EP0057430A1 - Container for transporting and storing radioactive wastes - Google Patents
Container for transporting and storing radioactive wastes Download PDFInfo
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- EP0057430A1 EP0057430A1 EP82100593A EP82100593A EP0057430A1 EP 0057430 A1 EP0057430 A1 EP 0057430A1 EP 82100593 A EP82100593 A EP 82100593A EP 82100593 A EP82100593 A EP 82100593A EP 0057430 A1 EP0057430 A1 EP 0057430A1
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- container
- transport
- storage
- graphite block
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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
Definitions
- the invention relates to a transport and storage container for long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of an outer container and an inner container.
- Irradiated, spent fuel elements are processed after temporary storage in water basins either immediately 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 fission products are conditioned using known processes, usually using large quantities of valuable materials such as lead and copper, and are virtually no longer removable in suitable geological formations.
- it is being considered (reports from the Nuclear Research Center Düsseldorf KFK 2535 and 2650) not to reprocess the irradiated fuel elements in the foreseeable future, to initially dispense with the fuels present in them and, after an appropriate decay time in the storage facilities provided for this purpose, to re-use the fuel elements 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.
- Containers made of alloyed and unalloyed steel, copper and corundum are used as packaging for radioactive materials and irradiated fuel elements beaten.
- 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 under pressure and temperature, 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.
- Containers used for the transport and storage of radioactive waste usually consist of an outer container and an inner container. Both parts of the container are generally made of metal. Compliance with the long storage times requires expensive materials because they have to be installed as corrosion barriers.
- the inner container consists of a monolithic graphite block in which the radioactive waste is embedded.
- This monolithic graphite block can be easily manufactured by known processes and cannot be attacked by corrosion.
- graphite powder with sulfur as a binder can be pressed up to approximately 120 ° C. into blocks in which the theoretical density is almost reached. If metal powders such as Ni, Mn, Fe, Zn, Pb and Sn are added to the mixture, which form insoluble sulfides with the sulfur at a somewhat higher temperature, the graphite block does not soften even at higher temperatures. Since no higher temperatures are required during production, spent fuel rods or fuel elements can be used embed in cans in such a graphite block. Such a monolithic graphite block, possibly still covered with a steel sleeve, then serves as an inner container for a transport container of a known type.
- metal powders such as Ni, Mn, Fe, Zn, Pb and Sn
- this transport container with the graphite block it contains is stored in deep geological layers, for example in rock salt, then the outer metal jacket, which is made of cheap cast iron, for example, can be destroyed by corrosion because the inner graphite block is corrosion-resistant and can absorb the full rock pressure .
- the outer metal jacket which is made of cheap cast iron, for example, can be destroyed by corrosion because the inner graphite block is corrosion-resistant and can absorb the full rock pressure .
- the figure schematically shows a transport and storage container according to the invention in an exemplary embodiment.
- the container consists of an outer container (1), for example made of cast iron, and a monolithic graphite block (2) as an inner container in which the radioactive waste, which is preferably located in cans (3), is embedded.
- the waste can advantageously be pressed into the graphite block as fuel elements open or in tins. However, it is also possible to introduce it into bores or other cavities in the graphite block.
- the outer container (1) is closed with a lid (4). All materials known for this purpose can be used as the material for the outer container and lid.
- the monolithic graphite block with a metallic coating in order to close any pores that may still be present or to improve the heat transfer to the outer container, e.g. galvanic or de-energized ..
- a hexagonal graphite block with a key width of 360 mm and a length of 4 m is pre-pressed with 210 channels in the inactive area.
- 210 spent fuel rods are then introduced into the channels of the block, the block is provided at the top and bottom with a graphite disc, which has also been pre-pressed, and is finished pressed in a hot press.
- a mixture of 43.3% graphite powder, 36.7% nickel powder and 20 sulfur flowers is used as the press powder.
- a 4-column press with 3 hydraulic drives is used to deform the block.
- the stroke of the hexagonal lower punch extends almost over the entire (4 m) die length.
- 210 polished steel rods are used to form the channels, which can be inserted through the die from below.
- the pressing is done in sections.
- hexagonal discs 180 mm thick are pre-pressed, which will later serve as the base and cover.
- the pre-pressed parts are then transported to a hot cell and inserted into a hot press. First, a pre-pressed disc (as the base) is placed on the die, on which the 4 m long block is placed. Then spent fuel rods (210 pieces) are inserted into the channels.
- the upper space up to the fuel rod is filled with press powder and the pre-pressed upper cover is put on.
- the press block by heating and radiant heat reaches 120 0 C, starting with the final pressing at 50 MN / m 2.
- the temperature is increased further while maintaining the pressure and, when using nickel powder, must reach 400 to 450 ° C. so that the sulfur is quantitatively set as NiS.
- the resulting, high-density graphite block can already be ejected from the die.
- This graphite block is used in a transport container made of cast iron for transport, to the intermediate or final storage facility. Final storage is also possible without the outer container by inserting the graphite block directly into the borehole of a salt mine.
- Example 1 While in Example 1 the fuel assembly has to be disassembled into individual rods beforehand, direct embedding of entire fuel assemblies ( ⁇ 235 fuel rods) is also possible.
- the end pieces are sawn off from a biblis fuel assembly to keep the overall length small.
- a steel cylinder with an inner diameter of 230 mm and a length of 4.30 m is used to hold the fuel assembly hull.
- the ends of the cylinder consist of spherical caps, which are welded tightly to the cylinder. This fuel assembly should withstand an external pressure of 300 bar.
- this fuel assembly is inserted into a graphite cylinder prefabricated according to Example 1 with only one hollow channel, inserted into the hot press at the open ends with pre-pressed lids and pressed as in Example 1.
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- Engineering & Computer Science (AREA)
- Environmental & Geological Engineering (AREA)
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- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
Abstract
Description
Gegenstand der Erfindung ist ein Transport- und Lagerbehälter zur Langzeitlagerung von radioaktiven Abfällen, insbesondere von abgebrannten Brennelementen, in geeigneten geologischen Formationen, bestehend aus einem Außenbehälter und einem Innenbehälter.The invention relates to a transport and storage container for long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of an outer container and an inner container.
Bestrahlte, abgebrannte Brennelemente werden nach einer vorübergehenden Aufbewahrung in 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 bekanten Verfahren, meist unter Verwendung großer Mengen Wertstoffe, wie zum Beispiel Blei und Kupfer, konditioniert und in geeigneten geologischen Formationen praktisch nicht mehr entnehmbar endgelagert. 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 Abklingzeit in dafür vorgesehenen 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.Irradiated, spent fuel elements are processed after temporary storage in water basins either immediately 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 fission products are conditioned using known processes, usually using large quantities of valuable materials such as lead and copper, and are virtually no longer removable in suitable geological formations. 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 present in them and, after an appropriate decay time in the storage facilities provided for this purpose, to re-use the fuel elements 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 Lagerbehältern 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 Brennelementen mittels Behältern aus Metall oder Beton in Salz, Sand oder in Felskavernen zu lagern.There are some very expensive K onzepte known, the irradiated fuel by means of containers made of metal or concrete in salt, sand or stored in rock caverns.
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 grundsäztlich 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.Containers made of alloyed and unalloyed steel, copper and corundum are used as packaging for radioactive materials and irradiated fuel elements beaten. 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.
Solche Behälter erfüllen die Bedingungen der Langzeitlagerung, wie dichter Einschluß bei 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.Such containers only partially meet the conditions of long-term storage, such as tight containment under pressure and temperature, 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.
Behälter, die zum Transport und zur Lagerung radioaktiver Abfälle dienen, bestehen normalerweise aus einem Außenbehälter und einem Innenbehälter. Beide Behälterteile sind im allgemeinen aus Metall. Die Einhaltung der langen Lagerzeiten erfordern teure Materialien, da sie als Korrosionsbarrieren eingebaut werden müssen.Containers used for the transport and storage of radioactive waste usually consist of an outer container and an inner container. Both parts of the container are generally made of metal. Compliance with the long storage times requires expensive materials because they have to be installed as corrosion barriers.
Es war deshalb Aufgabe der vorliegenden Erfindung, einen Transport- und Lagerbehälter zur Langzeitlagerung radioaktiver Abfälle, insbesondere abgebrannter Brennelemente, in geeigneten geologischen Formationen zu schaffen, bei dem die radioaktiven Abfälle in einem Innenbehälter korrosionssicher und druckbeständig so eingebracht werden können, daß der Außenbehälter aus billigem, minderwertigem Material hergestellt werden kann. Falls sich dieser Außenbehälter im ungünstigem Falle nach einer bestimmten Zeit im Salz oder in Salzlauge aufgelöst hat, muß der Innenbehälter einem Druck von 300 bar bei 200 0 C und Salzlauge bis zum Ablauf der vorgesehenen Lagerzeit widerstehen können.It was therefore an object of the present invention to provide a transport and storage container for long-term storage of radioactive waste, in particular abge to create burned fuel elements in suitable geological formations, in which the radioactive waste can be placed in an inner container in a manner which is corrosion-proof and pressure-resistant in such a way that the outer container can be produced from cheap, inferior material. If, in the worst case, this outer container has dissolved in the salt or in brine after a certain time, the inner container must be able to withstand a pressure of 300 bar at 200 ° C. and brine until the intended storage time has expired.
Diese Aufgabe wurde erfindungsgemäß dadurch gelöst, daß der Innenbehälter aus einem monolithischen Graphitblock besteht, in dem die radioaktiven Abfälle eingebettet sind. Dieser monolithische Graphitblock ist leicht nach bekannten Verfahren herstellbar und kann durch Korrosion nicht angegriffen werden.This object was achieved in that the inner container consists of a monolithic graphite block in which the radioactive waste is embedded. This monolithic graphite block can be easily manufactured by known processes and cannot be attacked by corrosion.
Es hat sich gezeigt, daß man Graphitpulver mit Schwefel als Bindemittel bis ca. 120 0 C zu Blöcken verpressen kann, bei denen nahezu die theoretische Dichte erreicht wird. Gibt man zu der Mischung noch Metallpulver, wie zum Beispiel Ni, Mn, Fe, Zn, Pb und Sn, die bei etwas höherer Temperatur mit dem Schwefel unlösliche Sulfide bilden, so erweicht der Graphitblock auch bei höheren Temperaturen nicht. Da bei der Herstellung keine höheren Temperaturen erforderlich sind, lassen sich abgebrannte Brennstäbe oder Brennelemente in Büchsen in einen solchen Graphitblock einbetten. Ein solcher monolithischer Graphitblock, eventuell noch mit einer Stahlbüchse ummantelt, dient dann als Innenbehälter für einen Transportbehälter bekannter Bauart. Wird dieser Transportbehälter mit dem enthaltenen Graphitblock in tiefen geologischen Schichten, zum Beispiel in Steinsalz endgelagert, dann kann der äußere Metallmantel, der zum Beispiel aus billigem.Eisenguß besteht, durch Korrosion zerstört werden, weil der innere Graphitblock korrosionsbeständig ist und den vollen Gebirgsdruck aufzunehmen vermag. Es besteht aber auch die Möglichkeit, den Graphitblock als Innenbehälter dem Außenbehälter zu entnehmen und direkt endzulagern.It has been shown that graphite powder with sulfur as a binder can be pressed up to approximately 120 ° C. into blocks in which the theoretical density is almost reached. If metal powders such as Ni, Mn, Fe, Zn, Pb and Sn are added to the mixture, which form insoluble sulfides with the sulfur at a somewhat higher temperature, the graphite block does not soften even at higher temperatures. Since no higher temperatures are required during production, spent fuel rods or fuel elements can be used embed in cans in such a graphite block. Such a monolithic graphite block, possibly still covered with a steel sleeve, then serves as an inner container for a transport container of a known type. If this transport container with the graphite block it contains is stored in deep geological layers, for example in rock salt, then the outer metal jacket, which is made of cheap cast iron, for example, can be destroyed by corrosion because the inner graphite block is corrosion-resistant and can absorb the full rock pressure . However, there is also the option of removing the graphite block as an inner container from the outer container and storing it directly.
Die Abbildung zeigt schematisch einen erfindungsgemäßen Transport-und Lagerbehälter in beispielhafter Ausführungsform.The figure schematically shows a transport and storage container according to the invention in an exemplary embodiment.
Der Behälter besteht aus einen Außenbehälter (1), beispielsweise aus Gußeisen, und einem monolithischen Graphitblock (2) als Innenbehälter, in den die radioaktiven Abfälle, die sich vorzugsweise in Büchsen (3) befinden, eingebettet sind. Die Abfälle können vorteilhafterweise als Brennelemente offen oder in Büchsen befindlich in den Graphitblock eingepreßt werden.Es ist jedoch auch möglich, sie in Bohrungen oder sonstige Hohlräume des Graphitblocks einzubringen. Der Äußenbehälter (1) wird mit einem Deckel (4) verschlossen. Als Material für Außenbehälter und Deckel sind alle dafür bekannten Werkstoffe verwendbar.The container consists of an outer container (1), for example made of cast iron, and a monolithic graphite block (2) as an inner container in which the radioactive waste, which is preferably located in cans (3), is embedded. The waste can advantageously be pressed into the graphite block as fuel elements open or in tins. However, it is also possible to introduce it into bores or other cavities in the graphite block. The outer container (1) is closed with a lid (4). All materials known for this purpose can be used as the material for the outer container and lid.
In manchen Fällen ist es vorteilhaft, den monolithischen Graphitblock metallisch zu beschichten, um eventuell noch vorhandene Poren zu verschliessen oder den Wärmeübergang auf den Außenbehälter zu verbessern, z.B. galvanisch oder stromlos..In some cases, it is advantageous to coat the monolithic graphite block with a metallic coating in order to close any pores that may still be present or to improve the heat transfer to the outer container, e.g. galvanic or de-energized ..
Folgende Beispiele sollen die Herstellung solcher monolithischen Graphitblöcke als Innenbehälter näher erläutern.The following examples are intended to explain the manufacture of such monolithic graphite blocks as inner containers in more detail.
Zunächst wird ein sechskantiger Graphitblock von 360 mm Schlüsselweite und 4 m Länge mit 210 Kanälen im inaktiven Bereich vorgepreßt. Im heißen Bereich werden dann 210 abgebrannte Brennstäbe in die Kanäle des Blockes eingeführt, der Block oben und unten mit einer ebenfalls vorgepreßten Graphitscheibe versehen und in einer Heißpresse fertiggepreßt.First, a hexagonal graphite block with a key width of 360 mm and a length of 4 m is pre-pressed with 210 channels in the inactive area. In the hot area, 210 spent fuel rods are then introduced into the channels of the block, the block is provided at the top and bottom with a graphite disc, which has also been pre-pressed, and is finished pressed in a hot press.
Als Preßpulver dient zum Beispiel eine Mischung aus 43,3 % Graphitpulver, 36,7 % Nickelpulver und 20 Schwefelblüte. Zur Verformung des Blockes wird eine 4-Säulenpresse mit 3 hydraulischen Antrieben verwendet. Der Hub des sechskantigen Unterstempels reicht nahezu über die gesamte (4 m) Matrizenlänge. Zur Formung der Kanäle dienen 210 polierte Stahlstäbe, die von unten durch die Matritze eingefahren werden können. Das Pressen geschieht abschnittweise. In der gleichen Presse, jedoch mit glatten Stempeln (ohne Löcher), werden Sechskantscheiben von 180 mm Stärke vorgepreßt, die später als Boden und Deckel dienen. Die so vorgepreßten Teile werden dann in eine heiße Zelle transportiert und dort in eine Heißpresse eingesetzt. In die Matrize wird zunächst eine vorgepreßte Scheibe (als Boden) gelegt, auf die der 4 m lange Block gestellt wird. Dann werden abgebrannte Brennstäbe (210 Stck.) in die Kanäle eingeführt.For example, a mixture of 43.3% graphite powder, 36.7% nickel powder and 20 sulfur flowers is used as the press powder. A 4-column press with 3 hydraulic drives is used to deform the block. The stroke of the hexagonal lower punch extends almost over the entire (4 m) die length. 210 polished steel rods are used to form the channels, which can be inserted through the die from below. The pressing is done in sections. In the same press, but with smooth punches (without holes), hexagonal discs 180 mm thick are pre-pressed, which will later serve as the base and cover. The pre-pressed parts are then transported to a hot cell and inserted into a hot press. First, a pre-pressed disc (as the base) is placed on the die, on which the 4 m long block is placed. Then spent fuel rods (210 pieces) are inserted into the channels.
Der obere Freiraum bis zum Brennstab wird mit Preßpulver gefüllt und der vorgepreßte obere Deckel aufgesezt. Wenn der Preßblock durch Heizen und Strahlungswärme 120 0 C erreicht hat, wird mit dem Fertigpressen bei 50 MN/m2 begonnen. Die Temperatur wird unter Beibehaltung des Druckes weitergesteigert und muß bei Anwendung von Nickelpulver 400 bis 450 ° C erreichen, damit der Schwefel quantitativ als NiS abgebunden wird. Unterhalb 400 0 C kann der entstehende, hochdichte Graphitblock bereits aus der Matritze ausgestoßen werden. Für den Transport, zum Zwischen- oder Endlager wird dieser Graphitblock in einen Transportbehälter aus Eisengraphitguß eingesetzt. Eine Endlagerung ist auch ohne den Außenbehälter möglich, indem der Graphitblock direkt ins Bohrloch eines Salzbergwerkes eingesetzt wird.The upper space up to the fuel rod is filled with press powder and the pre-pressed upper cover is put on. When the press block by heating and radiant heat reaches 120 0 C, starting with the final pressing at 50 MN / m 2. The temperature is increased further while maintaining the pressure and, when using nickel powder, must reach 400 to 450 ° C. so that the sulfur is quantitatively set as NiS. Below 400 0 C, the resulting, high-density graphite block can already be ejected from the die. This graphite block is used in a transport container made of cast iron for transport, to the intermediate or final storage facility. Final storage is also possible without the outer container by inserting the graphite block directly into the borehole of a salt mine.
Während bei Beispiel 1 das Brennelement vorher in Einzelstäbe zerlegt werden muß, ist auch die direkte Einbettung ganzer Brennelemente (~235 Brennstäbe) möglich.While in Example 1 the fuel assembly has to be disassembled into individual rods beforehand, direct embedding of entire fuel assemblies (~ 235 fuel rods) is also possible.
Von einem Biblis-Brennelement werden die Endstücke abgesägt, um die Gesamtlänge klein zu halten. Ein Stahlzylinder von 230 mm Innendurchmesser und 4,30 m Länge dient zur Aufnahme des Brennelementrumpfes. Die Enden des Zylinders bestehen aus Kugelkalotten, die dicht mit dem Zylinder verschweißt werden. Diese Brennelementbüchse soll einen Außendruck von 300 bar aushalten.The end pieces are sawn off from a Biblis fuel assembly to keep the overall length small. A steel cylinder with an inner diameter of 230 mm and a length of 4.30 m is used to hold the fuel assembly hull. The ends of the cylinder consist of spherical caps, which are welded tightly to the cylinder. This fuel assembly should withstand an external pressure of 300 bar.
In einer heißen Zelle wird diese Brennelementbüchse in einen nach Beispiel 1 vorgefertigten Graphitzylinder mit nur einem Hohlkanal eingesetzt, an den offenen Enden mit vorgepreßten Deckeln in die Heißpresse eingesetzt und wie in Beispiel 1 fertiggepreßt.In a hot cell, this fuel assembly is inserted into a graphite cylinder prefabricated according to Example 1 with only one hollow channel, inserted into the hot press at the open ends with pre-pressed lids and pressed as in Example 1.
Außer Nickelpulver und Schwefelblüte können selbstverständlich auch alle anderen Bindemittel verwendet werden, die bei einer Temperatur, bei der die Spaltprodukte nicht oder kaum flüchtig sind, zu dichtem Graphit führen.In addition to nickel powder and sulfur bloom, it is of course also possible to use all other binders which lead to dense graphite at a temperature at which the fission products are not or hardly volatile.
Claims (4)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE3103557 | 1981-02-03 | ||
| DE19813103557 DE3103557A1 (en) | 1981-02-03 | 1981-02-03 | "TRANSPORT AND STORAGE CONTAINERS FOR RADIOACTIVE WASTE" |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| EP0057430A1 true EP0057430A1 (en) | 1982-08-11 |
Family
ID=6123917
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP82100593A Withdrawn EP0057430A1 (en) | 1981-02-03 | 1982-01-28 | Container for transporting and storing radioactive wastes |
Country Status (3)
| Country | Link |
|---|---|
| EP (1) | EP0057430A1 (en) |
| JP (1) | JPS57178190A (en) |
| DE (1) | DE3103557A1 (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2151068A (en) * | 1983-12-09 | 1985-07-10 | Kernforschungsanlage Juelich | Process for storing fuel elements |
| US4560502A (en) * | 1981-11-11 | 1985-12-24 | Nukem Gmbh | Molded body for embedding radioactive waste and process for its production |
| US4626382A (en) * | 1983-07-06 | 1986-12-02 | Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh | Method of producing a glass block containing radioactive fission products and apparatus therefor |
| WO2003096355A1 (en) * | 2002-05-10 | 2003-11-20 | Pebble Bed Modular Reactor (Proprietary) Limited | Method of and apparatus for use in disposing of spent nuclear fuel |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP1434239B1 (en) * | 2002-12-24 | 2008-02-06 | GNS Gesellschaft für Nuklear-Service mbH | Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells |
| DE102009044963B4 (en) * | 2008-11-10 | 2011-06-22 | ALD Vacuum Technologies GmbH, 63450 | Graphite matrix blocks with inorganic binder suitable for storage of radioactive waste and method of making the same |
| US8502009B2 (en) | 2008-11-26 | 2013-08-06 | Ald Vacuum Technologies Gmbh | Matrix material comprising graphite and an inorganic binder suited for final disposal of radioactive waste, a process for producing the same and its processing and use |
| DE102010003289B4 (en) * | 2010-03-25 | 2017-08-24 | Ald Vacuum Technologies Gmbh | Containers for the storage of radioactive waste and process for its production |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3828197A (en) * | 1973-04-17 | 1974-08-06 | Atomic Energy Commission | Radioactive waste storage |
| US3993579A (en) * | 1975-10-22 | 1976-11-23 | The United States Of America As Represented By The United States Energy Research And Development Administration | Method of encapsulating solid radioactive waste material for storage |
| GB2048554A (en) * | 1979-04-28 | 1980-12-10 | Nukem Gmbh | Process for conditioning radioactive and/or toxic waste |
| DE2942092A1 (en) * | 1979-10-18 | 1981-04-30 | Steag Kernenergie Gmbh, 4300 Essen | Long term storage of spent fuel elements - in graphite container resistant to corrosion with external metal cover |
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1981
- 1981-02-03 DE DE19813103557 patent/DE3103557A1/en not_active Withdrawn
-
1982
- 1982-01-28 EP EP82100593A patent/EP0057430A1/en not_active Withdrawn
- 1982-02-03 JP JP57015005A patent/JPS57178190A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3828197A (en) * | 1973-04-17 | 1974-08-06 | Atomic Energy Commission | Radioactive waste storage |
| US3993579A (en) * | 1975-10-22 | 1976-11-23 | The United States Of America As Represented By The United States Energy Research And Development Administration | Method of encapsulating solid radioactive waste material for storage |
| GB2048554A (en) * | 1979-04-28 | 1980-12-10 | Nukem Gmbh | Process for conditioning radioactive and/or toxic waste |
| DE2942092A1 (en) * | 1979-10-18 | 1981-04-30 | Steag Kernenergie Gmbh, 4300 Essen | Long term storage of spent fuel elements - in graphite container resistant to corrosion with external metal cover |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4560502A (en) * | 1981-11-11 | 1985-12-24 | Nukem Gmbh | Molded body for embedding radioactive waste and process for its production |
| US4626382A (en) * | 1983-07-06 | 1986-12-02 | Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh | Method of producing a glass block containing radioactive fission products and apparatus therefor |
| GB2151068A (en) * | 1983-12-09 | 1985-07-10 | Kernforschungsanlage Juelich | Process for storing fuel elements |
| WO2003096355A1 (en) * | 2002-05-10 | 2003-11-20 | Pebble Bed Modular Reactor (Proprietary) Limited | Method of and apparatus for use in disposing of spent nuclear fuel |
Also Published As
| Publication number | Publication date |
|---|---|
| DE3103557A1 (en) | 1982-12-09 |
| JPS57178190A (en) | 1982-11-02 |
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| RIN1 | Information on inventor provided before grant (corrected) |
Inventor name: SCHMIDT-HANSBERG, THOMAS, DIPL.CHEM. Inventor name: VIETZKE, HORST, DR. DIPL.CHEM. Inventor name: HUSCHKA, HANS, DR. DIPL.CHEM. Inventor name: HROVAT, MILAN, DR. DIPL.ING. |