EP1122744B1 - Method for manufacturing a transport and/or storage container for radioactive materials - Google Patents

Method for manufacturing a transport and/or storage container for radioactive materials Download PDF

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Publication number
EP1122744B1
EP1122744B1 EP99125003A EP99125003A EP1122744B1 EP 1122744 B1 EP1122744 B1 EP 1122744B1 EP 99125003 A EP99125003 A EP 99125003A EP 99125003 A EP99125003 A EP 99125003A EP 1122744 B1 EP1122744 B1 EP 1122744B1
Authority
EP
European Patent Office
Prior art keywords
diaphragm
partial
shell
suspension
spacer arrangement
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
Application number
EP99125003A
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German (de)
French (fr)
Other versions
EP1122744A1 (en
Inventor
Konrad Dipl.-Ing. Gluschke
Rudolf Dr. Dipl.-Ing. Diersch
Dieter Dipl.-Ing. Methling
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.)
GNB Gesellschaft fuer Nuklear Behaelter mbH
Original Assignee
GNB Gesellschaft fuer Nuklear Behaelter 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 GNB Gesellschaft fuer Nuklear Behaelter mbH filed Critical GNB Gesellschaft fuer Nuklear Behaelter mbH
Priority to DE59903429T priority Critical patent/DE59903429D1/en
Priority to EP99125003A priority patent/EP1122744B1/en
Priority to AT99125003T priority patent/ATE227880T1/en
Priority to ES99125003T priority patent/ES2182452T3/en
Priority to TW089124260A priority patent/TW483005B/en
Priority to US09/728,604 priority patent/US6438190B2/en
Priority to CA002327663A priority patent/CA2327663A1/en
Priority to EA200001160A priority patent/EA002394B1/en
Priority to UA2000127076A priority patent/UA67781C2/en
Priority to BG105036A priority patent/BG64066B1/en
Priority to CZ20004597A priority patent/CZ293365B6/en
Priority to SK1874-2000A priority patent/SK284611B6/en
Priority to JP2000377626A priority patent/JP4683716B2/en
Priority to KR1020000075393A priority patent/KR100746929B1/en
Priority to CNB001356852A priority patent/CN1152387C/en
Publication of EP1122744A1 publication Critical patent/EP1122744A1/en
Application granted granted Critical
Publication of EP1122744B1 publication Critical patent/EP1122744B1/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/06—Details of, or accessories to, the containers
    • 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 method for producing a Transport and / or storage containers for radioactive objects, in particular spent nuclear reactor fuel elements, one between a metallic outer jacket and a Metallic inner jacket formed hollow cylindrical jacket space with a minimum grain size Concrete aggregate and then the rest with a suspension made of cement, water and additives.
  • the invention is based, in the context of the task Procedure of the type mentioned at the beginning for transport - and / or storage containers for radioactive objects to achieve high neutron source strengths, the lower concrete wall thicknesses than previously required.
  • the passage openings are smaller than the minimum grain size, two sub-spaces are formed which are concentric with each other and the concrete aggregate and the suspension in only one of the two Subspaces entered.
  • the diaphragm formed from perforated sieves or sheets or wire mesh, the passage openings in particular an opening width have between 2 and 4 mm.
  • the said heat conduction radial webs are on the containers in question known and serve to derive from the radioactive Objects developed heat outside.
  • the diaphragm is on an inner partial web arrangement of heat conduction radial webs, that run between the inner jacket and the outer jacket, and on the diaphragm a supplementary outer partial web arrangement is placed, which is screwed to the inner jacket becomes. It is recommended that the diaphragm, the inner partial web arrangement and the outer partial web arrangement in the area of corresponding longitudinal beads to sit on top of each other. There are also manipulation-related ones Advantages if there are two adjacent radial part webs the outer part web arrangement by an outer bridge are interconnected. Accordingly, two can Adjacent radial partial webs of the inner partial web arrangement be connected by an inner bridge. In all In cases it is advisable to use the diaphragm or this fixing the forming parts by welding.
  • the concrete aggregate and the Suspension can be entered in the same subspace.
  • the concrete surcharge should be left in the one adjacent to the inner jacket Subspace can be entered so that the outer Partial area the higher water content for neutron moderation having.
  • a jacket of a storage container for radioactive objects which initially consist of a metallic Outer jacket 1 and a concentrically arranged metallic inner jacket 2 is formed. Between Outer jacket 1 and inner jacket 2 is therefore a hollow cylindrical one Gap space 3 given. Between inner jacket 2 and outer jacket 1 run heat conducting material webs 4 with flared window elements 5. These heat conduction radial webs 4 are welded to U-profiles 6, which in turn are attached to the inner jacket 2. On the outer jacket 1 are also U-profiles 7 attached to which the heat conduction radial webs 4 but are only pressed.
  • the diaphragm 8 is made of open and closed profiles 81, 82 of perforated screens or sheets or wire mesh formed between the radial heat conducting webs 4 are used and are in contact with them and with them are welded.
  • a concrete aggregate with a minimum grain size and then a suspension of cement, Water and additives entered. Since the diaphragm has 8 openings that is smaller than the minimum grain size only the suspension gets into the outer subspace 32.
  • the diaphragm is 8th to an inner partial web arrangement 41 of heat conduction radial webs 4 and on the diaphragm 8 a supplementary outer partial web arrangement 42 placed with the inner jacket 2 is screwed.
  • the diaphragm 8 the inner part web arrangement 41 and the outer part web arrangement 42 in the area of corresponding longitudinal beads 9 placed on top of each other.
  • Two adjacent ones Radial partial webs of the outer partial web arrangement 42 are through an outer bridge 10 connected to each other.
  • Corresponding are also two adjacent radial webs of the inner one Part web arrangement 41 through an inner bridge 11 with each other connected.
  • the screw connection 12 takes place through the outer bridge 10 and the diaphragm 8 with the inner jacket 2.
  • the Outer jacket 1 is under elastic deformation of the heat conduction radial webs 4 has been put on.
  • the backfilling takes place in the same way as indicated above.
  • composition can correspond to that in WO 98/59346 is specified.

Abstract

A storage/transport container for radioactive material is made by first subdividing a chamber formed between an inner shell and an outer shell into first and second compartments by means of a foraminous partition having a predetermined maximum mesh size. Then an aggregate of a predetermined minimum particle size greater than the predetermined maximum mesh size is introduced into one of the compartments and a suspension of cement and water is introduced into the first compartment such that the aggregate remains in the one compartment and the cement and water flow through the partition into the second compartment. Normally the aggregate and the suspension are both introduced into the same compartment.

Description

Die Erfindung betrifft ein Verfahren zum Herstellen eines Transport- und/oder Lagerbehälters für radioaktive Gegenstände, insbesondere abgebrannte Kernreaktorbrennelemente, wobei ein zwischen einem metallischen Außenmantel und einem metallischen Innenmantel gebildeter hohlzylindrischer Mantelzwischenraum mit einem eine Mindestkorngröße aufweisenden Betonzuschlag und anschließend im Rest mit einer Suspension aus Zement, Wasser und Additiven verfüllt wird.The invention relates to a method for producing a Transport and / or storage containers for radioactive objects, in particular spent nuclear reactor fuel elements, one between a metallic outer jacket and a Metallic inner jacket formed hollow cylindrical jacket space with a minimum grain size Concrete aggregate and then the rest with a suspension made of cement, water and additives.

Bei einem bekannten Verfahren der genannten Art (WO 98/59346) wird der gesamte Mantelzwischenraum gleichartig verfüllt. Die auf diese Weise hergestellten Behälter eignen sich nur zur Abschirmung von Strahlenquellen mit relativ niedriger Neutronenquellstärke, z. B. Brennelementen mit niedrigem Abbrand. Soll ein solcher Behälter für Strahlenquellen mit hochdosierten Neutronenquellstärken, z. B. MOX-Brennelementen oder verglasten hochaktivem Abfall aus der Wiederaufarbeitung, verwendet werden, werden verhältnismäßig große Betonwanddicken erforderlich, um die für die Neutronenmoderation benötigten Wassermengen bereitzustellen.In a known method of the type mentioned (WO 98/59346) the entire space between the shells becomes the same filled. The containers produced in this way are suitable only for shielding from radiation sources with relative low neutron source strength, e.g. B. fuel elements with low burn-up. Should such a container for radiation sources with high dose neutron source strengths, e.g. B. MOX fuel assemblies or glazed highly active waste from the Remanufacturing, used, will be proportionate Large concrete wall thicknesses are required in order for the To provide neutron moderation required amounts of water.

Der Erfindung liegt die Aufgabe zugrunde, im Rahmen des Verfahrens der eingangs genannten Art zu Transport - und/oder Lagerbehältern für radioaktive Gegenstände mit hohen Neutronenquellstärken zu gelangen, die geringere Betonwandstärken als bisher erfordern. The invention is based, in the context of the task Procedure of the type mentioned at the beginning for transport - and / or storage containers for radioactive objects to achieve high neutron source strengths, the lower concrete wall thicknesses than previously required.

Zur Lösung dieser Aufgabe werden erfindungsgemäß im Mantelzwischenraum mit Hilfe eines Diaphragmas, dessen Durchtrittsöffnungen kleiner als die Mindestkorngröße sind, zwei zueinander konzentrische Teilräume gebildet und der Betonzuschlag sowie die Suspension jeweils nur in einen der beiden Teilräume eingegeben.To solve this problem, according to the invention, in the space between the shells with the help of a diaphragm, the passage openings are smaller than the minimum grain size, two sub-spaces are formed which are concentric with each other and the concrete aggregate and the suspension in only one of the two Subspaces entered.

Mit Hilfe der beschriebenen Maßnahmen wird der Mantelzwischenraum bzw. Betonraum in zwei unterschiedliche Teilräume mit unterschiedlicher Verfüllung geteilt. Der Betonzuschlag verbleibt aufgrund des Diaphragmas in dem Teilraum, in den er eingegeben worden ist, während das Diaphragma für die Suspension kein Hindernis darstellt und sich in beiden Teilräumen ausbreitet. Der von der Suspension allein eingenommene Teilraum enthält wesentlich mehr Wasser als bisher und kann daher die für die Neutronenmoderationen benötigten Wassermengen bereitstellen.With the help of the measures described, the space between the shells or concrete room in two different sub-rooms shared with different backfilling. The concrete surcharge remains because of the diaphragm in the subspace in which it has been entered while the diaphragm for the Suspension is not an obstacle and is in both Spreads subspaces. The one taken by the suspension alone Partial space contains much more water than before and can therefore be used for neutron moderation Provide water quantities.

Nach einer bevorzugten Ausführungsform wird das Diaphragma aus Lochsieben oder -blechen oder Drahtgeflecht gebildet, deren Durchtrittsöffnungen insbesondere eine Öffnungsweite zwischen 2 und 4 mm aufweisen. Im Einzelnen kann dabei zunächst so vorgegangen werden, dass das Diaphragma durch Einführen von offenen und/oder geschlossenen Diaphragmaprofilen zwischen Wärmeleitungsradialstegen gebildet wird, die zwischen Innenmantel und Außenmantel verlaufen und an denen die Diaphragmaprofile anliegen. Die besagten Wärmeleitungsradialstege sind bei den in Rede stehenden Behältern an sich bekannt und dienen der Ableitung der von den radioaktiven Gegenständen entwickelten Wärme nach außen. Eine andere Möglichkeit besteht darin, dass das Diaphragma auf eine innere Teilsteganordnung von Wärmeleitungsradialstegen, die zwischen Innenmantel und Außenmantel verlaufen, und auf das Diaphragma eine ergänzende äußere Teilsteganordnung aufgesetzt wird, die mit dem Innenmantel verschraubt wird. Hierbei empfiehlt es sich, das Diaphragma, die innere Teilsteganordnung und die äußere Teilsteganordnung im Bereich von einander entsprechenden Längssicken aufeinander zu setzen. Auch ergeben sich manipulationstechnische Vorteile, wenn jeweils zwei benachbarte Radialteilstege der äußeren Teilsteganordnung durch eine Außenbrücke miteinander verbunden sind. Entsprechend können auch zwei benachbarte Radialteilstege der inneren Teilsteganordnung durch eine Innenbrücke miteinander verbunden sein. In allen Fällen empfiehlt es sich, das Diaphragma bzw. die dieses bildenden Teile durch Schweißungen lagezufixieren.According to a preferred embodiment, the diaphragm formed from perforated sieves or sheets or wire mesh, the passage openings in particular an opening width have between 2 and 4 mm. In detail, you can start with be done so that the diaphragm through Introduction of open and / or closed diaphragm profiles is formed between heat conduction radial webs run between the inner jacket and outer jacket and on them the diaphragm profiles fit. The said heat conduction radial webs are on the containers in question known and serve to derive from the radioactive Objects developed heat outside. A another possibility is that the diaphragm is on an inner partial web arrangement of heat conduction radial webs, that run between the inner jacket and the outer jacket, and on the diaphragm a supplementary outer partial web arrangement is placed, which is screwed to the inner jacket becomes. It is recommended that the diaphragm, the inner partial web arrangement and the outer partial web arrangement in the area of corresponding longitudinal beads to sit on top of each other. There are also manipulation-related ones Advantages if there are two adjacent radial part webs the outer part web arrangement by an outer bridge are interconnected. Accordingly, two can Adjacent radial partial webs of the inner partial web arrangement be connected by an inner bridge. In all In cases it is advisable to use the diaphragm or this fixing the forming parts by welding.

Um die gewünschte Zweizonenstruktur des Betons zuverlässig und schnell herzustellen, sollte der Betonzuschlag und die Suspension in denselben Teilraum eingegeben werden. Im Übrigen sollte der Betonzuschlag in den dem Innenmantel benachbarten Teilraum eingegeben werden, so dass der äußere Teilraum den höheren Wassergehalt für die Neutronenmoderation aufweist.To reliably achieve the desired two-zone structure of the concrete and to manufacture quickly, the concrete aggregate and the Suspension can be entered in the same subspace. in the The concrete surcharge should be left in the one adjacent to the inner jacket Subspace can be entered so that the outer Partial area the higher water content for neutron moderation having.

Im Folgenden wird die Erfindung anhand einer Zeichnung erläutert. Es zeigen

Fig. 1
einen Schnitt durch einen Teil eines Behältermantels und
Fig. 2
einer anderen Ausführungsform.
The invention is explained below with reference to a drawing. Show it
Fig. 1
a section through part of a container shell and
Fig. 2
another embodiment.

In Fig. 1 erkennt man einen Mantel eines Lagerbehälters für radioaktive Gegenstände, der zunächst aus einem metallischen Außenmantel 1 und einem konzentrisch dazu angeordneten metallischen Innenmantel 2 gebildet ist. Zwischen Außenmantel 1 und Innenmatel 2 ist also ein hohlzylindrischer Mantelzwischenraum 3 gegeben. Zwischen Innenmantel 2 und Außenmantel 1 verlaufen Wärmeleitungsmaterialstege 4 mit ausgestellten Fensterelementen 5. Diese Wärmeleitungsradialstege 4 sind mit U-Profilen 6 verschweißt, die ihrerseits an dem Innenmantel 2 befestigt sind. Am Außenmantel 1 sind ebenfalls U-Profile 7 befestigt, an die die Wärmeleitungsradialstege 4 aber nur angepreßt sind.In Fig. 1 you can see a jacket of a storage container for radioactive objects, which initially consist of a metallic Outer jacket 1 and a concentrically arranged metallic inner jacket 2 is formed. Between Outer jacket 1 and inner jacket 2 is therefore a hollow cylindrical one Gap space 3 given. Between inner jacket 2 and outer jacket 1 run heat conducting material webs 4 with flared window elements 5. These heat conduction radial webs 4 are welded to U-profiles 6, which in turn are attached to the inner jacket 2. On the outer jacket 1 are also U-profiles 7 attached to which the heat conduction radial webs 4 but are only pressed.

Im Mantelzwischenraum 3 sind mit Hilfe eines Diaphragmas 8 zwei zueinander konzentrische Teilräume 31, 32 gebildet. Das Diaphragma 8 wird von offenen und geschlossenen Profilen 81, 82 von Lochsieben oder -blechen oder Drahtgeflecht gebildet, die zwischen die Wärmeleitungsradialstege 4 eingesetzt sind und an diesen anliegen sowie mit diesen verschweißt sind. Zum Fertigstellen des Behälters wird in den inneren Teilraum 31 ein Betonzuschlag mit einer Mindestkorngröße und anschließend eine Suspension aus Zement, Wasser und Additiven eingegeben. Da das Diaphragma 8 Durchtrittsöffnungen aufweist, die kleiner als die Mindestkorngröße sind, gelangt in den äußeren Teilraum 32 nur die Suspension.In the intermediate space 3 with the help of a diaphragm 8 two concentric subspaces 31, 32 are formed. The diaphragm 8 is made of open and closed profiles 81, 82 of perforated screens or sheets or wire mesh formed between the radial heat conducting webs 4 are used and are in contact with them and with them are welded. To finish the container is in the inner subspace 31 a concrete aggregate with a minimum grain size and then a suspension of cement, Water and additives entered. Since the diaphragm has 8 openings that is smaller than the minimum grain size only the suspension gets into the outer subspace 32.

Bei der Ausführungsform nach Fig. 2 wird das Diaphragma 8 auf eine innere Teilsteganordnung 41 von Wärmeleitungsradialstegen 4 und auf das Diaphragma 8 eine ergänzende äußere Teilsteganordnung 42 aufgesetzt, die mit dem Innenmantel 2 verschraubt wird. Hierbei werden das Diaphragma 8, die innere Teilsteganordnung 41 und die äußere Teilsteganordnung 42 im Bereich von einander entsprechenden Längssicken 9 aufeinander gesetzt. Jeweils zwei benachbarte Radialteilstege der äußeren Teilsteganordnung 42 sind durch eine Außenbrücke 10 miteinander verbunden. Entsprechend sind auch jeweils zwei benachbarte Radialstege der inneren Teilsteganordnung 41 durch eine Innenbrücke 11 miteinander verbunden. Die Verschraubung 12 erfolgt durch die Außenbrücke 10 und das Diaphragma 8 mit dem Innenmantel 2. Der Außenmantel 1 ist unter elastischer Verformung der Wärmeleitungsradialstege 4 aufgesetzt worden. Die Verfüllung erfolgt in der gleichen Weise wie oben angegeben.2, the diaphragm is 8th to an inner partial web arrangement 41 of heat conduction radial webs 4 and on the diaphragm 8 a supplementary outer partial web arrangement 42 placed with the inner jacket 2 is screwed. Here the diaphragm 8, the inner part web arrangement 41 and the outer part web arrangement 42 in the area of corresponding longitudinal beads 9 placed on top of each other. Two adjacent ones Radial partial webs of the outer partial web arrangement 42 are through an outer bridge 10 connected to each other. Corresponding are also two adjacent radial webs of the inner one Part web arrangement 41 through an inner bridge 11 with each other connected. The screw connection 12 takes place through the outer bridge 10 and the diaphragm 8 with the inner jacket 2. The Outer jacket 1 is under elastic deformation of the heat conduction radial webs 4 has been put on. The backfilling takes place in the same way as indicated above.

Die Zusammensetzung kann derjenigen entsprechen, welche in WO 98/59346 angegeben ist.The composition can correspond to that in WO 98/59346 is specified.

Claims (10)

  1. A method of producing a transport and/or storage vessel for radioactive articles, wherein a hollow cylindrical shell gap (3) which is formed between a metal outer shell (1) and a metal inner shell (2) is filled with a concrete aggregate which has a minimum particle size and the residual volume is subsequently filled with a suspension of cement, water and additives, characterised in that two partial volumes which are concentric with each other are formed in the shell gap by means of a diaphragm (8), the passageway openings of which are smaller than said minimum particle size, and the concrete aggregate as well as the suspension are each introduced into only one of the two partial volumes.
  2. A method according to claim 1, characterised in that the diaphragm (8) is formed from perforated screens or perforated plates, or wire braid.
  3. A method according to claims 1 or 2, characterised in that the diaphragm has passageway openings with an opening width between 2 and 4 mm.
  4. A method according to any one of claims 1 to 3, characterised in that the diaphragm (8) is formed by the introduction of open and/or closed diaphragm sections (81, 82) between thermally conducting radial spacers (4) which extend between the inner shell and the outer shell and against which the diaphragm sections are seated.
  5. A method according to any one of claims 1 to 3, characterised in that the diaphragm (8) is placed on an inner partial spacer arrangement (41) of thermally conducting radial spacers (4) which extend between the inner shell and the outer shell, and an additional, outer partial spacer arrangement (42), which is screwed to the inner shell, is placed on the diaphragm.
  6. A method according to claim 5, characterised in that the diaphragm, the inner partial spacer arrangement (41) and the outer partial spacer arrangement (42) are placed on each other in the region of longitudinal beads (9) which correspond to each other.
  7. A method according to claims 5 or 6, characterised in that each two adjacent radial partial spacers of the outer partial spacer arrangement (42) are joined to reach other by an outer bridge (10).
  8. A method according to any one of claims 1 to 7, characterised in that the diaphragm is fixed in position by welds.
  9. A method according to any one of claims 1 to 8, characterised in that the concrete aggregate and the suspension are introduced into the same partial volume.
  10. A method according to any one of claims 1 to 9, characterised in that the concrete aggregate is introduced into the partial volume adjacent to the inner shell.
EP99125003A 1999-12-15 1999-12-15 Method for manufacturing a transport and/or storage container for radioactive materials Expired - Lifetime EP1122744B1 (en)

Priority Applications (15)

Application Number Priority Date Filing Date Title
DE59903429T DE59903429D1 (en) 1999-12-15 1999-12-15 Process for producing a transport and / or storage container for radioactive objects
EP99125003A EP1122744B1 (en) 1999-12-15 1999-12-15 Method for manufacturing a transport and/or storage container for radioactive materials
AT99125003T ATE227880T1 (en) 1999-12-15 1999-12-15 METHOD FOR PRODUCING A TRANSPORT AND/OR STORAGE CONTAINER FOR RADIOACTIVE ITEMS
ES99125003T ES2182452T3 (en) 1999-12-15 1999-12-15 PROCEDURE FOR MANUFACTURING A TRANSPORT CONTAINER AND / OR STORAGE OF RADIOACTIVE OBJECTS.
TW089124260A TW483005B (en) 1999-12-15 2000-11-16 A method of manufacturing a transport and/or storage container for radioactive articles
US09/728,604 US6438190B2 (en) 1999-12-15 2000-12-01 Making storage/transport container for radioactive material
CA002327663A CA2327663A1 (en) 1999-12-15 2000-12-06 A method of manufacturing a transport and/or storage container for radioactive articles
EA200001160A EA002394B1 (en) 1999-12-15 2000-12-07 Method for manufacturing a transport and/or storage container for radioactive materials
UA2000127076A UA67781C2 (en) 1999-12-15 2000-12-08 Method for producing a container for transporting or storing radioactive articles
BG105036A BG64066B1 (en) 1999-12-15 2000-12-08 Method for the preparation of a shipment and/or storage container for radioactive objects
CZ20004597A CZ293365B6 (en) 1999-12-15 2000-12-08 Process for producing transport and/or storage container for radioactive objects
SK1874-2000A SK284611B6 (en) 1999-12-15 2000-12-08 Process for producing transport and/or storage container for radioactive objects
JP2000377626A JP4683716B2 (en) 1999-12-15 2000-12-12 Method for producing a transport container and / or storage container for radioactive material
KR1020000075393A KR100746929B1 (en) 1999-12-15 2000-12-12 A method of manufacturing a transport and/or storage container for radioactive articles
CNB001356852A CN1152387C (en) 1999-12-15 2000-12-15 Method for making transport and/or storage container for radial objects

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
EP99125003A EP1122744B1 (en) 1999-12-15 1999-12-15 Method for manufacturing a transport and/or storage container for radioactive materials

Publications (2)

Publication Number Publication Date
EP1122744A1 EP1122744A1 (en) 2001-08-08
EP1122744B1 true EP1122744B1 (en) 2002-11-13

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EP99125003A Expired - Lifetime EP1122744B1 (en) 1999-12-15 1999-12-15 Method for manufacturing a transport and/or storage container for radioactive materials

Country Status (15)

Country Link
US (1) US6438190B2 (en)
EP (1) EP1122744B1 (en)
JP (1) JP4683716B2 (en)
KR (1) KR100746929B1 (en)
CN (1) CN1152387C (en)
AT (1) ATE227880T1 (en)
BG (1) BG64066B1 (en)
CA (1) CA2327663A1 (en)
CZ (1) CZ293365B6 (en)
DE (1) DE59903429D1 (en)
EA (1) EA002394B1 (en)
ES (1) ES2182452T3 (en)
SK (1) SK284611B6 (en)
TW (1) TW483005B (en)
UA (1) UA67781C2 (en)

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FR2915307B1 (en) * 2007-04-18 2013-04-19 Tn Int CONTAINER FOR THE TRANSPORT AND / OR STORAGE OF NUCLEAR MATERIALS, THE CONTAINER COMPRISING A MOBILE THERMAL CONDUCTION STRUCTURE.
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CN102314954A (en) * 2011-09-06 2012-01-11 原子高科股份有限公司 Storage and transportation container of primary neutron source component for starting nuclear reactor
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CN104751925B (en) * 2013-12-29 2017-09-29 西安核设备有限公司 A kind of CNFC 3G fresh fuels shipping container manufacture method
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CN1152387C (en) 2004-06-02
CN1300079A (en) 2001-06-20
CZ293365B6 (en) 2004-04-14
JP2001201590A (en) 2001-07-27
ATE227880T1 (en) 2002-11-15
JP4683716B2 (en) 2011-05-18
US20010021237A1 (en) 2001-09-13
BG64066B1 (en) 2003-11-28
KR20010062330A (en) 2001-07-07
BG105036A (en) 2001-07-31
KR100746929B1 (en) 2007-08-08
ES2182452T3 (en) 2003-03-01
UA67781C2 (en) 2004-07-15
TW483005B (en) 2002-04-11
SK18742000A3 (en) 2001-10-08
CA2327663A1 (en) 2001-06-15
EA002394B1 (en) 2002-04-25
CZ20004597A3 (en) 2001-08-15
US6438190B2 (en) 2002-08-20
EP1122744A1 (en) 2001-08-08
SK284611B6 (en) 2005-07-01
DE59903429D1 (en) 2002-12-19
EA200001160A1 (en) 2001-06-25

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