EP0072429A1 - Container for long-term storage of radioactive waste - Google Patents

Container for long-term storage of radioactive waste Download PDF

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Publication number
EP0072429A1
EP0072429A1 EP82106184A EP82106184A EP0072429A1 EP 0072429 A1 EP0072429 A1 EP 0072429A1 EP 82106184 A EP82106184 A EP 82106184A EP 82106184 A EP82106184 A EP 82106184A EP 0072429 A1 EP0072429 A1 EP 0072429A1
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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.)
Granted
Application number
EP82106184A
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German (de)
French (fr)
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EP0072429B1 (en
Inventor
Jürgen Dr. Dipl.-Chem. Hofmann
Hans Dipl.-Chem. Pirk
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Nukem GmbH
Original Assignee
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Nukem GmbH
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Publication date
Application filed by Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH, Nukem GmbH filed Critical Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Publication of EP0072429A1 publication Critical patent/EP0072429A1/en
Application granted granted Critical
Publication of EP0072429B1 publication Critical patent/EP0072429B1/en
Expired legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • 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 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.
  • spent fuel elements After being temporarily stored in the water basin, irradiated, spent fuel elements are processed either immediately or after a limited period of intermediate storage, during which the nuclear fuels and broods are separated from the fission products and returned to the fuel cycle.
  • the fission products are conditioned by known methods, usually using large amounts of valuable materials, such as lead and copper, and in practical geological formations they are virtually no longer removable.
  • Containers made of alloyed and unalloyed steel, copper and corundum are proposed as packaging for radioactive materials and irradiated fuel elements.
  • the steel containers are not either sufficiently corrosion-resistant or, like copper, 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 sealing 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 has to 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 grater. 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.
  • the invention was therefore based on the object of creating 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 container protective layer applied to the outer surface, the outer protective layer being suitable for any base body that is as cheap as possible, having the highest possible corrosion protection and offering protection against mechanical damage, and preventing fission products from escaping from the repository.
  • the protective layer consists of a well-adhering plastic in which a filler which has swellable, ion-exchangeable and adsorptive properties in the presence of water is incorporated.
  • 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.
  • polytetrafluoroethylene, polycarbonate, epoxy resins, phenol formaldehyde resins or acrylate rubber can also be used as the plastic component.
  • a 1-3 cm thick layer of polyurethane for example, is applied to the outside of the closed final storage container, which contains spent fuel elements or individual rods, the two-component system of the polyurethane containing 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 tight coating which 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 exist in the repository formations provided for 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. a crack, the filler is exposed. This swells in the presence of water to 4-7 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 thus 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).

Abstract

1. Container for the long-term storage of radio-active waste, more particularly of spent fuel elements, in suitage geological formations, consisting of a basic container body and a protective layer applied to the outer surface, the protective layer (2) consisting of a plastics material from the group of polyurethanes, polytetrafluoroethylene, polycarbonate, epoxy resins, phenol for maldehyde resins and acrylate rubber, characterised in that an adsorptive filler which is swellable in the presence of water and is ionexchangeable is incorporated into the protective layer (2).

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.The invention relates to a container for 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.

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 zum Beispiel Blei und Kupfer, konditioniert und in geeigneten geologischen Formationen praktisch nicht mehr entnehmbar endgelagert.After being temporarily stored in the water basin, irradiated, spent fuel elements are processed either immediately or after a limited period of intermediate storage, during which the nuclear fuels and broods are separated from the fission products and returned to the fuel cycle. The fission products are conditioned by known methods, usually using large amounts of valuable materials, such as lead and copper, and in practical geological formations they are virtually no longer removable.

Darüberhinaus wird überlegt (Berichte des Kernforschungszentrums Karlsruhe KFK 2535 und 2650), die bestrahlten Brennelemente in absehbarer Zeit nicht aufzuarbeiten, auf die in ihnen vorhandenen Brenn- und Brutstoffe zunächst zu verzichten und die Brennelemente- nach einer angemessenen Abklinzeit 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 being considered (reports from the Nuclear Research Center Karlsruhe KFK 2535 and 2650) not to reprocess the irradiated fuel elements in the foreseeable future, to initially dispense with the fuels and broods present in them and, after an appropriate declining time, to the storage facilities provided for this purpose, if necessary removably to be disposed of. 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 extremely 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.In some cases, very complex concepts are known for storing the irradiated fuel assemblies in salt, sand or in rock caverns using metal or concrete containers.

Als Verpackung für radioaktive Stoffe und bestrahlte Brennelemente werden Behälter aus legierten und unlegierten 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 L;ngzeitlagerung, wie dichter Einschluß bei den auftretenden Drucken und Temperaturen, sowie Korrosion gegen Salzlaugen, nur zum Teil, oder sie müssen sehr dickwandig ausgebildet werden. Außerdem eigenen 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 unalloyed steel, copper and corundum are proposed as packaging for radioactive materials and irradiated fuel elements. The steel containers are not either sufficiently corrosion-resistant or, like copper, 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 sealing 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 has to 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 Spannungsreibe 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 grater. 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.

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 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 creating 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 container protective layer applied to the outer surface, the outer protective layer being suitable for any base body that is as cheap as possible, having the highest possible corrosion protection and offering protection against mechanical damage, and preventing fission products from escaping from the repository.

Die Aufgabe wird erfindungsgemäß dadurch gelöst, daß die Schutzschicht aus einem gut haftenden Kunststoff besteht, in den 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. Als Kunststoffkomponente kann man jedoch auch beispielsweise Polytetrafluoräthylen, Polycarbonat, Epoxyharze, Phenolformaldehydharze oder Acrylatkautschuk verwenden.The object is achieved in that the protective layer consists of a well-adhering plastic in which a filler which has swellable, ion-exchangeable and adsorptive properties in the presence of water is incorporated. 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. However, polytetrafluoroethylene, polycarbonate, epoxy resins, phenol formaldehyde resins or acrylate rubber can also be used 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.A 1-3 cm thick layer of polyurethane, for example, is applied to the outside of the closed final storage container, which contains spent fuel elements or individual rods, the two-component system of the polyurethane containing 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.After the two components of the polyurethane system have reacted on the surface of the repository, the latter has a well-adhering and tight coating which contains bentonite in a homogeneous distribution.

Die Beschichrung 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 Störfall in den in Deutschland vorgesehenen Endlagerformationen vorliegen würde, absolut korrosionsbeständig.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 exist in the repository formations provided for 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 4-7-fache 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. a crack, the filler is exposed. This swells in the presence of water to 4-7 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.The protective layer according to the invention thus 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 (4)

1. 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, dadurch gekennzeichnet, daß die Schutzschicht (2) aus einem gut haftenden Kunststoff besteht, in den ein in Gegenwart von Wasser quellfähiger, ionenaustauschfähiger und adsorptive. Eigenschäftsn aufweisender Füllstoff eingelagert ist.1. Container for 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, characterized in that the protective layer (2) consists of a well-adhering plastic in the a swellable, ion-exchangeable and adsorptive in the presence of water. Own filler is stored. 2. Behälter nach Anspruch 1, dadurch gekennzeichnet, daß in den Kunststoff ein Schichtsilikat vom Montmorillonittyp eingelagert ist.2. Container according to claim 1, characterized in that a layer silicate of the montmorillonite type is embedded in the plastic. 3. Behälter nach Anspruch 1 und 2, dadurch gekennzeichnet, daß als Schichtsilikat Bentonit verwendet wird.3. Container according to claim 1 and 2, characterized in that bentonite is used as layered silicate. 4. Behälter nach Anspruch 1 bis 3, dadurch behennzeichnet, daß als Kunststoff Polyurethan verwendet wird.4. Container according to claim 1 to 3, characterized in that polyurethane is used as plastic.
EP82106184A 1981-08-19 1982-07-10 Container for long-term storage of radioactive waste Expired EP0072429B1 (en)

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 true EP0072429A1 (en) 1983-02-23
EP0072429B1 EP0072429B1 (en) 1985-04-17

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EP82106184A Expired EP0072429B1 (en) 1981-08-19 1982-07-10 Container for long-term storage of radioactive waste

Country Status (6)

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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 (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2176925A (en) * 1985-06-19 1987-01-07 Us Energy Waste disposal package
FR2629625A1 (en) * 1988-03-31 1989-10-06 Westinghouse Electric Corp METHOD AND APPARATUS FOR MITIGATING 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
WO2005006349A1 (en) * 2003-06-27 2005-01-20 Polybern Gmbh Improved method for the containment of special waste
WO2013060326A1 (en) 2011-10-28 2013-05-02 Graef Volkmar Container system for intermediate or final storage of radioactive waste and/or toxic waste material
WO2015124773A1 (en) * 2014-02-24 2015-08-27 Cura Ingenieurgesellschaft Mbh Container for the storage of radioactive waste

Families Citing this family (6)

* Cited by examiner, † Cited by third party
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
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
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

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1350579A (en) * 1963-03-18 1964-01-24 Sorbent substance and its manufacturing process
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
US3935467A (en) * 1973-11-09 1976-01-27 Nuclear Engineering Co., Inc. Repository for fissile materials
US3951859A (en) * 1972-12-30 1976-04-20 Toyo Jozo Co., Ltd. Molecular sieving particle and preparation thereof
DE2065863A1 (en) * 1969-08-13 1976-09-23 Transnucleaire Transportation container for radioactive prods. - has cooling fins embedded in aluminous cement outside container wall
FR2473213A1 (en) * 1980-01-07 1981-07-10 Ecopo Drum for long term storage of radioactive or toxic wastes - has continuous sealed inner lining of thermosetting resin

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1350579A (en) * 1963-03-18 1964-01-24 Sorbent substance and its manufacturing process
DE2065863A1 (en) * 1969-08-13 1976-09-23 Transnucleaire Transportation container for radioactive prods. - has cooling fins embedded in aluminous cement outside container wall
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
FR2473213A1 (en) * 1980-01-07 1981-07-10 Ecopo Drum for long term storage of radioactive or toxic wastes - has continuous sealed inner lining of thermosetting resin

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
SPRECHSAAL, Band 113, Nr. 10, Oktober 1980, Seiten 753-764, Coburg, DE. *

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2176925A (en) * 1985-06-19 1987-01-07 Us Energy Waste disposal package
FR2629625A1 (en) * 1988-03-31 1989-10-06 Westinghouse Electric Corp METHOD AND APPARATUS FOR MITIGATING 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
WO2005006349A1 (en) * 2003-06-27 2005-01-20 Polybern Gmbh Improved method for the containment of special waste
WO2013060326A1 (en) 2011-10-28 2013-05-02 Graef Volkmar Container system for intermediate or final storage of radioactive waste and/or toxic waste material
DE102011085480A1 (en) 2011-10-28 2013-05-02 Volkmar Gräf CONTAINER SYSTEM FOR THE END STORAGE OF RADIOACTIVE WASTE AND / OR POISONOIL
WO2015124773A1 (en) * 2014-02-24 2015-08-27 Cura Ingenieurgesellschaft Mbh Container for the storage of radioactive waste

Also Published As

Publication number Publication date
DE3263122D1 (en) 1985-05-23
JPS5840000A (en) 1983-03-08
EP0072429B1 (en) 1985-04-17
ES280865Y (en) 1985-08-01
BR8204782A (en) 1983-08-02
CA1170845A (en) 1984-07-17
DE3132704A1 (en) 1983-03-10
DE3132704C2 (en) 1985-12-19
ES280865U (en) 1985-02-01

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