder Beton in Salz, Sand oder in Fels-Kavernen zu lagern.Very complex concepts are known in some cases for storing the irradiated fuel elements in metal, concrete in salt, sand or in rock caverns.
Als Verpackung für radioaktive Stoffe und bestrahlte Brennelemente werden Behälter aus legierten und unlegerten Stählen, aus Kupfer sowie aus Korund vorgeschlagen. Die Behälter aus Stahl sind entweder nicht genügend korrosionsbeständig oder wie solche aus Kupfer sehr teuer. Behälter aus Korund sind grundsätzlich geeignet, jedoch fehlen die für die Herstellung notwendigen Erfahrungen. Darüber hinaus müßten die Brennelemente zur Verpackung in die aus herstellungsbedingten Gründen kleinen Korundbehälter zerlegt werden, was mit einem erheblichen Aufwand verbunden ist. Solche Behälter erfüllen die Bedingungen der Langzeitlagerung, wie dichter Einschluß bei den auftretenden Drucken und Temperaturen, sowie Korrosion gegen Salzlaugen, nur zum Teil, oder sie müssen sehr dickwandig ausgebildet werden. Außerdem eignen sie sich meist nicht gleichzeitig auch als Transportbehälter, sodaß unter erheblichem Aufwand eine Umladung der Abfälle vom Transportbehälter in den Endlagerbehälter erfolgen muß.Containers made of alloyed and unexposed steel, copper and corundum are proposed as packaging for radioactive materials and irradiated fuel elements. The steel containers are either not sufficiently corrosion-resistant or, like copper, are very expensive. Corundum containers are generally suitable, but the experience required for their manufacture is lacking. In addition, the fuel elements for packaging would have to be disassembled into small corundum containers for manufacturing reasons, which is associated with considerable effort. Such containers only partially meet the conditions of long-term storage, such as tight containment at the pressures and temperatures that occur, and corrosion against brine, or they must be made very thick-walled. In addition, they are usually not suitable as a transport container at the same time, so that the waste must be reloaded from the transport container into the final storage container at considerable expense.
Es sind auch Endlagerbehälter für abgebrannte Brennelemente vorgeschlagen worden, die aus legierten und unlegierten Stählen mit nach der elektrochemischen Spannungsreihe ausgewählten galvanischen Schutzschichten bestehen. Diese bekannten außen aufgebrachte Schutzschichten sind vielfach gegen mechanische Belastungen empfindlich, sie können teilweise zerstört werden und im Störfall kann von diesen beschädigten Stellen ausgehend die Korrosion ihren Fortschritt nehmen.Repository containers for spent fuel elements have also been proposed, which consist of alloyed and unalloyed steels with galvanic protective layers selected according to the electrochemical voltage series. These known externally applied protective layers are often sensitive to mechanical loads, they can be partially destroyed and, in the event of a malfunction, corrosion can proceed from these damaged areas.
Aus der US-A-3935467 ist ein Lagerkonzept für radioaktive Abfälle bekannt, bei dem in einem größeren, korrosionsresistenten Behälter eine Vielzahl von kleineren, den Abfall enthaltenen Behältern untergebracht sind. Die Zwischenräume zwischen diesen Behältern sind mit einem stoßdämpfenden Polyurethanschaum ausgefüllt. Korrosionshemmende und Spaltprodukt zurückhaltende Funktionen kann dieser Polyurethanschaum nicht übernehmen.A storage concept for radioactive waste is known from US-A-3935467, in which a large number of smaller containers containing the waste are accommodated in a larger, corrosion-resistant container. The spaces between these containers are filled with a shock-absorbing polyurethane foam. This polyurethane foam cannot perform corrosion-inhibiting and fission product retention functions.
Der Erfindung lag deshalb die Aufgabe zugrunde, einen Behälter zur Langzeitlagerung von radioaktiven Abfällen, insbesondere von abgebrannten Brennelementen, in geeigneten geologischen Formationen zu schaffen, bestehend aus einem Behältergrundkörper und einer auf der äußeren Oberfläche aufgebrachten Schutzschicht, wobei die äußere Schutzschicht aus einem Kunststoff aus der Gruppe der Polyurethane, Polytetrafluoräthylen, Polycarbonat, Epoxyharze, Phenolformaldehydharze und Acrylkautschuk besteht und für beliebige, möglichst billige Behältergrundkörper geeignet ist, möglichst hohen Korrosionsschutz aufweist und Schutz gegen mechanische Beschädigungen bietet, sowie das Austreten von Spaltprodukten aus dem Endlagerbehälter verhindert.The invention was therefore based on the object of providing a container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of a container base body and a protective layer applied to the outer surface, the outer protective layer being made of a plastic from the Group of polyurethanes, polytetrafluoroethylene, polycarbonate, epoxy resins, phenol formaldehyde resins and acrylic rubber and is suitable for any cheap basic container body, has the highest possible protection against corrosion and offers protection against mechanical damage, and prevents leakage products from escaping from the repository.
Die Aufgabe wird erfindungsgemäß dadurch gelöst, daß in die Schutzschicht ein in Gegenwart von Wasser quellfähiger, ionenaustauschfähiger und adsorptive Eigenschaften aufweisender Füllstoff eingelagert ist. Als Füllstoff haben sich besonders Schichtsilikate vom Montmorillonittyp bewährt. Vorzugsweise verwendet man hierfür Bentonit, während als Kunststoffkomponente Polyurethan sich als besonders geeignet erwiesen hat.The object is achieved in that a filler which has swellable, ion-exchange and adsorptive properties in the presence of water is incorporated in the protective layer. Layered silicates of the montmorillonite type have proven particularly useful as fillers. Bentonite is preferably used for this, while polyurethane has proven to be particularly suitable as the plastic component.
Auf die Außenseite des verschlossenen Endlagerbehälters, der abgebrannte Brennelemente oder auch Einzelstäbe enthält, wird beispielsweise eine 1-3 cm dicke Schicht aus Polyurethan aufgetragen, wobei das Zweikomponentensystem des Polyurethan in einer Komponente Bentonit als Füllstoff enthält.On the outside of the closed repository, which contains spent fuel or individual rods, for example se a 1-3 cm thick layer of polyurethane applied, the two-component system of the polyurethane contains bentonite as a filler in one component.
Nachdem die beiden Komponenten des Polyurethansystems auf der Oberfläche des Endlagerbehälters ausreagiert haben, weist dieser eine gut haftende und dichte Beschichtung, die Bentonit in homogener Verteilung enthält, auf. Die Beschichtung weist eine überraschend hohe mechanische Beständigkeit gegen Druck und Stoß auf und verhindert so sicher eine Beschädigung des Behältergrundkörpers. Gleichzeitig ist diese Beschichtung aus Polyurethan mit dem in ihm enthaltenen Füllstoff gegen Salzlauge, so wie sie im Störanfall in den in Deutschland vorgesehenen Endlagerformationen vorliegen würde, absolut korrosionsbeständig.After the two components of the polyurethane system have reacted on the surface of the repository, the latter has a well-adhering and dense coating that contains bentonite in a homogeneous distribution. The coating has a surprisingly high mechanical resistance to pressure and shock and thus reliably prevents damage to the body of the container. At the same time, this polyurethane coating with the filler it contains against brine, as it would be present in the repository formations intended in Germany in the event of a fault, is absolutely corrosion-resistant.
Der in dem Polyurethan als Füllstoff vorzugsweise enthaltene Bentonit bietet einen zusätzlichen Schutz und bildet eine zweite Barriere. Tritt eine Beschädigung der Kunststoffschicht, z. B. ein Riß auf, so wird der Füllstoff freigelegt. Dieser quillt in Gegenwart von Wasser auf das 4- bis 7fache seines Volumens und dichtet so den entstandenen Riß wieder ab.The bentonite preferably contained in the polyurethane as a filler offers additional protection and forms a second barrier. If the plastic layer is damaged, e.g. B. a crack, the filler is exposed. This swells in the presence of water to 4 to 7 times its volume and thus seals the crack that has formed.
Zusätzlich bietet die Schichtsilikatfüllung Schutz vor dem Austreten von Spaltprodukten aus einem beschädigten Endlagerbehälter. Bentonit weist sowohl adsorptive als- auch ionenaustauschende Eigenschaften auf. Aus dem Endlagerbehälter austretende Spaltprodukte würden also sowohl durch Adsorption als auch durch Ionenaustausch an den Bentonit gebunden und vom Eintritt in die Biosphäre zurückgehalten werden.In addition, the layered silicate filling offers protection against the discharge of fission products from a damaged repository. Bentonite has both adsorptive and ion exchange properties. Fission products emerging from the final storage container would thus be bound to the bentonite both by adsorption and by ion exchange and be prevented from entering the biosphere.
Die erfindungsgemäße Schutzschicht bietet auf diese Weise einen Mehrfachschutz und erhöht die Sicherheit der Endlagerung von abgebrannten Brennelementen wesentlich.In this way, the protective layer according to the invention offers multiple protection and significantly increases the safety of the final storage of spent fuel elements.
Die Abbildung zeigt schematisch eine beispielhafte Ausführungsform des erfindungsgemäßen Behälters. Auf dem Behältergrundkörper (1) ist eine Schutzschicht (2) aufgebracht, bestehend aus einem gut haftenden Kunststoff und einem quellfähigen Füllstoff.The figure shows schematically an exemplary embodiment of the container according to the invention. A protective layer (2) consisting of a well-adhering plastic and a swellable filler is applied to the container body (1).
Claims (3)
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 |
| DE3132704 | 1981-08-19 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| EP0072429A1 EP0072429A1 (en) | 1983-02-23 |
| EP0072429B1 true EP0072429B1 (en) | 1985-04-17 |
Family
ID=6139600
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP82106184A Expired EP0072429B1 (en) | 1981-08-19 | 1982-07-10 | 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) |
Families Citing this family (15)
| 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 |
| RU2152648C1 (en) * | 1998-08-25 | 2000-07-10 | Открытое акционерное общество "Сосна" | Container for long-time storage of harmful wastes |
| 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 |
| RU2430435C1 (en) * | 2009-12-24 | 2011-09-27 | Валентин Александрович Жабрев | Long-term storage container for hazardous wastes |
| 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 |
| FR3030864B1 (en) * | 2014-12-22 | 2020-04-24 | Tn International | USE OF A LOADED ELASTOMERIC COMPOSITION FOR THE MANUFACTURE OF A JOINT FOR PACKAGING OF RADIOACTIVE MATERIAL, JOINT AND PACKAGING THEREOF |
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 |
| US3951859A (en) * | 1972-12-30 | 1976-04-20 | Toyo Jozo Co., Ltd. | Molecular sieving particle and 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
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5840000A (en) | 1983-03-08 |
| EP0072429A1 (en) | 1983-02-23 |
| DE3263122D1 (en) | 1985-05-23 |
| ES280865Y (en) | 1985-08-01 |
| DE3132704A1 (en) | 1983-03-10 |
| DE3132704C2 (en) | 1985-12-19 |
| BR8204782A (en) | 1983-08-02 |
| CA1170845A (en) | 1984-07-17 |
| ES280865U (en) | 1985-02-01 |
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