EP0078988B1 - Concrete protection container for the storage of fuel-element receptacles - Google Patents

Concrete protection container for the storage of fuel-element receptacles Download PDF

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Publication number
EP0078988B1
EP0078988B1 EP82109951A EP82109951A EP0078988B1 EP 0078988 B1 EP0078988 B1 EP 0078988B1 EP 82109951 A EP82109951 A EP 82109951A EP 82109951 A EP82109951 A EP 82109951A EP 0078988 B1 EP0078988 B1 EP 0078988B1
Authority
EP
European Patent Office
Prior art keywords
concrete protective
concrete
protective casing
peripheral
storage
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
Application number
EP82109951A
Other languages
German (de)
French (fr)
Other versions
EP0078988A1 (en
Inventor
Hans-Peter Dipl.-Phys. Dyck
Harry Dipl.-Ing. Spilker
Heinz-Dieter Gregor
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Original Assignee
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH filed Critical Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Publication of EP0078988A1 publication Critical patent/EP0078988A1/en
Application granted granted Critical
Publication of EP0078988B1 publication Critical patent/EP0078988B1/en
Expired legal-status Critical Current

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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
    • 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
    • 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
    • G21F5/06—Details of, or accessories to, the containers
    • G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins

Definitions

  • the invention relates to a concrete protective housing for receiving and storing a fuel assembly loaded with spent nuclear reactor fuel elements, which is suitable for transport and storage, the external dimensions of which are somewhat smaller than the clear dimensions of the concrete protective housing, which consists of a drive-under, pallet-like foot part, a concrete protective jacket that can be placed on the foot part, and one the upper end of the concrete protective cover can be placed on the cover, at least one supply air opening being arranged in the lower region of the concrete protective housing and at least one exhaust air opening being arranged in the upper region of the concrete protective housing.
  • silo containers made of concrete or reinforced concrete.
  • These silo containers which form a concrete protective housing for each fuel element container, can have different designs.
  • a concrete protective housing for receiving fuel element containers has side supply air channels in the area of the upper jacket edge below the lid.
  • the base of the protective container is designed as a separately accessible pallet on which the fuel element container and above it the concrete protective jacket of the concrete protective jacket can be placed.
  • the arrangement of the supply air and extract air ducts results in natural convection within the concrete protective housing, which is used to dissipate the decay heat.
  • the pallet-like foot section makes it possible to drive the entire concrete protective housing to the storage area by means of a suitable conveyor vehicle after the fuel element container has been delivered and the concrete protective housing has been assembled.
  • This storage area is preferably located outdoors and is therefore exposed to the weather conditions.
  • the invention has for its object to design a concrete protective housing of the type described in such a way that surface water collecting on the concrete protective housing due to precipitation can run off well.
  • the object is achieved in that the cross-sectional dimensions of the foot part are smaller than the diameter or the cross-sectional dimensions of the concrete protective jacket.
  • the water that collects on the surface of the concrete protective housing will run off and can drip from the protruding concrete protective jacket to the floor.
  • the favorable water drainage achieved in this way reduces the adverse effects of the weather conditions.
  • Another significant advantage of the invention is seen in the fact that the transport aisle in the container store can be made narrower.
  • a further advantageous embodiment of the invention is characterized by the features specified in claim 2.
  • the segment-shaped inner recesses arranged at the lower end of the container shell form supply air openings.
  • the usual radial ventilation openings can be eliminated by this design.
  • a further minimization of the radiation exit is the advantageous consequence.
  • the manufacturing simplification of the production of the ventilation openings is also a major advantage.
  • the invention achieves a favorable drainage of the surface water from the concrete protective housing and enables the transport aisles in the container storage to be designed more closely.
  • the concrete protective housing consists of a pallet-like base 4, a cylindrical concrete protective jacket 5 placed thereon and a cylindrical cover 6 lying on the concrete protective jacket 5.
  • the foot part 4 consists of a square base plate 7, at the corners of which a foot 8 is arranged, so that the foot part 4 is designed as a pallet that can be driven under.
  • the base plate 7 has a centrally arranged, circular raised surface 9.
  • the diameter of the footprint 9 is smaller than the inside diameter of the cylindrical concrete protective jacket 5, which is placed on the foot part 4 and is aligned to the foot part 4 by suitable centering devices (not shown here).
  • the concrete protective jacket 5 has segment-shaped inner recesses 11 at its lower end, which serve as supply air channels.
  • the cover 6 lying on the concrete protective jacket 5 likewise has recesses 12 in the edge area on its surface facing the concrete protective jacket 5, which serve as exhaust air channels.
  • a fuel element container 13 shown here in broken lines, is arranged upright.
  • the outer diameter of the concrete protective jacket 5 corresponds to the length of the diagonals of the pallet-like base part 4. Surface water running off the concrete protective jacket 5 now drips directly down to the ground without standing on protruding heels of the foot part 4.
  • the transport aisle in the warehouse can be designed narrower.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Pallets (AREA)
  • Laying Of Electric Cables Or Lines Outside (AREA)
  • Packaging Of Machine Parts And Wound Products (AREA)
  • Containers Having Bodies Formed In One Piece (AREA)
  • Packages (AREA)

Description

Die Erfindung betrifft ein Betonschutzgehäuse zur Aufnahme und Lagerung eines mit abgebrannten Kernreaktorbrennelementen beladenen, transport- und lagergeeigneten Brennelementbehälters, dessen Außenabmessungen etwas kleiner als die lichten Maße des Betonschutzgehäuses sind, das aus einem unterfahrbaren, palettenartigen Fußteil, einem auf das Fußteil aufsetzbaren Betonschutzmantel und einem auf das obere Ende des Betonschutzmantels auflegbaren Deckel besteht, wobei im unteren Bereich des Betonschutzgehäuses mindestens eine Zuluftöffnung und im oberen Bereich des Betonschutzgehäuses mindestens eine Abluftöffnung angeordnet sind.The invention relates to a concrete protective housing for receiving and storing a fuel assembly loaded with spent nuclear reactor fuel elements, which is suitable for transport and storage, the external dimensions of which are somewhat smaller than the clear dimensions of the concrete protective housing, which consists of a drive-under, pallet-like foot part, a concrete protective jacket that can be placed on the foot part, and one the upper end of the concrete protective cover can be placed on the cover, at least one supply air opening being arranged in the lower region of the concrete protective housing and at least one exhaust air opening being arranged in the upper region of the concrete protective housing.

Bei den Bemühungen, Brennelementbehälter im Freien zwischenzulagem, wurde bereits vorgeschlagen, die Brennelementbehälter in Silobehälter aus Beton oder Stahlbeton einzubringen. Diese ein Betonschutzgehäuse für jeweils einen Brennelementbehälter bildenden Silobehälter können verschiedene Ausbildungen aufweisen. Bei den Staaten BE, CH, FR, GB, IT, LI und SE nicht vorveröffentlichten nach Art 54(3) EPU zu berücksichtigenden EP-A1-0 039 785) weist ein Betonschutzgehäuse zur Aufnahme von Brennelementbehältern seitliche Zuluftkanäle im Bereich des oberen Mantelrandes unterhalb des Deckels auf. Der Fuß des Schutzbehälters ist als separat unterfahrbare Palette ausgebildet, auf die der Brennelementbehälter und darüber der Betonschutzmantel des Betonschutzmantels aufsetzbar sind. Durch die Anordnung der Zuluft-und Abluftkanäle wird innerhalb des Betonschutzgehäuses eine natürliche Konvektion bewirkt, die zur Abfuhr der Nachzerfallswärme dient. Das palettenartig ausgebildete Fußteil ermöglicht es, das gesamte Betonschutzgehäuse nach Anlieferung des Brennelementbehälters und Zusammenstellen des Betonschutzgehäuses mit seinem Inhalt mittels eines geeigneten Förderfahrzeuges zum Lagerfeld zu fahren. Dieses Lagerfeld befindet sich vorzugsweise im Freien und ist daher den Witterungsbedingungen ausgesetzt.In the effort to interpose fuel element containers outdoors, it has already been proposed to insert the fuel element containers into silo containers made of concrete or reinforced concrete. These silo containers, which form a concrete protective housing for each fuel element container, can have different designs. For the states BE, CH, FR, GB, IT, LI and SE EP-A1-0 039 785), which has not been prepublished in accordance with Art 54 (3) EPU and has to be taken into account, a concrete protective housing for receiving fuel element containers has side supply air channels in the area of the upper jacket edge below the lid. The base of the protective container is designed as a separately accessible pallet on which the fuel element container and above it the concrete protective jacket of the concrete protective jacket can be placed. The arrangement of the supply air and extract air ducts results in natural convection within the concrete protective housing, which is used to dissipate the decay heat. The pallet-like foot section makes it possible to drive the entire concrete protective housing to the storage area by means of a suitable conveyor vehicle after the fuel element container has been delivered and the concrete protective housing has been assembled. This storage area is preferably located outdoors and is therefore exposed to the weather conditions.

Der Erfindung liegt die Aufgabe zugrunde, ein Betonschutzgehäuse der eingang beschriebenen Art derart auszugestalten, daß sich auf dem Betonschutzgehäuse aufgrund von Niederschlag sammelndes Oberflächenwasser gut ablaufen kann.The invention has for its object to design a concrete protective housing of the type described in such a way that surface water collecting on the concrete protective housing due to precipitation can run off well.

Die Aufgabe wird erfindungsgemäß dadurch gelöst, daß die Querschnittsabmessungen des Fußteiles kleiner sind als der Durchmesser oder die Querschnittsabmessungen des Betonschutzmantels.The object is achieved in that the cross-sectional dimensions of the foot part are smaller than the diameter or the cross-sectional dimensions of the concrete protective jacket.

Wird das palettenartige Fußteil gemäß der Erfindung ausgebildet, wird das sich auf der Oberfläche des Betonschutzgehäuses sammelnde Wasser ablaufen und von dem überstehenden Betonschutzmantel zum Boden abtropfen können. Der so erreichte günstige Wasserablauf verringert die nachteiligen Einwirkungen der Witterungsbedingungen.If the pallet-like foot part is designed according to the invention, the water that collects on the surface of the concrete protective housing will run off and can drip from the protruding concrete protective jacket to the floor. The favorable water drainage achieved in this way reduces the adverse effects of the weather conditions.

Ein weiterer wesentlicher Vorteil der Erfindung wird darin gesehen, daß die Transportgasse im Behälterlager enger ausgelegt werden kann.Another significant advantage of the invention is seen in the fact that the transport aisle in the container store can be made narrower.

Eine weitere vorteilhafte Ausgestaltung der Erfindung wird durch die im Anspruch 2 angegebenen Merkmale gekennzeichnet. Die am unteren Ende des Behältermantels angeordneten, segmentförmigen Innenausnehmungen bilden Zuluftöffnungen. Durch diese konstruktive Ausgestaltung können die üblichen radialen Lüftungsöffnungen wegfallen. Eine weitere Minimierung des Strahlungsaustrittes ist die vorteilhafte Folge. Die fertigungstechnische Vereinfachung der Herstellung der Belüftungsöffnungen ist ebenfalls ein wesentlicher Vorteil.A further advantageous embodiment of the invention is characterized by the features specified in claim 2. The segment-shaped inner recesses arranged at the lower end of the container shell form supply air openings. The usual radial ventilation openings can be eliminated by this design. A further minimization of the radiation exit is the advantageous consequence. The manufacturing simplification of the production of the ventilation openings is also a major advantage.

Durch die Erfindung wird ein günstiger Ablauf des Oberflächenwassers vom Betonschutzgehäuse erreicht und in engeres Auslegen der Transportgassen im Behälterlager ermöglicht.The invention achieves a favorable drainage of the surface water from the concrete protective housing and enables the transport aisles in the container storage to be designed more closely.

Anhand der Zeichnung wird nachstehend ein Ausführungsbeispiel der Erfindung näher erläutert. Es zeigt.

  • Figur 1 ein Betonschutzgehäuse in der Seitenansicht,
  • Figur 2 einen Schnitt durch das in Fig. 1 dargestellte Betonschutzgehäuse gemäß Linie 11-11 in Fig. 3 und
  • Figur 3 einen Querschnitt des Betonschutzgehäuses gemäß Linie 111-111 in Fig. 2.
An exemplary embodiment of the invention is explained in more detail below with reference to the drawing. It shows.
  • FIG. 1 shows a concrete protective housing in a side view,
  • Figure 2 shows a section through the concrete protective housing shown in Fig. 1 along line 11-11 in Fig. 3 and
  • FIG. 3 shows a cross section of the concrete protective housing according to line 111-111 in FIG. 2.

Das Betonschutzgehäuse besteht aus einem palettenartig ausgebildeten Fußteil 4, einem darauf aufgesetzten zylindrischen Betonschutzmantel 5 und einem auf dem Betonschutzmantel 5 liegenden zylindrischen Deckel 6.The concrete protective housing consists of a pallet-like base 4, a cylindrical concrete protective jacket 5 placed thereon and a cylindrical cover 6 lying on the concrete protective jacket 5.

Das Fußteil 4 besteht aus einer quadratischen Bodenplatte 7, an deren Ecken jeweils ein Fuß 8 angeordnet ist, so daß das Fußteil 4 als unterfahrbare Palette ausgebildet ist. Die Bodenplatte 7 weist eine zentrisch angeordnete, kreisförmige, erhobene Stellfläche 9 auf. Der Durchmesser der Stellfläche 9 ist kleiner als der lichte Durchmesser des zylinderförmigen Betonschutzmantels 5, der auf das Fußteil 4 aufgesetzt und durch hier nicht gezeigte, geeignete Zentriervorrichtungen zum Fußteil 4 ausgerichtet ist.The foot part 4 consists of a square base plate 7, at the corners of which a foot 8 is arranged, so that the foot part 4 is designed as a pallet that can be driven under. The base plate 7 has a centrally arranged, circular raised surface 9. The diameter of the footprint 9 is smaller than the inside diameter of the cylindrical concrete protective jacket 5, which is placed on the foot part 4 and is aligned to the foot part 4 by suitable centering devices (not shown here).

Der Betonschutzmantel 5 weist an seinem unteren Ende segmentförmige Innenausnehmungen 11 auf, die als Zuluftkanäle dienen. Der auf dem Betonschutzmantel 5 liegende Deckel 6 weist im Randbereich auf seiner dem Betonschutzmantel 5 zugewandten Fläche ebenfalls Ausnehmungen 12 auf, die als Abluftkanäle dienen.The concrete protective jacket 5 has segment-shaped inner recesses 11 at its lower end, which serve as supply air channels. The cover 6 lying on the concrete protective jacket 5 likewise has recesses 12 in the edge area on its surface facing the concrete protective jacket 5, which serve as exhaust air channels.

Auf der Stellfläche 9 des Fußteiles 4 ist ein hier strichpunktiert dargestellter Brennelementbehälter 13 aufrechtstehend angeordnet.On the footprint 9 of the foot part 4, a fuel element container 13, shown here in broken lines, is arranged upright.

Der Außendurchmesser des Betonschutzmantels 5 entspricht in diesem Ausführungsbeispiel der Länge der Diagonalen des palettenartigen Fußteiles 4. Von dem Betonschutzmantel 5 ablaufendes Oberflächenwasser tropft nun direkt zum Erdboden ab, ohne auf vorspringenden Absätzen des Fußteiles 4 stehenzubleiben.In this exemplary embodiment, the outer diameter of the concrete protective jacket 5 corresponds to the length of the diagonals of the pallet-like base part 4. Surface water running off the concrete protective jacket 5 now drips directly down to the ground without standing on protruding heels of the foot part 4.

Dadurch, daß das Fußteil 4 schmaler als der Außendurchmesser des Betonschutzmantels 5 ist, kann die Transportgasse im Lager enger ausgelegt werden.Characterized in that the foot part 4 is narrower than the outer diameter of the protective concrete jacket 5, the transport aisle in the warehouse can be designed narrower.

Claims (2)

1. A concrete protective casing for accommodating and storing a fuel element container (13) which is suitable for transportation and storage and which is loaded with spent nuclear reactor fuel elements and whose outside dimensions are somewhat smaller than the internal dimensions of the concrete protective casing which comprises a pallet-like base portion (4) which can be underrun, a concrete peripheral protective casing portion (5) which can be put on to the base portion, and a cover (6) which can be laid on to the upper end of the peripheral casing portion (5), wherein at least one air inlet opening (11) is disposed in the lower region of the concrete protective casing and at least one air discharge opening (12) is arranged in the upper region of the concrete protective casing characterised in that the cross-sectional dimensions of the base portion (4) are smaller than the diameter or the cross-sectional dimensions of the peripheral casing portion (5).
2. A concrete protective casing according to claim 1 characterised in that internal recesses (11) are disposed in the lower end of the peripheral casing portion (5), in the protruding region of the peripheral casing portion (5).
EP82109951A 1981-11-06 1982-10-28 Concrete protection container for the storage of fuel-element receptacles Expired EP0078988B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3144116 1981-11-06
DE19813144116 DE3144116A1 (en) 1981-11-06 1981-11-06 CONCRETE PROTECTIVE HOUSING FOR DRY INTERMEDIATE STORAGE OF FUEL ELEMENT CONTAINERS

Publications (2)

Publication Number Publication Date
EP0078988A1 EP0078988A1 (en) 1983-05-18
EP0078988B1 true EP0078988B1 (en) 1985-04-03

Family

ID=6145783

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82109951A Expired EP0078988B1 (en) 1981-11-06 1982-10-28 Concrete protection container for the storage of fuel-element receptacles

Country Status (5)

Country Link
US (1) US4527066A (en)
EP (1) EP0078988B1 (en)
JP (1) JPS58135494A (en)
CA (1) CA1190668A (en)
DE (2) DE3144116A1 (en)

Families Citing this family (32)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4780269A (en) * 1985-03-12 1988-10-25 Nutech, Inc. Horizontal modular dry irradiated fuel storage system
FR2601809B1 (en) * 1986-07-17 1988-09-16 Commissariat Energie Atomique DEVICE FOR THE DRY STORAGE OF MATERIALS GENERATING HEAT, PARTICULARLY RADIOACTIVE MATERIALS
US5633508A (en) * 1995-10-12 1997-05-27 Cold Spring Granite Company Secondary shielding structure
US5852643A (en) * 1997-06-09 1998-12-22 Copson; Alex G. Flak jacket protective cover for spent nuclear fuel storage casks
US6519307B1 (en) * 2000-05-30 2003-02-11 Holtec International Ventilated overpack apparatus and method for storing spent nuclear fuel
JP3962542B2 (en) * 2000-11-08 2007-08-22 三菱重工業株式会社 Storage system, and storage container and container transport device used for storage system
US6718000B2 (en) * 2002-02-06 2004-04-06 Holtec International, Inc. Ventilated vertical overpack
US7590213B1 (en) 2004-03-18 2009-09-15 Holtec International, Inc. Systems and methods for storing spent nuclear fuel having protection design
US20050220256A1 (en) * 2004-03-18 2005-10-06 Singh Krishna P Systems and methods for storing spent nuclear fuel having a low heat load
US7068748B2 (en) * 2004-03-18 2006-06-27 Holtec International, Inx. Underground system and apparatus for storing spent nuclear fuel
US8098790B2 (en) * 2004-03-18 2012-01-17 Holtec International, Inc. Systems and methods for storing spent nuclear fuel
JP3917998B2 (en) * 2004-11-08 2007-05-23 三菱重工業株式会社 Storage system, and storage container and container transport device used for storage system
US8718220B2 (en) 2005-02-11 2014-05-06 Holtec International, Inc. Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment
EP1849163B1 (en) * 2005-02-11 2014-07-30 Holtec International, Inc. Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment
US9443625B2 (en) 2005-03-25 2016-09-13 Holtec International, Inc. Method of storing high level radioactive waste
US7330526B2 (en) * 2005-03-25 2008-02-12 Holtec International, Inc. System and method of storing high level waste
US7786456B2 (en) * 2006-10-11 2010-08-31 Holtec International, Inc. Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials
FR2918649B1 (en) * 2007-07-10 2012-02-10 Transnuclear Inc LONG STORAGE PACKAGING WITH REMOVABLE BOTTOM.
US8660230B2 (en) * 2007-12-22 2014-02-25 Holtec International, Inc. System and method for the ventilated storage of high level radioactive waste in a clustered arrangement
US9001958B2 (en) 2010-04-21 2015-04-07 Holtec International, Inc. System and method for reclaiming energy from heat emanating from spent nuclear fuel
US11569001B2 (en) 2008-04-29 2023-01-31 Holtec International Autonomous self-powered system for removing thermal energy from pools of liquid heated by radioactive materials
EP2430635A4 (en) 2009-05-06 2013-12-25 Holtec International Inc Apparatus for storing and/or transporting high level radioactive waste, and method for manufacturing the same
US8995604B2 (en) 2009-11-05 2015-03-31 Holtec International, Inc. System, method and apparatus for providing additional radiation shielding to high level radioactive materials
US8905259B2 (en) 2010-08-12 2014-12-09 Holtec International, Inc. Ventilated system for storing high level radioactive waste
US9514853B2 (en) 2010-08-12 2016-12-06 Holtec International System for storing high level radioactive waste
US11887744B2 (en) 2011-08-12 2024-01-30 Holtec International Container for radioactive waste
US10811154B2 (en) 2010-08-12 2020-10-20 Holtec International Container for radioactive waste
US11373774B2 (en) 2010-08-12 2022-06-28 Holtec International Ventilated transfer cask
WO2013085638A1 (en) 2011-10-28 2013-06-13 Holtec International, Inc. Method for controlling temperature of a radioactive waste storage system
EP2839484A4 (en) 2012-04-18 2016-01-06 Holtec International Inc Storing and/or transferring high level radioactive waste
US20220367078A1 (en) * 2021-05-17 2022-11-17 Holtec International Stackable nuclear waste storage system
US11735327B2 (en) 2021-06-16 2023-08-22 Holtec International Ventilated cask for nuclear waste storage

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1257299B (en) * 1961-10-03 1967-12-28 Licentia Gmbh Transport container for radioactive materials
DE2300620A1 (en) * 1973-01-08 1974-07-11 Transnuklear Gmbh Shielded transport flask - for plutonium nitrate or uranyl nitrate solutions
DE2821780A1 (en) * 1978-05-18 1979-11-22 Lovincic Miroslav Transport coffin for radioactive cpd., esp. irradiated fuel elements - has ventilation openings at opposite ends and internal sealed capsules
DE7838526U1 (en) * 1978-12-27 1979-03-29 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe DISPOSABLE CONCRETE CONTAINER FOR RECEIVING BARRELS WITH RADIOACTIVE CONTENT
GB2060466B (en) * 1979-10-11 1983-03-09 British Nuclear Fuels Ltd Nuclear fuel transport flask
DE3017767C2 (en) * 1980-05-09 1984-11-15 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Protective container for the transport, storage and radiation shielding of fuel element containers loaded with spent reactor fuel elements
FR2495817B1 (en) * 1980-12-06 1988-05-13 Kernforschungsz Karlsruhe CONTAINER FOR STORING AND TRANSPORTING AT LEAST ONE SHELL FILLED WITH RADIO-ACTIVE WASTE INCORPORATED IN MOLTEN GLASS

Also Published As

Publication number Publication date
JPH0348479B2 (en) 1991-07-24
DE3262897D1 (en) 1985-05-09
DE3144116A1 (en) 1983-05-19
US4527066A (en) 1985-07-02
CA1190668A (en) 1985-07-16
EP0078988A1 (en) 1983-05-18
JPS58135494A (en) 1983-08-12

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