EP0143212A1 - Container for transporting and storing radioactive materials - Google Patents
Container for transporting and storing radioactive materials Download PDFInfo
- Publication number
- EP0143212A1 EP0143212A1 EP84110456A EP84110456A EP0143212A1 EP 0143212 A1 EP0143212 A1 EP 0143212A1 EP 84110456 A EP84110456 A EP 84110456A EP 84110456 A EP84110456 A EP 84110456A EP 0143212 A1 EP0143212 A1 EP 0143212A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- transport
- cover
- storage container
- container
- reinforced 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.)
- Granted
Links
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 placed in 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 also serve as a storage container for serve an 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 manufacturing costs of which are low.
- 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.
- a filling can be used Steel sheet exists and which can be welded to the outer formwork and to the cover jacket.
- 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 the lid being damaged.
- 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 10 -4 mbar. 1 sec -1 ), which contain radioactive material, for example fuel elements of a high-temperature reactor where 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.
- 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, which is necessary for pouring the concrete in the manufacture of the transport and storage container.
- Sheet steel is used for the formwork 4, 5.
- the steel sheet can be selected to different degrees. A weight saving with the same safety results if 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 support surface 6 formed by the filled concrete in the container for a cover 7, with which the interior 1 is closed.
- the lid 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 , a Gap 11 remains, which can be closed gas-tight by welding.
- a steel ring is 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 rule contact surface 6 of the wall 3 and support surface 12 of the cover 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. 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 the 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 to the center of gravity axis are provided on the outer formwork.
- the container When lifting the container on the support pin 20, 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.
Landscapes
- 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)
Abstract
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 placed in 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 umgeben. 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 als Lagerbehälter für eine Zwischen- oder Endlagerung des in den Behälter eingebrachten radioaktiven Materials dienen, so ist ein mit niedrigen Kosten herstellbarer Behälter erforderlich.Should the transport container also serve as a storage container for serve an 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.The object of the invention is to provide a transport and storage container made of reinforced concrete, the manufacturing costs of which are low.
Diese 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.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 towers above 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, so that the production of the transport container requires only 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 radioaktiven Materials wieder geöffnet werden, so läßt sich der Verschluß öffnen, ohne daß der 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 Steel sheet exists and which can be welded to the outer formwork and to the cover jacket. 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 the lid being damaged.
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 verhältnismäßig dünne Stahlbleche zu verwenden, ohne daß bei 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 jacket on the support surface of the reinforced concrete in the container, threaded bushes 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 impaired when the transport container is subjected to a shock load.
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 II/II 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 II / II 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-1) 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 10 -4 mbar. 1 sec -1 ), which contain radioactive material, for example fuel elements of a high-temperature reactor where the nuclear fuels are embedded in graphite. The
Beim Transport- und Lagerbehälter wird zur Strahlenabschirmung Stahlbeton verwendet.Reinforced concrete is used for radiation shielding in the transport and storage container.
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.In the concrete example 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.
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.The interior 1 is thus surrounded by walls 3 made of reinforced concrete, 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 6 of the outer formwork 4 of the transport and storage container projecting beyond the support surface 6, the
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
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 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
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 Hebewerkzeug ein auf dem Deckel 7 aufschraubbarer Tragstern 17 mit Kranösen 18 vorgesehen, der ein sicheres Abheben des Deckels 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
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
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 des Behälters an den Tragzapfen 20 läßt sich der 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 |
---|---|---|---|
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 |
---|---|
EP0143212A1 true EP0143212A1 (en) | 1985-06-05 |
EP0143212B1 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 |
---|---|
EP (1) | EP0143212B1 (en) |
JP (1) | JPH0664186B2 (en) |
DE (1) | DE3331892C2 (en) |
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0216219A2 (en) * | 1985-09-25 | 1987-04-01 | Forschungszentrum Jülich Gmbh | Cylindrical container |
EP0269896A1 (en) * | 1986-11-29 | 1988-06-08 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH | Lid-locking facility for the outer screening vessel of a duplex-container system for the transport and storage of radioactive waste |
FR2640410A1 (en) * | 1988-12-12 | 1990-06-15 | Cogema | Storage container for radioactive waste |
EP0373997A1 (en) * | 1988-12-12 | 1990-06-20 | Cogema Compagnie Generale Des Matieres Nucleaires | Container for storing radioactive waste |
ES2070737A2 (en) * | 1993-04-28 | 1995-06-01 | Nacional De Residuos Radiactiv | Reinforced-concrete container for the recoverable storage of medium- and low-activity radioactive waste |
DE19725922A1 (en) * | 1997-06-19 | 1998-12-24 | Gnb Gmbh | Process for manufacturing a container and a container itself |
EP1016091A2 (en) * | 1997-05-19 | 2000-07-05 | Holtec International | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
FR2807409A1 (en) * | 2000-04-11 | 2001-10-12 | Sogefibre | Concrete container, e.g., for hazardous radioactive waste has cover bolts inserted through sleeves with thrust surfaces matching those on nuts in rim |
ITMI20111637A1 (en) * | 2011-09-09 | 2013-03-10 | G R M S R L | CONCRETE CONTAINER AND ITS METHOD OF DISPOSAL OF DANGEROUS MATERIALS |
Families Citing this family (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
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 |
JPH04304975A (en) * | 1991-04-02 | 1992-10-28 | Hitachi Koki Co Ltd | Speed change gear of motor-driven tool |
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 |
JP5984000B2 (en) * | 2012-07-13 | 2016-09-06 | 清水建設株式会社 | Waste container manufacturing method |
Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1438347A (en) * | 1964-03-13 | 1966-05-13 | Atomic Energy Authority Uk | Vessels for transporting radioactive and fissile materials |
US3749917A (en) * | 1971-05-12 | 1973-07-31 | H Kucherer | Device for encapsulating a radioactive resin-water slurry |
FR2231079A1 (en) * | 1973-05-25 | 1974-12-20 | Cnen | |
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 |
FR2445590A3 (en) * | 1978-12-27 | 1980-07-25 | Kernforschungsz Karlsruhe | LOST CONCRETE TRANSPORT CONTAINER FOR RECEIVING A FUT WITH RADIOACTIVE CONTENT |
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 |
NL8102952A (en) * | 1980-06-30 | 1982-01-18 | Kernforschungsz Karlsruhe | CONCRETE HOLDER FOR THE STORAGE OR TRANSPORT OF BARRELS WITH RADIOACTIVE CONTENTS. |
Family Cites Families (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
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 |
JPS5620515A (en) * | 1979-07-30 | 1981-02-26 | Suzuki Nihondou:Kk | Preparation of plaster |
DE8006393U1 (en) * | 1980-03-08 | 1980-06-04 | Transnuklear Gmbh | Shielding container |
JPS57400U (en) * | 1980-05-30 | 1982-01-05 |
-
1983
- 1983-09-03 DE DE19833331892 patent/DE3331892C2/en not_active Expired
-
1984
- 1984-09-03 JP JP59182889A patent/JPH0664186B2/en not_active Expired - Lifetime
- 1984-09-03 EP EP19840110456 patent/EP0143212B1/en not_active Expired - Lifetime
Patent Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1438347A (en) * | 1964-03-13 | 1966-05-13 | Atomic Energy Authority Uk | Vessels for transporting radioactive and fissile materials |
US3749917A (en) * | 1971-05-12 | 1973-07-31 | H Kucherer | Device for encapsulating a radioactive resin-water slurry |
FR2231079A1 (en) * | 1973-05-25 | 1974-12-20 | Cnen | |
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 |
FR2445590A3 (en) * | 1978-12-27 | 1980-07-25 | Kernforschungsz Karlsruhe | LOST CONCRETE TRANSPORT CONTAINER FOR RECEIVING A FUT WITH RADIOACTIVE CONTENT |
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 |
NL8102952A (en) * | 1980-06-30 | 1982-01-18 | Kernforschungsz Karlsruhe | CONCRETE HOLDER FOR THE STORAGE OR TRANSPORT OF BARRELS WITH RADIOACTIVE CONTENTS. |
Cited By (13)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0216219A2 (en) * | 1985-09-25 | 1987-04-01 | Forschungszentrum Jülich Gmbh | Cylindrical container |
EP0216219A3 (en) * | 1985-09-25 | 1988-03-02 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Cylindrical container |
EP0269896A1 (en) * | 1986-11-29 | 1988-06-08 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH | Lid-locking facility for the outer screening vessel of a duplex-container system for the transport and storage of radioactive waste |
FR2640410A1 (en) * | 1988-12-12 | 1990-06-15 | Cogema | Storage container for radioactive waste |
EP0373997A1 (en) * | 1988-12-12 | 1990-06-20 | Cogema Compagnie Generale Des Matieres Nucleaires | Container for storing radioactive waste |
FR2648611A2 (en) * | 1988-12-12 | 1990-12-21 | Cogema | STORAGE CONTAINER FOR RADIOACTIVE WASTE |
ES2070737A2 (en) * | 1993-04-28 | 1995-06-01 | Nacional De Residuos Radiactiv | Reinforced-concrete container for the recoverable storage of medium- and low-activity radioactive waste |
EP1016091A2 (en) * | 1997-05-19 | 2000-07-05 | Holtec International | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
EP1016091A4 (en) * | 1997-05-19 | 2002-02-06 | Holtec Internat | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
DE19725922A1 (en) * | 1997-06-19 | 1998-12-24 | Gnb Gmbh | Process for manufacturing a container and a container itself |
DE19725922C2 (en) * | 1997-06-19 | 2000-07-20 | Gnb Gmbh | Process for manufacturing a container |
FR2807409A1 (en) * | 2000-04-11 | 2001-10-12 | Sogefibre | Concrete container, e.g., for hazardous radioactive waste has cover bolts inserted through sleeves with thrust surfaces matching those on nuts in rim |
ITMI20111637A1 (en) * | 2011-09-09 | 2013-03-10 | G R M S R L | CONCRETE CONTAINER AND ITS METHOD OF DISPOSAL OF DANGEROUS MATERIALS |
Also Published As
Publication number | Publication date |
---|---|
EP0143212B1 (en) | 1990-08-16 |
DE3331892A1 (en) | 1985-04-04 |
DE3331892C2 (en) | 1986-01-23 |
JPS6091295A (en) | 1985-05-22 |
JPH0664186B2 (en) | 1994-08-22 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
EP0143212B1 (en) | Container for transporting and storing radioactive materials | |
DE2726335C2 (en) | Container unit for radioactive waste that can be used for final disposal | |
EP0129782B1 (en) | Device for handling and protecting containers for radioactive materials | |
DE2500927A1 (en) | DEVICE FOR HANDLING RADIOACTIVE NUCLEAR FUEL ELEMENTS DURING TRANSPORT OPERATIONS | |
EP1721322A1 (en) | Storage transport system and method for storing and transporting nuclear waste | |
EP0741904B1 (en) | Fuel-element storage and transport rack | |
DE102012101319B4 (en) | Disposal container and method for producing the same | |
DE19610102C1 (en) | Disposal method for reactor components of a nuclear power plant | |
DE3125211A1 (en) | STORAGE CONTAINER AND METHOD FOR THE PRODUCTION THEREOF | |
DE2716463C2 (en) | Disposable shielded container for the transport and final storage of radioactive waste in the sea | |
DE3424938C2 (en) | ||
DE2338480A1 (en) | Transportable container for weakly radio-active waste - which is surrounded by gas-tight concrete vessel | |
DE2520804A1 (en) | NUCLEAR REACTOR PLANT | |
DE3244727A1 (en) | Method and flask system for transferring or transporting fuel elements from a nuclear power station to a storage site | |
DE2837631A1 (en) | Transport container for radioactive waste esp. fuel elements - has projecting flanges at top and bottom to give extra protection | |
DE2907738C2 (en) | Procedure for dismantling activated containers in decommissioned nuclear facilities | |
EP0043096A1 (en) | Device for the storage of radioactive materials | |
DE3015553A1 (en) | Irradiated fuel transport container with lifting trunnions - designed as buffers to crush on impact and protect container | |
EP0978849B1 (en) | Container for the final storage of spent fuel elements from nuclear power plants | |
DE3005466A1 (en) | Storage system for radioactive substances - with corrosion resistant ceramic covered modules screened in carrier container | |
DE3140020A1 (en) | METHOD FOR PRODUCING A DENSITY AND HOMOGENEOUS CAST COVER FOR A CONTAINER WITH HIGH RADIOACTIVE CONTENT AND DEVICE FOR IMPLEMENTING THE METHOD | |
DE8017567U1 (en) | CONCRETE CONTAINER FOR STORAGE OR TRANSPORTATION OF BARRELS WITH RADIOACTIVE CONTENT | |
DE7317984U (en) | Containers for the collection, transport and disposal of fission products | |
DE2836955A1 (en) | Final disposal and storage vessel for radioactive waste - which is transported in lost flasks which are then placed in the vessel with packing material between | |
DE8529691U1 (en) | Storage container in rectangular shape for the intermediate or final storage of radioactive or harmful waste |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PUAI | Public reference made under article 153(3) epc to a published international application that has entered the european phase |
Free format text: ORIGINAL CODE: 0009012 |
|
AK | Designated contracting states |
Designated state(s): BE CH FR GB IT LI LU NL SE |
|
17P | Request for examination filed |
Effective date: 19851209 |
|
17Q | First examination report despatched |
Effective date: 19891003 |
|
RAP3 | Party data changed (applicant data changed or rights of an application transferred) |
Owner name: FORSCHUNGSZENTRUM JUELICH GMBH |
|
GRAA | (expected) grant |
Free format text: ORIGINAL CODE: 0009210 |
|
AK | Designated contracting states |
Kind code of ref document: B1 Designated state(s): BE CH FR GB IT LI LU NL SE |
|
ITF | It: translation for a ep patent filed |
Owner name: STUDIO JAUMANN |
|
GBT | Gb: translation of ep patent filed (gb section 77(6)(a)/1977) | ||
EN | Fr: translation not filed | ||
PLBE | No opposition filed within time limit |
Free format text: ORIGINAL CODE: 0009261 |
|
STAA | Information on the status of an ep patent application or granted ep patent |
Free format text: STATUS: NO OPPOSITION FILED WITHIN TIME LIMIT |
|
26N | No opposition filed | ||
ITTA | It: last paid annual fee | ||
ET | Fr: translation filed | ||
REG | Reference to a national code |
Ref country code: FR Ref legal event code: BR |
|
EPTA | Lu: last paid annual fee | ||
EAL | Se: european patent in force in sweden |
Ref document number: 84110456.5 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: GB Payment date: 20000821 Year of fee payment: 17 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: FR Payment date: 20000918 Year of fee payment: 17 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: SE Payment date: 20000921 Year of fee payment: 17 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: LU Payment date: 20000922 Year of fee payment: 17 Ref country code: CH Payment date: 20000922 Year of fee payment: 17 Ref country code: BE Payment date: 20000922 Year of fee payment: 17 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: NL Payment date: 20000926 Year of fee payment: 17 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: LU Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20010903 Ref country code: GB Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20010903 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: SE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20010904 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: LI Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20010930 Ref country code: CH Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20010930 Ref country code: BE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20010930 |
|
BERE | Be: lapsed |
Owner name: FORSCHUNGSZENTRUM JULICH G.M.B.H. Effective date: 20010930 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: NL Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20020401 |
|
EUG | Se: european patent has lapsed |
Ref document number: 84110456.5 |
|
REG | Reference to a national code |
Ref country code: CH Ref legal event code: PL |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: FR Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20020531 |
|
NLV4 | Nl: lapsed or anulled due to non-payment of the annual fee |
Effective date: 20020401 |
|
REG | Reference to a national code |
Ref country code: FR Ref legal event code: ST |
|
NLV4 | Nl: lapsed or anulled due to non-payment of the annual fee |
Effective date: 20020401 |