EP0092679A1 - Container for radioactive wastes - Google Patents

Container for radioactive wastes Download PDF

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Publication number
EP0092679A1
EP0092679A1 EP83102908A EP83102908A EP0092679A1 EP 0092679 A1 EP0092679 A1 EP 0092679A1 EP 83102908 A EP83102908 A EP 83102908A EP 83102908 A EP83102908 A EP 83102908A EP 0092679 A1 EP0092679 A1 EP 0092679A1
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EP
European Patent Office
Prior art keywords
container
corrosion protection
layer
protection layer
container body
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EP83102908A
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German (de)
French (fr)
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EP0092679B1 (en
Inventor
Franz-Wolfgang Dipl.-Ing. Popp
Kurt Dipl.-Ing. Feuring
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Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Original Assignee
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Nukem GmbH
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Publication of EP0092679A1 publication Critical patent/EP0092679A1/en
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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-alloyed 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 cover sealing system, and adequate shielding of the. Ensure radioactivity.
  • the transport containers must have sufficient mechanical strength that can withstand accident conditions. Furthermore, the transport container must 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; burned nuclear reactor fuel elements are packed in special repositories and placed in geological formations for safe disposal.
  • the repository containers must have certain repository properties. They have to be mechanically stable, corrosion-proof and tightly sealed.
  • the main body of the repository container is therefore made of steel or cast iron to ensure the mechanical stability of the container. It is preferable to use spheroidal graphite cast iron (GGG 40) for the thick-walled container body, since spheroidal cast iron is characterized by particularly high strength and toughness.
  • This corrosion-resistant protective layer can consist of ceramic, graphite or other materials.
  • 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 austenitic spheroidal graphite cast material cast around the inner layer.
  • the receiving opening of the container is closed by a sealing cover welded to the outer layer.
  • 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 has for its object to design a container of the type described in such a way that it can be used not only for final storage, but also for longer surface storage and for the transport of the irradiated fuel elements, the amount of material of the corrosion protection layer should be kept as low as possible.
  • the container 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 anti-corrosion 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 in 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.
  • 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, it being possible for each casting position to be checked individually.
  • the Brennense.aufensede the container not shown (F ig. 1) comprises a thick-walled container body 3, which is constructed from 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 layer covering 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 is 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 used 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. 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. As a result, the middle corrosion protection layer 8 is on a smaller diameter.

Abstract

Die Erfindung betrifft einen Behälter zur Aufnahme von radioaktiven Stoffen, insbesondere bestrahlte Kernreaktorbrennelemente, bei dem der Behältergrundkörper mehrschichtig aufgebaut ist. Die innere Schicht des Behältergrundkörpers besteht aus einem mechanisch stabilen, billigen metallischen Werkstoff und wird von einer Korrosionsschutzschicht aus hochlegiertem austenitischen Gußwerkstoff mit Kugelgraphit umgeben. Die Aufnahmeöffnung des Behältergrundkörpers ist durch einen mit der Korrosionsschutzschicht verschweißten Verschlußdeckel verschlossen. Dieser Behälter soll nicht nur zur Endlagerung sondern auch zur längeren Oberflächenlagerung und zum Transport der bestrahlten Brennelemente einsetzbar sein. Dabei soll die Werkstoffmenge der Korrosionsschutzschicht möglichst niedrig gehalten werden. Um dieses zu erreichen, weist der Behältergrundkörper eine um die Korrosionsschutzshicht gegossene äußere Schicht aus Gußeisen mit Kugelgraphit auf. Diese äußere Schicht wird in ihrer Dicke entsprechend den Anforderungen bezüglich der Abschirmwirkung gewählt.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 of the container body consists of a mechanically stable, inexpensive metallic material and is surrounded by a corrosion protection layer made of high-alloy austenitic cast iron with nodular graphite. The receiving opening of the container body is closed by a sealing cover welded to the corrosion protection layer. This container should not only be used for final storage but also for longer surface storage and for the transport of the irradiated fuel elements. The amount of material in the corrosion protection layer should be kept as low as possible. In order to achieve this, the container body has an outer layer of cast iron with spheroidal graphite cast around the corrosion protection layer. The thickness of this outer layer is chosen according to the requirements regarding the shielding effect.

Description

Die Erfindung betrifft einen Behälter-zur Aufnahme von radioaktiven Stoffen, insbesondere bestrahlte Kernreaktorbrennelemente, 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 des 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-alloyed 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 er- reicht 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 cover sealing system, and adequate shielding of the. Ensure radioactivity. The transport containers must have sufficient mechanical strength that can withstand accident conditions. Furthermore, the transport container must 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 Zwischenlager verbracht, wo sie bis zu einer späteren Wiederaufarbeitung der abgebrannten Kernbrennelemente oder einer Langzeitlagerung, der sogenannten direkten Endlagerung, aufbewahrt werden sollen. Die Transportbehälter müssen dann wieder geöffnet werden. Im Falle der direkten Endlagerung müssen die ab- ; gebrannten 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; burned nuclear reactor fuel elements are packed in special repositories and placed in geological formations for safe disposal.

Die Endlagerbehälter müssen bestimmte Endlagereigenschaften aufweisen. Sie müssen mechanisch stabil, korrosionsfest und dicht verschlossen sein. Der Behältergrundkörper 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 repository properties. They have to be mechanically stable, corrosion-proof and tightly sealed. The main body of the repository container is therefore made of steel or cast iron to ensure the mechanical stability of the container. It is preferable to use spheroidal graphite cast iron (GGG 40) for the thick-walled container body, since spheroidal cast iron is characterized by 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 nodular 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 (P 31 50 663.1) 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. 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.In a not previously published patent application (P 31 50 663.1) 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 austenitic spheroidal graphite cast material cast around the inner layer. The receiving opening of the container is closed by a sealing cover welded to the outer layer. 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 is sufficient for final storage to always have a certain thickness, 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 die Aufgabe 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 has for its object to design a container of the type described in such a way that it can be used not only for final storage, but also for longer surface storage and for the transport of the irradiated fuel elements, the amount of material of the corrosion protection layer should be kept as low as possible.

Die Aufgabe wird erfindungsgemäß dadurch gelöst, daß der Behältergrundkörper eine um die Korrosionsschutzschicht gegossene äußere Schicht aus Gußeisen mit Kugelgraphit aufweist.The object is achieved in that the container body has an outer layer of cast iron with spheroidal graphite cast around the corrosion protection layer.

Es ist nun möglich, die Korrosionsschutzschicht des Behältergrundkörpers 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 according to the required shielding effect. The outer layer is cast in a mold around the anti-corrosion 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 in 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 Durchmesser der inneren Schicht. Das hat vorteilhaft zur 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 is also 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 des erfindungsgemäßen 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, it being possible for each casting position to be checked individually.

Anhand der Zeichnung werden nachstehend zwei Ausführungsbeispiele der Erfindung näher erläutert. Es zeigt

  • Fig. 1 einen dreischichtigen gegossenen Brennelementbehälter im Längsschnitt,
  • Fig. 2 eine Ausführungsform eines dreischichtigen Brennelementbehälters, bei der die innere Schicht aus einem gezogenen Stahlrohr besteht.
Two exemplary embodiments of the invention are explained in more detail below with reference to the drawing. It shows
  • 1 shows a three-layer cast fuel element container in longitudinal section,
  • F ig. 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 Brennelemente.aufnehmende the container, not shown (F ig. 1) comprises a thick-walled container body 3, which is constructed from three layers. The container body 3 is cylindrical and open at its front end.

Dadurch wird eine Aufnahmeöffnung 4 zum Beladen mit den hier nicht gezeigten Brennelementen gebildet.This forms a receiving opening 4 for loading with the fuel elements, not shown here.

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 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.

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 konzentrische 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 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"). At its open end, the corrosion protection layer covering 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 is 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).

Ein aus sphärolithischem Gußeisen bestehender Abschirmdeckel 14 ist mit dem äußeren Gußkörper 13 verschraubt.A shielding cover 14 made of spherulitic cast iron is screwed to the outer cast body 13.

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 used 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.

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 corrosion protection cover 11 is made of the same material as the corrosion protection layer 8. Subsequent heat treatment of the container after the cover is welded is therefore not necessary.

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 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. As a result, the middle corrosion protection layer 8 is on a smaller diameter.

Claims (2)

1. Behälter zur Aufnahme von radioaktiven Stoffen, insbesondere bestrahlte Kernreaktorbrennelemente, 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 des Behältergrundkörpers durch einen mit der Korrosionsschutzschicht verschweißten Verschlußdeckel verschlossen ist, dadurch gekennzeichnet , , daß der Behältergrundkörper (3) eine um die Korrosionsschutzschicht (8) gegossene, äußere Schicht (13) aus Gußeisen mit Kugelgraphit aufweist.1.container for holding radioactive substances, in particular irradiated nuclear reactor fuel elements, in which the basic container body has a multilayer structure, the inner layer being made of a mechanically stable, cheap metallic material and the adjacent layer being a corrosion protection layer made of a high-alloy austenitic cast around the inner layer Cast material with spheroidal graphite, and in which the receiving opening of the container base body is closed by a sealing cover welded to the corrosion protection layer, characterized in that the container base body (3) has an outer layer (13) cast from spheroidal graphite cast iron around the corrosion protection layer (8) having. 2. Behälter nach Anspruch 1, dadurch gekennzeichnet, daß die innere Schicht aus einem gezogenen Stahlrohr (21) besteht.2. Container according to claim 1, characterized in that the inner layer consists of a drawn steel tube (21).
EP83102908A 1982-04-22 1983-03-24 Container for radioactive wastes Expired EP0092679B1 (en)

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 true EP0092679A1 (en) 1983-11-02
EP0092679B1 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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EP0148776A1 (en) * 1984-01-09 1985-07-17 Westinghouse Electric Corporation Cast iron containers
GB2171632A (en) * 1984-12-22 1986-09-03 Kernforschungsz Karlsruhe Containment with long-time corrosion resistant cover for sealed containers with highly radio-active 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
EP0244599A1 (en) * 1986-04-01 1987-11-11 Kernforschungszentrum Karlsruhe Gmbh Cylindrical container for the final storage of one or more radio-active waste-filled flasks
WO1994001871A1 (en) * 1992-07-13 1994-01-20 HÄRING, Ursel Container for the transport and terminal storage of nuclear-fuel rods

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DE3445124C1 (en) * 1984-12-11 1986-01-23 Nukem Gmbh, 6450 Hanau Lining for boreholes in salt domes
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
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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DE3150663A1 (en) * 1981-12-21 1983-06-30 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover CONTAINER FOR LONG-TERM STORAGE OF IRRADIATED NUCLEAR REACTOR FUEL ELEMENTS

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GB1005196A (en) * 1962-07-27 1965-09-22 Nuclear Power Plant Co Ltd Radiation shielding material
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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
DE2740933B1 (en) * 1977-09-10 1979-01-18 Rheinisch Westfaelisches Elek Transport or storage container for radioactive materials, in particular irradiated nuclear reactor fuel elements
GB2009657A (en) * 1977-12-09 1979-06-20 Steag Kernenergie Gmbh Shielded transport or storage container for radioactive wastes
GB2024694A (en) * 1978-06-28 1980-01-16 Transnuklear Gmbh Radioactive material enclosures
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 (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0148776A1 (en) * 1984-01-09 1985-07-17 Westinghouse Electric Corporation Cast iron containers
GB2171632A (en) * 1984-12-22 1986-09-03 Kernforschungsz Karlsruhe Containment with long-time corrosion resistant cover for sealed containers with highly radio-active content
GB2171632B (en) * 1984-12-22 1989-06-07 Kernforschungsz Karlsruhe Long term corrosion-resistant covering structure for sealed containers having a highly 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
EP0244599A1 (en) * 1986-04-01 1987-11-11 Kernforschungszentrum Karlsruhe Gmbh Cylindrical container for the final storage of one or more radio-active waste-filled flasks
WO1994001871A1 (en) * 1992-07-13 1994-01-20 HÄRING, Ursel Container for the transport and terminal storage of nuclear-fuel rods

Also Published As

Publication number Publication date
US4569818A (en) 1986-02-11
JPS58190798A (en) 1983-11-07
ES8405189A1 (en) 1984-05-16
BR8302011A (en) 1983-12-27
EP0092679B1 (en) 1986-01-29
CA1189203A (en) 1985-06-18
JPH0437398B2 (en) 1992-06-19
DE3361958D1 (en) 1986-03-13
DE3214880A1 (en) 1983-10-27
ES522024A0 (en) 1984-05-16

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