EP0092679B1 - Container for radioactive wastes - Google Patents
Container for radioactive wastes Download PDFInfo
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- EP0092679B1 EP0092679B1 EP83102908A EP83102908A EP0092679B1 EP 0092679 B1 EP0092679 B1 EP 0092679B1 EP 83102908 A EP83102908 A EP 83102908A EP 83102908 A EP83102908 A EP 83102908A EP 0092679 B1 EP0092679 B1 EP 0092679B1
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- Prior art keywords
- container
- layer
- corrosion
- cast
- inner layer
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
- G21F5/008—Containers for fuel elements
Definitions
- the invention relates to a container for holding radioactive substances, in particular irradiated nuclear reactor fuel elements, in which the basic container body is constructed in multiple layers, the inner layer consisting of a mechanically stable, inexpensive metallic material and the adjacent layer as a corrosion protection layer made of a cast around the inner layer.
- high-alloy austenitic cast iron with spheroidal graphite and in which the receiving opening of the container body is closed by a sealing cover welded to the corrosion protection layer.
- the fuel elements are loaded into a transport container.
- These transport containers must be sealed gas-tight, which is achieved via a lid sealing system, and ensure adequate shielding against radioactivity.
- the transport containers must have sufficient mechanical strength that can withstand accident conditions.
- the transport container must also be designed so that the post-decay heat of the transported fuel elements can be safely dissipated to the outside.
- the loaded transport containers are brought to an interim storage facility, where they are to be stored until the spent nuclear fuel elements are reprocessed later or for long-term storage, the so-called direct final storage.
- the transport containers must then be opened again.
- direct final storage the spent nuclear reactor fuel elements must be packed in special final storage containers and placed in geological formations for safe final storage.
- the repository containers must have certain endager properties. They have to be mechanically stable, corrosion-proof and tightly sealed.
- the hardener base of the repository container is therefore made of steel or cast iron to ensure the mechanical stability of the container. It would be preferable to use spheroidal graphite cast iron (GGG 40) for the thick-walled container body, since spheroidal cast iron is characterized by its particularly high strength and toughness.
- This corrosion-resistant protective layer can consist of ceramic, graphite or other materials.
- This fuel element container designed in this way can also be used for longer surface storage of the irradiated fuel elements and for transport if the thickness of the cheap inner layer is increased in accordance with the requirements for the shielding.
- the invention is based on the object of designing a container of the type described at the outset in such a way that it can be used not only for final storage, but also for longer surface storage and for transporting the irradiated fuel elements, the amount of material in the corrosion protection layer being kept as low as possible.
- the container base body has an outer layer of cast iron with spheroidal graphite cast around the corrosion protection layer.
- the outer layer is cast in a mold around the corrosion protection layer. The surface of the corrosion protection layer is melted, so that a good connection between the outer layer and the corrosion protection layer is created.
- the good connection between the two layers is also promoted by the fact that the structure of the outer layer is similar to the structure of the corrosion protection layer.
- the outer layer made of nodular cast iron is very well suited for the use according to the invention due to the high yield strength of spherulitic cast iron, since the nodular cast iron withstands the shrinkage stresses well due to its high yield strength.
- An advantageous embodiment of the invention is characterized in that the inner layer consists of a drawn steel tube.
- the inner layer can have a smaller thickness due to the higher mechanical strength of a drawn steel tube. This smaller thickness means a smaller diameter of the inner layer.
- the invention provides a fuel assembly container which receives the spent nuclear reactor fuel elements delivered in transport containers after a certain decay time.
- the fuel assemblies can then be stored on the surface in an intermediate storage facility until the final repository is built or the reprocessing of the fuel assembly is decided.
- the welded-on cover is milled and the fuel elements removed. If the fuel assemblies are to be sent to the direct repository in a geological formation, the fuel assembly container is brought directly to the repository without reloading or additional transport shielding.
- test of the fuel element container according to the invention is carried out by the usual test methods such as ultrasound examination and X-ray examination, whereby each cast layer can be checked individually.
- the container receiving the fuel elements has a thick-walled basic container body 3, which is composed of three layers.
- the container body 3 is cylindrical and open at its front end.
- the inner layer 5 of the container body 3 consists of a spherulitic cast iron (GGG 40). At the open end, this pot-shaped inner layer 5 has an internal thread 6, into which a pressure cover 7 is screwed.
- GGG 40 spherulitic cast iron
- a corrosion protection layer 8 made of high-alloy austenitic nodular cast iron is cast around the inner layer 5.
- This cast material which provides protection against corrosion, is an austenitic nodular cast iron with a max. 3% C, 13 to 36% Ni and lower alloy components of Si, Cu and Cr.
- Such a material is GGGNiCr 20.2 (trade name: "Ni-resist").
- the corrosion protection coating 8 has a welding lip 9 which is concentric with the receiving opening 4.
- a corrosion protection cover 11 made of the same material is inserted into the receiving opening 4 and connected to the welding lip 9 of the casing 8 via a counter welding lip 12.
- the outer layer 13 of the container body consists of cast iron with spheroidal graphite (GGG 40).
- a shielding cover 14 made of spherulitic cast iron is screwed to the outer cast body 13.
- the respective cup-shaped casting layer was inserted as a molded part in the casting mold during the manufacturing process of the next outer layer. After the material melt of the next layer has been poured in, the surface connects to the cast layer. The three layers of the container body 3 are thus firmly connected.
- the corrosion protection cover 11 is made of the same material as the corrosion protection layer 8. A subsequent heat treatment of the container after the cover is welded is therefore not necessary.
- the inner layer 21 is formed from a drawn steel tube, which is welded at the end opposite the receiving opening 4 by a circular steel plate 23.
- Drawn steel pipes have a higher mechanical strength than corresponding cast bodies. Therefore, the inner layer 21 of the container body 3 can be made thinner. The result of this is that the central corrosion protection layer 8 is of a smaller diameter.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Other Surface Treatments For Metallic Materials (AREA)
- Butt Welding And Welding Of Specific Article (AREA)
- Laminated Bodies (AREA)
- Devices For Use In Laboratory Experiments (AREA)
- Thermally Insulated Containers For Foods (AREA)
- Secondary Cells (AREA)
Description
Die Erfindung betrifft einen Behälter zur Aufnahme von radioaktiven Stoffen, insbesondere bestrahlten Kernreaktorbrennelementen, bei dem der Behältergrundkörper mehrschichtig aufgebaut ist, wobei die innere Schicht aus einem mechanisch stabilen, billigen metallischen Werkstoff und die daran angrenzende Schicht als Korrosionsschutzschicht aus einem um die innere Schicht gegossenen, hochlegierten austenitischen Gusswerkstoff mit Kugelgraphit besteht, und bei dem die Aufnahmeöffnung ds Behältergrundkörpers durch einen mit der Korrosionsschutzschicht verschweissten Verschlussdeckel verschlossen ist.The invention relates to a container for holding radioactive substances, in particular irradiated nuclear reactor fuel elements, in which the basic container body is constructed in multiple layers, the inner layer consisting of a mechanically stable, inexpensive metallic material and the adjacent layer as a corrosion protection layer made of a cast around the inner layer. high-alloy austenitic cast iron with spheroidal graphite, and in which the receiving opening of the container body is closed by a sealing cover welded to the corrosion protection layer.
Zum Transport der abgebrannten Kernreaktorbrennelemente zu einer Lagerstelle werden die Brennelemente in einen Transportbehälter geladen. Diese Transportbehälter müssen gasdicht verschlossen sein, was über ein Deckeldichtsystem erreicht wird, und eine ausreichende Abschirmung der Radioaktivität gewährleisten. Die Transportbehälter müssen eine ausreichende mechanische Festigkeit aufweisen, die auch Unfallbedingungen widerstehen kann. Weiter muss der Transportbehälter so ausgelegt sein, dass die Nachzerfallswärme der transportierten Brennelemente sicher nach aussen abgeleitet werden kann.To transport the spent nuclear reactor fuel elements to a storage location, the fuel elements are loaded into a transport container. These transport containers must be sealed gas-tight, which is achieved via a lid sealing system, and ensure adequate shielding against radioactivity. The transport containers must have sufficient mechanical strength that can withstand accident conditions. The transport container must also be designed so that the post-decay heat of the transported fuel elements can be safely dissipated to the outside.
Die beladenen Transportbehälter werden in ein Zwischenlagerverbracht, wo sie bis zu einer späteren Wiederaufbereitung der abgebrannten Kernbrennelemente oder einer Langzeitlagerung, der sogenannten direkten Endlagerung, aufbewahrt werden sollen. Die Transportbehälter müssen dann wieder geöffnet wrden. Im Falle der direkten Endlagerung müssen die abgebrannten Kernreaktorbrennelemente in spezielle Endlagerbehälter gepackt und in diesen in geologische Formationen zur sicheren Endlagerung verbracht werden.The loaded transport containers are brought to an interim storage facility, where they are to be stored until the spent nuclear fuel elements are reprocessed later or for long-term storage, the so-called direct final storage. The transport containers must then be opened again. In the case of direct final storage, the spent nuclear reactor fuel elements must be packed in special final storage containers and placed in geological formations for safe final storage.
Die Endlagerbehälter müssen bestimmte Endiagereigenschaften aufweisen. Sie müssen mechanisch stabil, korrosionsfest und dicht verschlossen sein. Der Behärtergrundkörper des Endlagerbehälters wird daher aus Stahl oder Gusseisen hergestellt, um die mechanische Stabilität des Behälters zu gewährleisten. Bevorzugt möchte man für den dickwandigen Behältergrundkörper Gusseisen mit Kugelgraphit (GGG 40) verwenden, da sphärolithisches Gusseisen sich durch besonders hohe Festigkeit und Zähigkeit auszeichnet.The repository containers must have certain endager properties. They have to be mechanically stable, corrosion-proof and tightly sealed. The hardener base of the repository container is therefore made of steel or cast iron to ensure the mechanical stability of the container. It would be preferable to use spheroidal graphite cast iron (GGG 40) for the thick-walled container body, since spheroidal cast iron is characterized by its particularly high strength and toughness.
Da aber die Korrosionsbeständigkeit von Stahl oder Gusseisen mit Kugelgraphit für den Zweck der Endlagerung ungenügend ist, wurde bereits vorgeschlagen, auf dem Behältergrundkörper aus Stahl oder Gusseisen aussen eine korrosionsfeste Schutzschicht aufzubringen. Diese korrosionsfeste Schutzschicht kann aus Keramik, Graphit oder anderen Werkstoffen bestehen.However, since the corrosion resistance of steel or cast iron with spheroidal graphite is insufficient for the purpose of final storage, it has already been proposed to apply a corrosion-resistant protective layer on the outside of the container base made of steel or cast iron. This corrosion-resistant protective layer can consist of ceramic, graphite or other materials.
In einer nicht vorveröffentlichten Patentanmeldung (EP-A Nr. 0083024) wird vorgeschlagen, einen Behälter für die Endlagerung von bestrahlten Kernreaktorbrennelementen aus zwei metallischen Schichten aufzubauen, wobei die innere Schicht aus einem mechanisch stabilen, billigen Werkstoff und die äussere Schicht aus einem korrosionsfesten Werkstoff besteht. Dabei soll die innere Schicht aus Gusseisen mit Kugelgraphit oder Lamellengraphit und die äussere Schicht aus einem um die innere Schicht gegossenen, hochlegierten austenitischen Gusswerkstoff mit Kugelgraphit bestehen. Die Aufnahmeöffnung des Behälters ist durch einen mit der äusseren Schicht verschweissten Verschlussdeckel verschlossen.In a non-prepublished patent application (EP-A No. 0083024) it is proposed to construct a container for the final storage of irradiated nuclear reactor fuel elements from two metallic layers, the inner layer consisting of a mechanically stable, inexpensive material and the outer layer consisting of a corrosion-resistant material . The inner layer should consist of spheroidal graphite or flake graphite cast iron and the outer layer of a high-alloy spheroidal graphite cast iron alloy cast around the inner layer. The receptacle opening of the container is closed by a sealing cover welded to the outer layer.
Dieser so ausgebildete Brennelementbehälter kann auch zur längeren Oberflächenlagerung der bestrahlten Brennelemente und zum Transport genutzt werden, wenn die Dicke der billigen inneren Schicht entsprechend den Anforderungen für die Abschirmung erhöht wird. Dieses hätte allerdings die Folge, dass die teure Korrosionsschutzschicht, die, um für eine Endlagerung ausreichend zu sein, immer eine bestimmte Dicke haben muss, auf einem grösseren Behälterdurchmesser liegt. Der Umfang und damit die erforderliche Werkstoffmenge der Korrosionsschutzschicht wird vergrössert.This fuel element container designed in this way can also be used for longer surface storage of the irradiated fuel elements and for transport if the thickness of the cheap inner layer is increased in accordance with the requirements for the shielding. However, this would have the consequence that the expensive corrosion protection layer, which must always have a certain thickness in order to be sufficient for final storage, lies on a larger container diameter. The scope and thus the required amount of material of the corrosion protection layer is increased.
Der Erfindung liegt dieAufgabe zugrunde, einen Behälter der eingangs beschriebenen Art derart auszugestalten, dass er nicht nur zur Endlagerung, sondern auch zur längeren Oberflächenlagerung und zum Transport der bestrahlten Brennelemente nutzbar ist, wobei die Werkstoffmenge der Korrosionsschutzschicht möglichst niedrig gehalten werden soll.The invention is based on the object of designing a container of the type described at the outset in such a way that it can be used not only for final storage, but also for longer surface storage and for transporting the irradiated fuel elements, the amount of material in the corrosion protection layer being kept as low as possible.
Die Aufgabe wird erfindungsgemäss dadurch gelöst dass der Behältergrundkörper eine um die Karrosionsschuizschicht gegossene äussere Schicht aus Gusseisen mit Kugelgraphit aufweist.The object is achieved according to the invention in that the container base body has an outer layer of cast iron with spheroidal graphite cast around the corrosion protection layer.
Es ist nun möglich, die Korrosionsschutzschicht des Behättergrundkörpers auf einem möglichst kleinen Durchmesser zu belassen, da die Dicke der äusseren Schicht entsprechend der erforderlichen Abschirmwirkung gewählt werden kann. Die äussere Schicht wird in einer Giessform um die Korrosionsschutzschicht gegossen. Die Oberfläche der Korrosionsschutzschicht wird angeschmolzen, so dass eine gute Verbindung zwischen der äusseren Schicht und der Korrosionsschutzschicht entsteht.It is now possible to keep the corrosion protection layer of the container base body as small as possible, since the thickness of the outer layer can be selected in accordance with the required shielding effect. The outer layer is cast in a mold around the corrosion protection layer. The surface of the corrosion protection layer is melted, so that a good connection between the outer layer and the corrosion protection layer is created.
Die gute Verbindung zwischen den beiden Schichten wird auch dadurch gefördert, dass der Gefügeaufbau der äusseren Schicht dem Gefügeaufbau der Korrosionsschutzschicht ähnlich ist. Die äussere Schicht aus Sphäroguss ist aufgrund der hohen Streckgrenze des sphärolithischen Gusseisens für den erfindungsgemässen Einsatz denkbar gut geeignet, da der Sphäroguss aufgrund seiner hohen Streckgrenze die Schrumpfspannungen gut aushält.The good connection between the two layers is also promoted by the fact that the structure of the outer layer is similar to the structure of the corrosion protection layer. The outer layer made of nodular cast iron is very well suited for the use according to the invention due to the high yield strength of spherulitic cast iron, since the nodular cast iron withstands the shrinkage stresses well due to its high yield strength.
Eine vorteilhafte Ausgestaltung der Erfindung wird dadurch gekennzeichnet, dass die innere Schicht aus einem gezogenen Stahlrohr besteht. Dieses hat den wesentlichen Vorteil, dass die innere Schicht aufgrund der höheren mechanischen Festigkeit eines gezogenen Stahlrohres eine geringere Dicke erhalten kann. Diese geringere Dicke bedeutet einen kleineren Durchmeser der inneren Schicht. Das hatvorteilhaftzur Folge, dass die teure Korrosionsschutzschicht auch auf einem kleineren Durchmesser liegt und somit einen geringeren Umfang hat.An advantageous embodiment of the invention is characterized in that the inner layer consists of a drawn steel tube. This has the essential advantage that the inner layer can have a smaller thickness due to the higher mechanical strength of a drawn steel tube. This smaller thickness means a smaller diameter of the inner layer. This has the advantageous consequence that the expensive corrosion protection layer also lies on a smaller diameter and thus has a smaller scope.
Durch die Erfindung wird ein Brennelementbehälter geschaffen, der die in Transportbehältern gelieferten abgebrannten Kernreaktorbrennelemente nach einer bestimmten Abklingzeit aufnimmt. In diesem Brennelementbehälter können die Brennelemente dann in einem Zwischenlager an der Oberfläche gelagert werden, bis das Endlager errichtet oder die Wiederaufarbeitung der Brennelemente beschlossen ist.The invention provides a fuel assembly container which receives the spent nuclear reactor fuel elements delivered in transport containers after a certain decay time. In this fuel assembly, the fuel assemblies can then be stored on the surface in an intermediate storage facility until the final repository is built or the reprocessing of the fuel assembly is decided.
Bei der Entscheidung für eine Wiederaufarbeitung wird der aufgeschweisste Deckel aufgefräst und die Brennelemente entnommen. Sollen die Brennelemente der direkten Endlagerung in einer geologischen Formation zugeführt werden, so wird der Brennelementbehälter direkt ohne ein Umladen oder eine zusätzliche Transportabschirmung in das Endlager verbracht.When deciding to refurbish, the welded-on cover is milled and the fuel elements removed. If the fuel assemblies are to be sent to the direct repository in a geological formation, the fuel assembly container is brought directly to the repository without reloading or additional transport shielding.
Die Prüfung deserfindungsgemässen Brennelementbehälters wird durch die üblichen Prüfungsmethoden wie Ultraschalluntersuchung und Röntgenuntersuchung durchgeführt, wobei jede Gusslage einzeln geprüft werden kann.The test of the fuel element container according to the invention is carried out by the usual test methods such as ultrasound examination and X-ray examination, whereby each cast layer can be checked individually.
Anhand der Zeichnung werden nachstehend zwei Ausführungsbeispiele der Erfindung näher erläutert. Es zeigt
- Fig. einen dreischichtigen gegossenen Brennelementbehälter im Längsschnitt,
- Fig. 2 eine Ausführungsform eines dreischichtigen Brennelementbehälters, bei der die innere Schicht aus einem gezogenen Stahlrohr besteht.
- 3 shows a three-layer cast fuel element container in longitudinal section,
- Fig. 2 shows an embodiment of a three-layer fuel assembly, in which the inner layer consists of a drawn steel tube.
Der die hier nicht gezeigten Brennelemente aufnehmende Behälter (Fig. 1) weist einen dickwandigen Behältergrundkörper 3 auf, der aus drei Schichten aufgebaut ist. Der Behältergrundkörper 3 ist zylindrisch ausgebildet und an seinem stirnseitigen Ende offen.The container receiving the fuel elements, not shown here (FIG. 1), has a thick-walled
Dadurch wird eineAufnahmeöffnung 4 zum Beladen mit den hier nicht gezeigten Brennelementen gebildet.This forms a receiving
Die innere Schicht 5 des Behältergrundkörpers 3 besteht aus einem sphärolithischen Gusseisen (GGG 40). Am offenen Ende weist diese topfförmige Innenschicht 5 ein Innengewinde 6 auf, in das ein Druckdeckel 7 eingeschraubt ist.The
Um die Innenschicht 5 ist eine Korrosionsschutzschicht 8 aus hochlegiertem austenitischem Sphäroguss gegossen. Dieser den Korrosionsschutz bewirkende Gusswerkstoff ist ein austenitischer Sphäroguss mit max. 3% C, 13 bis 36% Ni sowie geringeren Legierungsbestandteilen von Si, Cu und Cr. Ein derartiger Werkstoff ist GGGNiCr 20.2 (Handelsname: «Ni-resist»). An seinem offenen Ende weist die Korrosionsschutzschichtumhüllung 8 eine zur Aufnahmeöffnung 4 konzentrischen Schweisslippe 9 auf. In die Aufnahmeöffnung 4 ist ein Korrosionsschutzdeckel 11 aus dem gleichen Werkstoff eingesetzt und über eine Gegenschweisslippe 12 mit der Schweisslippe 9 der Hülle 8 verbunden. Die äussere Schicht 13 des Behältergrundkörpers besteht aus Gusseisen mit Kugelgraphit (GGG 40).A
Ein aus sphärolithischem Gusseisen bestehenderabschirmdeckel 14 ist mit dem äusseren Gusskörper 13 verschraubt.A
Die jeweilige topfförmige Gussschicht ist beim Herstellungsvorgang der nächstäusseren Schicht als Formteil in die Giessform eingesetzt worden. Nach dem jeweiligen Eingiessen der Werkstoffschmelze der nächsten Schicht verbindet sich die Oberfläche mit der vergossenen Schicht. Die drei Schichten des Behältergrundkörpers 3 sind somit fest miteinander verbunden.The respective cup-shaped casting layer was inserted as a molded part in the casting mold during the manufacturing process of the next outer layer. After the material melt of the next layer has been poured in, the surface connects to the cast layer. The three layers of the
Der Korrosionsschutzdeckel 11 ist aus dem gleichen Werkstoff wie die Korrosionsschutzschicht 8. Eine nachträgliche Wärmebehandlung des Behälters nach dem Deckelverschweissen ist daher nicht notwendig.The
Bei der in der Fig. 2 gezeigten Ausführungsform des Behälters ist die innere Schicht 21 aus einem gezogenen Stahlrohr gebildet, das am der Aufnahmeöffnung 4 gegenüberliegenden Ende durch eine kreisförmige Stahlplatte 23 verschweisst ist. Gezogene Stahlrohre haben eine höhere mechanische Festigkeit als entsprechende Gusskörper. Daher kann die innere Schicht 21 des Behältergrundkörpers 3 dünner ausgebildet werden. Das hat zur Folge, dass die mittlere Korrosionsschutzschicht 8 auf einem kleineren Durchmesser liegt.In the embodiment of the container shown in FIG. 2, the
Claims (2)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19823214880 DE3214880A1 (en) | 1982-04-22 | 1982-04-22 | CONTAINER TO RECEIVE RADIOACTIVE SUBSTANCES |
| DE3214880 | 1982-04-22 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| EP0092679A1 EP0092679A1 (en) | 1983-11-02 |
| EP0092679B1 true EP0092679B1 (en) | 1986-01-29 |
Family
ID=6161574
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP83102908A Expired EP0092679B1 (en) | 1982-04-22 | 1983-03-24 | Container for radioactive wastes |
Country Status (7)
| Country | Link |
|---|---|
| US (1) | US4569818A (en) |
| EP (1) | EP0092679B1 (en) |
| JP (1) | JPS58190798A (en) |
| BR (1) | BR8302011A (en) |
| CA (1) | CA1189203A (en) |
| DE (2) | DE3214880A1 (en) |
| ES (1) | ES522024A0 (en) |
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|---|---|---|---|---|
| JPS60158399A (en) * | 1984-01-09 | 1985-08-19 | ウエスチングハウス エレクトリック コ−ポレ−ション | Vessel made of cast iron |
| DE3445124C1 (en) * | 1984-12-11 | 1986-01-23 | Nukem Gmbh, 6450 Hanau | Lining for boreholes in salt domes |
| 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 |
| US4700863A (en) * | 1986-01-09 | 1987-10-20 | The United States Of America As Represented By The United States Department Of Energy | Seal welded cast iron nuclear waste container |
| DE3610862A1 (en) * | 1986-04-01 | 1987-10-08 | Kernforschungsz Karlsruhe | LENGTH CYLINDRICAL CONTAINER FOR THE FINAL STORAGE OF ONE OR MORE CHILLERS FILLED WITH HIGH RADIOACTIVE WASTE |
| DE3632270A1 (en) * | 1986-09-23 | 1988-04-07 | Wiederaufarbeitung Von Kernbre | METHOD AND DEVICE FOR LOADING AND SEALING A DOUBLE CONTAINER SYSTEM FOR THE STORAGE OF RADIOACTIVE MATERIAL AND LOCKING FOR THE DOUBLE CONTAINER SYSTEM |
| US4754894A (en) * | 1987-05-11 | 1988-07-05 | Centre Foundry & Machine Co. | Waste container |
| US5337917A (en) * | 1991-10-21 | 1994-08-16 | Sandia Corporation | Crash resistant container |
| DE4204527C2 (en) * | 1992-02-15 | 1993-12-23 | Siempelkamp Gmbh & Co | Method of making a shielded transport container for irradiated nuclear reactor fuel elements |
| AT398012B (en) * | 1992-07-13 | 1994-08-25 | Theodor Haering | CONTAINER FOR THE TRANSPORT AND FINAL STORAGE OF ATOMIC FUEL TUBES |
| US5442186A (en) * | 1993-12-07 | 1995-08-15 | Troxler Electronic Laboratories, Inc. | Radioactive source re-encapsulation including scored outer jacket |
| US6891179B2 (en) * | 2002-10-25 | 2005-05-10 | Agilent Technologies, Inc. | Iron ore composite material and method for manufacturing radiation shielding enclosure |
| NO20044434D0 (en) * | 2004-10-19 | 2004-10-19 | Nuclear Prot Products As | Long-term storage container and process for making it |
| NO336476B1 (en) | 2009-03-11 | 2015-09-07 | Mezonic As | A method and plant for producing a storage container for storing nuclear radiation material |
| CN102708933B (en) * | 2012-06-06 | 2014-09-03 | 清华大学 | Spent fuel storage shaft shielding well lid and lifting device thereof |
| US10020084B2 (en) | 2013-03-14 | 2018-07-10 | Energysolutions, Llc | System and method for processing spent nuclear fuel |
| CN111739672B (en) * | 2020-05-13 | 2023-12-22 | 中国核电工程有限公司 | Structure for reducing tritium permeation rate |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0083024A1 (en) * | 1981-12-21 | 1983-07-06 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH | Long-term storage container for irradiated nuclear fuel elements |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1005196A (en) * | 1962-07-27 | 1965-09-22 | Nuclear Power Plant Co Ltd | Radiation shielding material |
| GB1073751A (en) * | 1964-03-13 | 1967-06-28 | Atomic Energy Authority Uk | Improvements in or relating to containers for transporting radioactive and/or fissile materials |
| FR2258692A1 (en) * | 1974-01-23 | 1975-08-18 | Transnucleaire | Package for nuclear fuel elements - particularly for transport prior to reprocessing |
| US4031921A (en) * | 1975-09-09 | 1977-06-28 | The United States Of America As Represented By The United States Energy Research And Development Administration | Hydrogen-isotope permeation barrier |
| DE2740933C2 (en) * | 1977-09-10 | 1982-11-25 | GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen | Transport and storage containers for radioactive substances, especially irradiated nuclear reactor fuel elements |
| DE7737499U1 (en) * | 1977-12-09 | 1978-05-24 | Steag Kernenergie Gmbh, 4300 Essen | SHIELD TRANSPORT AND / OR SHIELD STORAGE CONTAINER FOR RADIOACTIVE WASTE |
| DE7819282U1 (en) * | 1978-06-28 | 1978-10-12 | Transnuklear Gmbh, 6450 Hanau | SHIELDING CONTAINER FOR THE TRANSPORT AND STORAGE OF IRRADIATED FUEL ELEMENTS OR OTHER BIO-HARMFUL WASTE |
| DE2942092C2 (en) * | 1979-10-18 | 1985-01-17 | Steag Kernenergie Gmbh, 4300 Essen | Final storage containers for radioactive waste, in particular irradiated nuclear reactor fuel elements |
-
1982
- 1982-04-22 DE DE19823214880 patent/DE3214880A1/en not_active Withdrawn
-
1983
- 1983-03-24 DE DE8383102908T patent/DE3361958D1/en not_active Expired
- 1983-03-24 EP EP83102908A patent/EP0092679B1/en not_active Expired
- 1983-04-18 JP JP58067143A patent/JPS58190798A/en active Granted
- 1983-04-19 US US06/486,449 patent/US4569818A/en not_active Expired - Fee Related
- 1983-04-19 BR BR8302011A patent/BR8302011A/en not_active IP Right Cessation
- 1983-04-21 CA CA000426493A patent/CA1189203A/en not_active Expired
- 1983-04-22 ES ES522024A patent/ES522024A0/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0083024A1 (en) * | 1981-12-21 | 1983-07-06 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH | Long-term storage container for irradiated nuclear fuel elements |
Also Published As
| Publication number | Publication date |
|---|---|
| DE3361958D1 (en) | 1986-03-13 |
| ES8405189A1 (en) | 1984-05-16 |
| EP0092679A1 (en) | 1983-11-02 |
| CA1189203A (en) | 1985-06-18 |
| DE3214880A1 (en) | 1983-10-27 |
| JPS58190798A (en) | 1983-11-07 |
| ES522024A0 (en) | 1984-05-16 |
| BR8302011A (en) | 1983-12-27 |
| US4569818A (en) | 1986-02-11 |
| JPH0437398B2 (en) | 1992-06-19 |
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