EP0143212B1 - Container for transporting and storing radioactive materials - Google Patents
Container for transporting and storing radioactive materials Download PDFInfo
- Publication number
- EP0143212B1 EP0143212B1 EP19840110456 EP84110456A EP0143212B1 EP 0143212 B1 EP0143212 B1 EP 0143212B1 EP 19840110456 EP19840110456 EP 19840110456 EP 84110456 A EP84110456 A EP 84110456A EP 0143212 B1 EP0143212 B1 EP 0143212B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- transport
- lid
- storage container
- container
- concrete
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
- 239000012857 radioactive material Substances 0.000 title claims description 13
- 238000003860 storage Methods 0.000 claims description 30
- 239000011150 reinforced concrete Substances 0.000 claims description 19
- 229910000831 Steel Inorganic materials 0.000 claims description 17
- 239000010959 steel Substances 0.000 claims description 17
- 239000004567 concrete Substances 0.000 claims description 15
- 238000003466 welding Methods 0.000 claims description 4
- 230000002787 reinforcement Effects 0.000 claims description 2
- 239000002184 metal Substances 0.000 claims 2
- 238000009415 formwork Methods 0.000 description 25
- 238000004519 manufacturing process Methods 0.000 description 3
- 230000005855 radiation Effects 0.000 description 2
- 230000035939 shock Effects 0.000 description 2
- 229920003319 Araldite® Polymers 0.000 description 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 238000005266 casting Methods 0.000 description 1
- 210000000078 claw Anatomy 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000002035 prolonged effect Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000003566 sealing material Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 210000002268 wool Anatomy 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
Definitions
- the invention relates to a transport and storage container for radioactive material which is introduced into steel cans in the interior of a container made of reinforced concrete, which is surrounded on the outside and in the interior by a jacket and can be closed with a covered cover also made of reinforced concrete .
- Reinforced concrete transport containers for the transport of radioactive materials are known.
- the required shielding of the radiation emanating from the radioactive material can be ensured by reinforced concrete.
- the reinforced concrete filling is completely surrounded by a jacket. This increases the desired impact resistance of the transport container.
- the transport container is also intended to serve storage containers for intermediate or final storage of the radioactive material introduced into the container, a container which can be produced at low cost is required.
- the object of the invention is to provide a transport and storage container made of reinforced concrete, the production costs of which are low.
- This object is achieved according to the invention in a container of the type mentioned by the features specified in claim 1.
- the formwork for the reinforced concrete filling is advantageously the formwork required for pouring with concrete, for which sheet steel is used as the lost formwork.
- the outer formwork dominates the filled reinforced concrete, the free surface of which serves as a support surface for the lid, which can be inserted into the outer formwork of the container.
- the production of the transport container thus requires little effort.
- a filling can be used which is made of sheet steel and which can be welded to the outer formwork and to the cover shell.
- a closure can be placed on the lid, which can be welded to the outer formwork. If the transport and storage container is to be opened again, for example after the radioactive material has been stored temporarily, the closure can be opened without damaging the lid.
- metallic soft seals for example made of lead, are used between the contact surfaces of the container and lid, which adapt well to the concrete structure of the contact surfaces.
- the contact surfaces preferably have exposed concrete quality.
- the drawing shows a cylindrical transport and storage container, the interior 1 of which is provided for the use of gas-tightly closed steel cans 2 (leakage rate? 10- 4 mbar- .1 .sec "') which contain radioactive material, for example fuel elements of a high-temperature reactor, in which the nuclear fuels are embedded in graphite
- the steel cans 2 are made of stainless steel.
- Reinforced concrete is used for radiation shielding in the transport and storage container.
- concrete of quality class B 25 K 3 with a density * 2.5 g / cm 3 according to DIN 1045, depending on the technical requirements, reinforced concrete of higher density can also be used.
- the interior 1 is thus surrounded by walls 3 made of reinforced concrete, the reinforcement 3a of which is indicated in FIG. 1.
- the floor 3b is reinforced with fine mesh.
- the outer and inner formwork 4, 5 is used as the outer jacket of the transport and storage container and as a jacket for lining the interior 2, which is necessary for pouring the concrete when manufacturing the transport and storage container.
- Sheet steel is used for the formwork 4, 5. The steel sheet can be selected to different degrees.
- the steel sheet - in a modification of the exemplary embodiment - is dimensioned thicker for the inner formwork 5 than the steel sheet for the outer formwork 4.
- the formworks are part of the transport and storage container and serve as protection against Shock loads. In addition, they serve to better decontaminate the container surfaces.
- the outer formwork 4 of the transport container projects beyond a bearing surface 6 formed by the filled concrete in the container for a cover 7, with which the interior 1 is closed.
- the Cover 7 is also made of reinforced concrete, the quality of which corresponds to the reinforced concrete quality of the wall 3, and is covered with a jacket 8, for which the formwork is used in the same way as for the container, which is necessary for the casting of the reinforced concrete. Sheet steel is used for the formwork.
- the cover 7 can be used in such a way that between the upper edge 9 of the outer formwork 4 and the upper surface 10 of the cover shell, which in the exemplary embodiment lies in one plane with the upper edge 9 of the outer formwork 4 , An intermediate space 11 remains, which can be closed gas-tight by welding.
- a steel ring is also inserted into the intermediate space as the filling 11a, which is welded to the outer formwork 4 and the casing 8 of the cover 7. The welding serves as a gas-tight seal of the transport and storage container when the radioactive material is introduced into an intermediate or final storage facility.
- cover 7 can also be covered with a cover plate 7a, which is welded to the outer formwork 4.
- the cover plate 7a can, for example, be mechanically separated without damaging the cover 7 in the event that the transport container is to be opened again after being introduced into an interim storage facility.
- the intermediate space 11 can be clogged with lead wool and sealed with sealing material.
- the aforementioned closures can be removed again without destroying the casing of the container and lid.
- the cover 7 After being placed on the support surface 6, the cover 7 is fastened in the transport and storage container by means of suitable screws 13, which can be screwed into the bushings 14 in the wall 3. Between the support surface 6 of the wall 3 and the support surface 12 of the lid 7, a soft seal 15 made of lead is inserted, which adapts to the concrete structure of the support surfaces under the contact pressure of the screws 13.
- the contact surfaces 6, 12 have fair-faced concrete quality and thus form relatively smooth concrete surfaces. Steel plates covering the concrete can also be used as contact surfaces for the soft seal 15.
- the cover 7 can be held via laterally guided bolts 13a.
- the bolts 13a can also be screwed to the cover 7. These screws and also the screws 13 can be sealed so that the safety requirements during the transport and storage of radioactive material can be taken into account.
- a lifting star 17 which can be screwed onto the cover 7 and has crane eyelets 18, is provided as a lifting tool, which allows the cover 7 to be safely lifted off even in the case of a low room height.
- wire rope pieces between the crane eye 18 and the crane hook are not required.
- the crane hook can engage directly in the crane eye 18. After the transport and storage container has been set down, the support star 17 is released from the cover 7 again.
- the cover 7 is flat on its underside with the support surface 12.
- the underside can also have a centering which rests on the inner formwork 5 and protrudes a little into the interior 1.
- claws 19 and support pins 20 attached in the center of gravity axis are provided on the outer formwork.
- the container can be rotated about its axis.
- the transport and storage container has a very cost-effective construction and still meets the high requirements for the safety of transport and storage containers for radioactive material.
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Environmental & Geological Engineering (AREA)
- Filling Or Discharging Of Gas Storage Vessels (AREA)
- Packages (AREA)
Description
Die Erfindung bezieht sich auf einen Transport-und Lagerbehälter für radioaktives Material, das in Stahlkannen im Innenraum eines aus Stahlbeton bestehenden Behälters eingebracht ist, der nach außen und im Innenraum von einem Mantel umgeben ist und mit einem ebenfalls aus Stahlbeton bestehenden, ummantelten Deckel verschließbar ist.The invention relates to a transport and storage container for radioactive material which is introduced into steel cans in the interior of a container made of reinforced concrete, which is surrounded on the outside and in the interior by a jacket and can be closed with a covered cover also made of reinforced concrete .
Transportbehälter aus Stahlbeton zum Transport radioaktiven Materials sind bekannt. Durch Stahlbeton läßt sich die erforderliche Abschirmung der Strahlung gewährleisten, die vom radioaktiven Material ausgeht. Zum Schutz der Betonmasse wird die Stahlbetonfüllung vollständig mit einem Mantel umgebenen. Dies erhöht die erwünschte Stoßfestigkeit des Transportbehälters.Reinforced concrete transport containers for the transport of radioactive materials are known. The required shielding of the radiation emanating from the radioactive material can be ensured by reinforced concrete. To protect the concrete mass, the reinforced concrete filling is completely surrounded by a jacket. This increases the desired impact resistance of the transport container.
Soll der Transportbehälter zugleich Lagerbehälter für eine Zwischen- oder Endlagerung des in den Behälter eingebrachten radioaktiven Materials dienen, so ist ein mit niedrigen Kosten herstellbarer Behälter erforderlich.If the transport container is also intended to serve storage containers for intermediate or final storage of the radioactive material introduced into the container, a container which can be produced at low cost is required.
Aufgabe der Erfindung ist es, einen Transport-und Lagerbehälter aus Stahlbeton zu schaffen, dessen Herstellungskosten niedrig sind. Dies Aufgabe wird gemäß der Erfindung bei einem Behälter der eingangs erwähnten Art durch die in Patentanspruch 1 angegebenen Merkmale gelöst. Als Mantel für die Stahlbetonfüllung dient in vorteilhafter Weise die für den Abguß mit Beton notwendige Schalung, für die als verlorene Schalung Stahlblech verwendet wird. Die äußere Schalung überragt den abgefüllten Stahlbeton, dessen freie Oberfläche als Auflagefläche für den Deckel dient, der in die äußere Schalung des Behälters einsetzbar ist. Die Herstellung des Transportbehälters erfordert somit nur geringen Aufwand. Darüberhinaus besteht zwischen Oberkante der äußeren Schalung und Deckelmanteloberkante ein Zwischenraum, der verschweißbar ist, was den Transportbehält zugleich als gasdicht verschließbaren Lagerbehälter auszeichnet.The object of the invention is to provide a transport and storage container made of reinforced concrete, the production costs of which are low. This object is achieved according to the invention in a container of the type mentioned by the features specified in claim 1. The formwork for the reinforced concrete filling is advantageously the formwork required for pouring with concrete, for which sheet steel is used as the lost formwork. The outer formwork dominates the filled reinforced concrete, the free surface of which serves as a support surface for the lid, which can be inserted into the outer formwork of the container. The production of the transport container thus requires little effort. In addition, there is an intermediate space between the upper edge of the outer formwork and the upper edge of the casing, which can be welded, which at the same time characterizes the transport container as a gas-tight lockable storage container.
Weitere Ausgestaltungen der Erfindung sind in Patentansprüchen 2 bis 7 angegeben.Further refinements of the invention are specified in
So ist zur günstigen Verschweißung im Zwischenraum zwischen Oberkante der äußeren Schalung und Deckelmanteloberkante eine Füllung einsetzbar, die aus Stahlblech besteht und die mit der äußeren Schalung und mit dem Deckelmantel verschweißbar ist. Alternativ dazu kann auf dem Deckel ein Verschluß aufgesetzt werden, der mit der äußeren Schalung verschweißbar ist. Soll der Transport- und Lagerbehälter beispielsweise nach einer Zwischenlagerung des radiaktiven Materials wieder geöffnet werden, so läßt sich der Verschluß öffnen, ohne daß de Deckel beschädigt wird.For cheap welding in the space between the upper edge of the outer formwork and the upper edge of the cover shell, a filling can be used which is made of sheet steel and which can be welded to the outer formwork and to the cover shell. Alternatively, a closure can be placed on the lid, which can be welded to the outer formwork. If the transport and storage container is to be opened again, for example after the radioactive material has been stored temporarily, the closure can be opened without damaging the lid.
Zur Abdichtung des Transportbehälters werden zwischen den Auflageflächen von Behälter und Deckel metallische Weichdichtungen, beispielsweise aus Blei, eingesetzt, die sich der Betonstruktur der Auflageflächen gut anpassen. Zur Ausbildung glatter Dichtflächen weisen die Auflageflächen bevorzugt Sichtbetonqualität auf.To seal the transport container, metallic soft seals, for example made of lead, are used between the contact surfaces of the container and lid, which adapt well to the concrete structure of the contact surfaces. To form smooth sealing surfaces, the contact surfaces preferably have exposed concrete quality.
Um den Deckel in den vom äußeren Mantel umschlossenen Innenraum auf die Auflagefläche des Stahlbetons im Behälter ungehindert auflegen zu können, sind im Deckel zur Befestigung von Hebewerkzeugen Gewindebuchsen eingelassen, die von der Deckeloberseite her zugänglich sind. Der Beton von Deckel und Boden des Behälters ist engmaschig bewehrt. Dies ermöglicht es, als äußeren Mantel verhältnissmäßig dünne Stahlbleche zu verwenden, ohne daß einer Stoßbelastung des Transportbehälters der Innenraum beeinträchtigt wird, der das radioaktive Material enthält.In order to be able to place the lid unhindered in the interior enclosed by the outer casing on the support surface of the reinforced concrete in the container, threaded bushings are embedded in the lid for fastening lifting tools, which are accessible from the top of the lid. The concrete of the lid and bottom of the container is reinforced with fine mesh. This makes it possible to use relatively thin steel sheets as the outer jacket without the interior containing the radioactive material being impacted by a shock load on the transport container.
Die Erfindung wird im folgenden anhand eines Ausführungsbeispiels, das in der Zeichnung schematisch wiedergegeben ist, näher erläutert.The invention is explained in more detail below using an exemplary embodiment which is shown schematically in the drawing.
Es zeigen im einzelnen:
- Fig. 1 eine Seitenansicht eines Transportbehälters mit Halbschnitt nach Schnittlinie I/I nach Fig. 2;
- Fig. 2 einen Querschnitt des Transportbehälters gemäß Schnittlinie 11/11 nach Fig. 1;
- Fig. 3 eine Aufsicht auf den Deckel des Transportbehälters mit aufgeschraubtem Hebezeug.
- Figure 1 is a side view of a transport container with a half section along section line I / I of FIG. 2.
- FIG. 2 shows a cross section of the transport container according to section line 11/11 according to FIG. 1;
- Fig. 3 is a plan view of the lid of the transport container with the hoist screwed on.
In der Zeichnung ist ein zylindrischer Transport- und Lagerbehälter dargestellt, dessen Innenraum 1 zum Einsatz von gasdicht verschlossenen Stahlkannen 2 (Leckrate ? 10-4 mbar- .1 .sec"' ) vorgesehen ist, die radioaktives Material enthalten, beispielsweise Brennelemente eines Hochtemperaturreaktors, bei denen die Kernbrennstoffe in Graphit eingebettet sind. Die Stahlkannen 2 bestehen aus Edelstahl.The drawing shows a cylindrical transport and storage container, the interior 1 of which is provided for the use of gas-tightly closed steel cans 2 (leakage rate? 10- 4 mbar- .1 .sec "') which contain radioactive material, for example fuel elements of a high-temperature reactor, in which the nuclear fuels are embedded in graphite The
Beim Transport- und Lagerbehälter wird zur Strahlenabschirmung Stahlbeton verwendet. Im Ausführungsbeispiel Beton der Güteklasse B 25 K3 mit einer Dichte * 2,5 g/cm3 nach DIN 1045, je nach technischer Anforderung ist auch Stahlbeton höherer Dichte einsetzbar. Der Innenraum 1 ist somit von Wänden 3 aus Stahlbeton umgeben, deren Bewehrung 3a in Fig. 1 angedeutet ist. Der Boden 3b ist engmaschig bewehrt. Als äußerer Mantel des Transport- und Lagerbehälters und als Mantel zur Auskleidung des Innenraumes 2 wird die äußere und innere Schalung 4, 5 benutzt, die für das Vergießen des Betons beim Herstellen des Transport- und Lagerbehälters notwendig ist. Für die Schalungen 4, 5 wird Stahlblech eingesetzt. Das Stahlblech kann unterschiedlich stark gewählt werden. Eine Gewichtsersparnis bei gleicher Sicherheit ergibt sich dann, wenn das Stahlblech - in Abänderung des Ausführungsbeispiels - für die innere Schalung 5 dicker bemessen ist, als das Stahlblech für die äußere Schalung 4. Die Schalungen sind Teil des Transport- und Lagerbehälters und dienen als Schutz vor Stoßbelastungen. Darüberhinaus dienen sie einer besseren Dekontaminierbarkeit der Behälteroberflächen. Die äußere Schalung 4 des Transport- behälters überragt eine vom abgefüllten Beton im Behälter gebildete Auflagefläche 6 für einen Deckel 7, mit dem der Innenraum 1 verschlossen wird. Der Deckel 7 besteht ebenfalls aus Stahlbeton, dessen Qualität der Stahlbetonqualität der Wand 3 entspricht, und ist mit einem Mantel 8 überzogen, für den in gleicher Weise wie für den Behälter die Schalung benutzt wird, die für den Abguß des Stahlbetons notwendig ist. Für die Schalung wird Stahlblech benutzt.Reinforced concrete is used for radiation shielding in the transport and storage container. In the exemplary embodiment, concrete of quality class B 25 K 3 with a density * 2.5 g / cm 3 according to DIN 1045, depending on the technical requirements, reinforced concrete of higher density can also be used. The interior 1 is thus surrounded by walls 3 made of reinforced concrete, the reinforcement 3a of which is indicated in FIG. 1. The
In dem die Auflagefläche 6 überragenden Teil der äußeren Schalung 4 des Transport- und Lagerbehälters ist der Deckel 7 so einsetzbar, daß zwischen Oberkante 9 der äußeren Schalung 4 und Deckelmanteloberkante 10, die im Ausführungsbeispiel in einer Ebene mit der Oberkante 9 der äußeren Schalung 4 liegt, ein Zwischenraum 11 verbleibt, der sich durch Verschweißen gasdicht verschließen läßt. Im Ausführungsbeispiel ist in den Zwischenraum als Füllung 11a noch ein Stahlring eingesetzt, der mit der äußeren Schalung 4 und dem Mantel 8 des Deckels 7 verschweißt wird. Die Verschweißung dient als gasdichter Verschluß des Transport- und Lagerbehälters beim Einbringen des radioaktiven Materials in ein Zwischen- oder Endlager. Für einen weiteren Verschluß ist der Deckel 7 noch mit einem Deckelblech 7a abdeckbar, das mit der äußeren Schalung 4 verschweißt wird. Das Deckelblech 7a ist beispielsweise für den Fall, daß der Transportbehälter nach Einbringen in ein Zwischenlager wieder geöffnet werden soll, ohne Beschädigung des Deckels 7 mechanisch abtrennbar.In the part of the outer formwork 4 of the transport and storage container projecting beyond the bearing surface 6, the cover 7 can be used in such a way that between the upper edge 9 of the outer formwork 4 and the upper surface 10 of the cover shell, which in the exemplary embodiment lies in one plane with the upper edge 9 of the outer formwork 4 , An intermediate space 11 remains, which can be closed gas-tight by welding. In the exemplary embodiment, a steel ring is also inserted into the intermediate space as the filling 11a, which is welded to the outer formwork 4 and the casing 8 of the cover 7. The welding serves as a gas-tight seal of the transport and storage container when the radioactive material is introduced into an intermediate or final storage facility. For a further closure, the cover 7 can also be covered with a cover plate 7a, which is welded to the outer formwork 4. The cover plate 7a can, for example, be mechanically separated without damaging the cover 7 in the event that the transport container is to be opened again after being introduced into an interim storage facility.
Falls mit dem Transport- und Lagerbehälter ohne längere Lagerung lediglich ein Transport von radioaktivem Material vorgesehen ist, läßt sich der Zwischenraum 11 mit Bleiwolle verstopfen und mit Dichtmaterial abdichten. Es läßt sich aber auch Stahlkugelschrot einbringen, der mit Araldit vergossen würde. Die vorgenannten Verschlüsse lassen sich ohne Zerstörung der Ummantelung von Behälter und Deckel wieder entfernen.If only transport of radioactive material is provided with the transport and storage container without prolonged storage, the intermediate space 11 can be clogged with lead wool and sealed with sealing material. However, it is also possible to bring in steel shot that would be shed with araldite. The aforementioned closures can be removed again without destroying the casing of the container and lid.
Der Deckel 7 wird nach Absetzen auf der Auflagefläche 6 im Transport- und Lagerbehälter mittels geeigneter Schrauben 13 befestigt, die in Gewindebuchsen 14 in der Wand 3 verschraubbar sind. Zwischen Auflagefläche 6 der Wand 3 und Auflagefläche 12 des Deckels 7 ist eine Weichdichtung 15 aus Blei eingelegt, die sich der Betonstruktur der Auflageflächen unter dem Anpreßdruck der Schrauben 13 anpaßt. Die Auflageflächen 6, 12 weisen Sichtbetonqualität auf und bilden somit verhältnismäßig glatte Betonoberflächen. Als Auflageflächen für die Weichdichtung 15 lassen sich auch den Beton abdeckende Stahlbleche verwenden. Zusätzlich zu den Schrauben 13 oder ersatzweise kann der Deckel 7 über seitlich geführte Bolzen 13a gehalten werden. Alternativ zu der in Fig. 1 wiedergegebenen Befestigung der Bolzen lassen sich die Bolzen 13a am Deckel 7 auch verschrauben. Diese Schrauben und auch die Schrauben 13 sind verplompbar, damit den Sicherheitsanforderungen bei Transport und Lagerung radioaktiven Materials Rechnung getragen werden kann.After being placed on the support surface 6, the cover 7 is fastened in the transport and storage container by means of suitable screws 13, which can be screwed into the
Um den Deckel 7 in die äußere Schalung 4 ungehindert einsetzen zu können, sind im Deckel 7 von der Oberseite des Deckels zugängliche Gewindebuchsen 16 zur Befestigung von Hebewerkzeug eingelassen. Im Ausführungsbeispiel ist als Hebewerkzeung ein auf dem Deckel 7 aufschraubbarer Tragstern 17 mit Kranösen 18 vorgesehen, der ein sicheres Abheben des Dekkels 7 auch bei niedriger Raumhöhe gestattet. Beim Tragstern 17 sind Drahtseilstücke zwischen Kranöse 18 und Kranhaken nicht erforderlich. Der Kranhaken kann direkt in die Kranöse 18 eingreifen. Nach Absetzen des Transport- und Lagerbehälters wird der Tragstern 17 vom Deckel 7 wieder gelöst.In order to be able to insert the cover 7 into the outer formwork 4 unhindered, threaded
Im Ausführungsbeispiel ist der Deckel 7 auf seiner Unterseite mit der Auflagefläche 12 eben gestaltet. Alternativ dazu kann die Unterseite jedoch auch eine an der inneren Schalung 5 anliegende Zentrierung aufweisen, die ein Stück in den Innenraum 1 hineinragt.In the exemplary embodiment, the cover 7 is flat on its underside with the support surface 12. As an alternative to this, however, the underside can also have a centering which rests on the inner formwork 5 and protrudes a little into the interior 1.
Zum Transport und Bewegen des Transport-und Lagerbehälters sind an der äußeren Schalung vier Pratzen 19 und in der Schwerpunktachse angebrachte Tragzapfen 20 vorgesehen. Beim Heben de Behälters an den Tragzapfen 20 laßt sich de Behälter um seine Achse drehen.For the transport and movement of the transport and storage container, four
Der Transport- und Lagerbehälter weist einen sehr kostengünstigen Aufbau auf und erfüllt dennoch die an die Sicherheit von Transport- und Lagerbehältern für radioaktives Material zu stellenden hohen Anforderungen.The transport and storage container has a very cost-effective construction and still meets the high requirements for the safety of transport and storage containers for radioactive material.
Claims (7)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
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DE19833331892 DE3331892C2 (en) | 1983-09-03 | 1983-09-03 | Transport and storage containers for radioactive material |
DE3331892 | 1983-09-03 |
Publications (2)
Publication Number | Publication Date |
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EP0143212A1 EP0143212A1 (en) | 1985-06-05 |
EP0143212B1 true EP0143212B1 (en) | 1990-08-16 |
Family
ID=6208205
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP19840110456 Expired - Lifetime EP0143212B1 (en) | 1983-09-03 | 1984-09-03 | Container for transporting and storing radioactive materials |
Country Status (3)
Country | Link |
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EP (1) | EP0143212B1 (en) |
JP (1) | JPH0664186B2 (en) |
DE (1) | DE3331892C2 (en) |
Families Citing this family (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3534134C1 (en) * | 1985-09-25 | 1987-01-02 | Kernforschungsanlage Juelich | Transport and storage containers for radioactive materials |
DE3535420C1 (en) * | 1985-10-04 | 1986-12-18 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | Transport and storage device for radioactive materials |
DE3635500A1 (en) * | 1986-10-18 | 1988-05-11 | Kernforschungsanlage Juelich | HEAVY CONCRETE FOR THE PRODUCTION OF A CONTAINER FOR RADIOACTIVE MATERIAL |
DE3639653A1 (en) * | 1986-11-29 | 1988-06-23 | Wiederaufarbeitung Von Kernbre | LID LOCK FOR THE EXTERNAL SHIELDING CONTAINER OF A DOUBLE CONTAINER SYSTEM FOR TRANSPORTING AND STORING RADIOACTIVE WASTE |
FR2640410A1 (en) * | 1988-12-12 | 1990-06-15 | Cogema | Storage container for radioactive waste |
FR2648611B2 (en) * | 1988-12-12 | 1994-08-19 | Cogema | STORAGE CONTAINER FOR RADIOACTIVE WASTE |
JPH04304975A (en) * | 1991-04-02 | 1992-10-28 | Hitachi Koki Co Ltd | Speed change gear of motor-driven tool |
ES2070737B1 (en) * | 1993-04-28 | 1998-01-16 | Nacional De Residuos Radiactiv | REINFORCED CONCRETE CONTAINER FOR RECOVERABLE STORAGE OF MEDIUM AND LOW ACTIVITY RADIOACTIVE WASTE. |
US5898747A (en) * | 1997-05-19 | 1999-04-27 | Singh; Krishna P. | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
DE19725922C2 (en) * | 1997-06-19 | 2000-07-20 | Gnb Gmbh | Process for manufacturing a container |
DE19952130C2 (en) * | 1999-10-29 | 2003-04-17 | Nuklear Service Gmbh Gns | Shielding container for the transport and storage of low to medium level radioactive waste |
DE10000844C2 (en) * | 2000-01-12 | 2001-11-29 | Siempelkamp Guss Und Anlagente | Method of anchoring a concrete cover on a concrete container, concrete container and anchor bolt |
FR2807409B1 (en) * | 2000-04-11 | 2002-08-30 | Sogefibre | CONCRETE CONTAINER WITH BOLT LID |
ITMI20111637A1 (en) * | 2011-09-09 | 2013-03-10 | G R M S R L | CONCRETE CONTAINER AND ITS METHOD OF DISPOSAL OF DANGEROUS MATERIALS |
JP5984000B2 (en) * | 2012-07-13 | 2016-09-06 | 清水建設株式会社 | Waste container manufacturing method |
Family Cites Families (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
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 |
US3749917A (en) * | 1971-05-12 | 1973-07-31 | H Kucherer | Device for encapsulating a radioactive resin-water slurry |
IT1016901B (en) * | 1973-05-25 | 1977-06-20 | Cnen | CONTAINER FOR THE TRANSPORT OF FISSILE MATERIAL IN THE SO LIDO AGGLOMERATED STATE OR IN THE FORM OF POWDER |
DE2359114A1 (en) * | 1973-11-27 | 1975-05-28 | Kraftwerk Union Ag | Transport vessel for fuel elements - or other radioactive material with outer thermally insulated protective vessel |
US3982134A (en) * | 1974-03-01 | 1976-09-21 | Housholder William R | Shipping container for nuclear fuels |
DE2738592A1 (en) * | 1977-08-26 | 1979-03-01 | Kraftwerk Union Ag | Fuel element transportation container with two=part closure - comprising inner shielding plug and outer lid with fixing bolts |
DE7737499U1 (en) * | 1977-12-09 | 1978-05-24 | Steag Kernenergie Gmbh, 4300 Essen | SHIELD TRANSPORT AND / OR SHIELD STORAGE CONTAINER FOR RADIOACTIVE WASTE |
DE2817193A1 (en) * | 1978-04-20 | 1979-10-31 | Transnuklear Gmbh | Transport casket for irradiated fuel elements - with webs in concrete filling between inner and outer metal shell |
DE7838526U1 (en) * | 1978-12-27 | 1979-03-29 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | DISPOSABLE CONCRETE CONTAINER FOR RECEIVING BARRELS WITH RADIOACTIVE CONTENT |
JPS5620515A (en) * | 1979-07-30 | 1981-02-26 | Suzuki Nihondou:Kk | Preparation of plaster |
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 |
DE8006393U1 (en) * | 1980-03-08 | 1980-06-04 | Transnuklear Gmbh | Shielding container |
JPS57400U (en) * | 1980-05-30 | 1982-01-05 | ||
DE8017567U1 (en) * | 1980-06-30 | 1980-09-25 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | CONCRETE CONTAINER FOR STORAGE OR TRANSPORTATION OF BARRELS WITH RADIOACTIVE CONTENT |
-
1983
- 1983-09-03 DE DE19833331892 patent/DE3331892C2/en not_active Expired
-
1984
- 1984-09-03 EP EP19840110456 patent/EP0143212B1/en not_active Expired - Lifetime
- 1984-09-03 JP JP59182889A patent/JPH0664186B2/en not_active Expired - Lifetime
Also Published As
Publication number | Publication date |
---|---|
EP0143212A1 (en) | 1985-06-05 |
JPS6091295A (en) | 1985-05-22 |
DE3331892C2 (en) | 1986-01-23 |
JPH0664186B2 (en) | 1994-08-22 |
DE3331892A1 (en) | 1985-04-04 |
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