EP0171773B1 - Storage container for isolated fuel rods of irradiated nuclear reactor fuel elements - Google Patents

Storage container for isolated fuel rods of irradiated nuclear reactor fuel elements Download PDF

Info

Publication number
EP0171773B1
EP0171773B1 EP85110053A EP85110053A EP0171773B1 EP 0171773 B1 EP0171773 B1 EP 0171773B1 EP 85110053 A EP85110053 A EP 85110053A EP 85110053 A EP85110053 A EP 85110053A EP 0171773 B1 EP0171773 B1 EP 0171773B1
Authority
EP
European Patent Office
Prior art keywords
fuel
fuel rod
containers
container
insert basket
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
EP85110053A
Other languages
German (de)
French (fr)
Other versions
EP0171773A2 (en
EP0171773A3 (en
Inventor
Helfrid Dr. Lahr
Bernd Pontani
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 EP0171773A2 publication Critical patent/EP0171773A2/en
Publication of EP0171773A3 publication Critical patent/EP0171773A3/en
Application granted granted Critical
Publication of EP0171773B1 publication Critical patent/EP0171773B1/en
Expired legal-status Critical Current

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
    • 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
    • G21F5/012—Fuel element racks in the containers

Definitions

  • the invention relates to a storage container referred to in the preamble of claim 1.
  • Shielded transport and storage containers made of spherulitic cast iron or steel are used for the transport and storage of irradiated nuclear reactor fuel elements.
  • the interior of the container can have a round or square cross section.
  • Containers with a circular interior have the advantage that they can be manufactured more easily and offer very good storage space utilization.
  • the irradiated fuel elements are accommodated in special insert baskets in these storage containers
  • the fuel rods removed from the fuel assemblies are filled in tightly packed cans which geometrically correspond to a fuel assembly (DE-OS-3 222 822).
  • the filled cans are inserted into the receiving shafts of the insert basket which are designed for the fuel elements.
  • a major technical problem in the storage of individual fuel rods in the densest possible packing in a storage container is the temperature control of this storage container. Due to the heat of decay of the radioactive fuel, there is a possibility that the temperature inside the container will increase inadmissibly. The heat dissipation from the inside of the fuel rod pack creates problems. This heat dissipation problem can therefore lead to limitations in the packing density or to a longer previous decay time of the fuel elements before they are introduced into the storage container.
  • the invention has for its object to provide a container of the type described in such a way that good heat dissipation from the storage container is achieved and an inadmissible heat impairment of the fuel rods is prevented.
  • the object is achieved in that the individual sleeves in the insert basket are arranged in a circle, that the cross section of the sleeves is in the form of a segment of a circle, that the sleeves are loaded with hold-down springs on their upper end faces, and that the sleeve segments are limited in radial extension to the center in such a way that an empty square shaft is formed in the middle of the insert basket.
  • the circular segment-shaped design of the respective fuel rod bushing results in a good adaptation to the round storage space cross section.
  • the curved back surfaces of the fuel rod liners fit the circular inner wall of the container and thus ensure good heat transfer between the liners and the storage container.
  • the hold-down springs By means of the hold-down springs, the respective fuel rod sleeve is pressed against the bottom of the storage container in the direction parallel to the axis, so that good heat transfer is also guaranteed there.
  • the empty square shaft that arises in the middle of the storage room enables the scrap that is produced when the fuel rods are separated, i. H. the spacers and the like to put in the middle.
  • This structural material of the disassembled fuel elements has a considerably lower heat output than the fuel rods. It is also insensitive to the effects of heat. It can endure heat increases without protection. In contrast, the irradiated fuel rods must not exceed the temperature values prescribed by the approval, otherwise leakages could occur. This would result in the escape of fission gases or
  • An advantageous embodiment of the invention is characterized by the features mentioned in claim 2.
  • the double-walled separating segments each create a cavity between two fuel rod liners arranged side by side. This division of the circular storage space allows fuel rod liners with the same configuration to be used. In this case, one fuel rod can each receive the fuel rods of a fuel assembly in an advantageous manner.
  • the cavities in the separating segments offer the possibility of introducing neutron-absorbing substances or heat-conducting substances. The essence of this embodiment of the invention is seen in the fact that the fuel rod liners can have the same configurations.
  • a further advantageous embodiment of the invention is characterized in the features of subclaim 3.
  • the sloping muzzle bars, which work together with the sloping run-up surfaces in the insert basket, and the lower guide surfaces eliminate any play that may exist between the curved back surfaces of the fuel rod liners and the circular inner wall of the storage container.
  • the invention provides a storage container for receiving individual fuel rods, in which fuel rods can be stored, which have a higher heat output. After the fuel elements have been removed from the reactor storage pool and separated, the fuel rods can therefore be brought directly into the container intended for final storage. Another intermediate storage to decrease the temperature is not necessary.
  • a final storage container 11 made of steel (FIGS. 1 and 2) has a circular storage space 13 for receiving individual fuel rods 15 of some irradiated nuclear reactor fuel elements.
  • the fuel rods 15 are packed tightly in four fuel rod liners 17 in the form of segments of a circle. These cans 17 are closed after loading.
  • the fuel rod liners 17 are inserted into an insert basket 19 located in the circular storage space 13. Seen in cross section, this insert basket 19 has a centrally arranged square shaft 21, from the corners of which diagonal partition walls 23 strive toward the container inner wall 24 of the storage space 13. As a result, four receiving shafts 25 are formed, in which the fuel rod liners 17 are located.
  • the fuel rod liners 17 are designed in the shape of a segment of a circle. Their rear walls 27 abutting against the inner wall 24 of the container are each arc-shaped. The curvature of the rear walls 27 corresponds to the curvature of the inner container wall 24. The radially extending side surfaces 29 of the liners 17 lie parallel to the partition walls 23. The inwardly closing wall 31, which is designed in the form of a lattice, each fuel rod liner 17 runs parallel to the respective side of the square one Middle shaft 21.
  • the fuel rod liners 17 are flattened at their transition from the radial side surfaces 29 to their arcuate rear wall 27.
  • Each fuel rod can 17 can receive the fuel rods from two disassembled irradiated nuclear reactor fuel elements.
  • the loading is carried out while the fuel rod liner 17 is lying down.
  • the fuel rod liner 17 lies on the rear wall 27.
  • the grid-shaped wall 31 has not yet been inserted.
  • the fuel rods are loaded into the fuel rod sleeve 17 via this open area.
  • the wall 31 is welded in after loading.
  • the loading opening of the final storage container 11 is closed with a step-shaped cover 33 (FIG. 1), which is screwed onto a corresponding projection 37 of the loading opening, including a seal (not shown here) with screw bolts 35.
  • a further closure cover 41 is arranged above this screwed cover 33, which is inserted into the loading opening and welded to the container wall 43.
  • the repository container 11 is placed in a shield transport container 45 in the illustration shown (FIGS. 1 and 2).
  • the loading opening of the shielding transport container 45 is secured by a screwed-on closure cap 47.
  • a polyethylene layer 49 is used in the inner wall of the shielding transport container 45 for neutron shielding.
  • the shielding transport container 45 is provided with support pins 51 fastened to the outer circumference.
  • the filled fuel rod liners 17 each have a handling block 55 on their upper end faces 53, to which suitable lifting devices can engage.
  • the upper end faces 53 of the fuel rod liners 17 are acted upon by hold-down springs 57 which are supported on the screwed-on cover 33.
  • the individual fuel rods 15 are introduced into the segment-shaped fuel rod liners 17. After loading, the fuel rod liners 17 are closed. The fuel rod liners 17 are gripped above the edge handling block 55 and inserted into a receiving shaft 25 of the insert basket 19. Hold-down springs 57 are placed on the upper end face 53 of the fuel rod liners 17, which press against the fuel rod liners 17 when the first sealing cap 33 is screwed on and thereby cause the fuel rod liners 17 to bear against the bottom of the container. The fuel rod liners 17 rest with their arc-shaped rear walls 27 on the inner wall 24 of the container. Good heat transfer to the container body is guaranteed.
  • the empty square central shaft 21 is filled with fuel element structural parts 63 which were separated when the fuel elements were disassembled. These are the head and foot pieces as well as the spacers with the control rod guide tubes. The fuel assembly structural parts are compacted.
  • FIG. 3 shows the cross section of a circular storage space 71 of a final storage container 73 of a modified embodiment.
  • a modified insert basket 75 is inserted in the storage space 71 and likewise has a square central shaft 77 in the middle of the storage space 71.
  • This square central shaft 77 is held by partitions 78, 79 which extend from the corners and which are supported radially against the inner wall 81 of the container.
  • the partitions 78 and 79 each of a pair are by an arcuate rear wall 83 connected to each other.
  • a pair of dividing walls 87, 89 likewise runs from the center of the side surfaces 85 of the square central shaft 77 to the container inner wall 81, the dividing walls 87 and 89 of which are each connected at their ends by a short rear wall 91.
  • the rear walls 83 and 91 of the pairs of dividing walls 78, 79 and 87, 89 facing the inner wall 81 of the container are formed in an arc shape.
  • a fuel rod sleeve 93 in the form of a segment of a circle.
  • These fuel rod liners 93 each have an arcuate rear wall 95.
  • the radial side surfaces 97 of the fuel rod liners 95 run parallel to the respectively adjacent partitions of the partition wall pairs 78, 79 and 87, 89.
  • the inner end surface 99 of the fuel rod liners 93 is slightly curved.
  • each fuel rod liner 93 can accommodate the fuel rods 101 of an individual fuel assembly.
  • the fuel rod liners of this embodiment are loaded on the end face.
  • the cross section of the fuel rod liners 93 is desirably always the same, so as not to complicate the method for loading the fuel rod liners 93 on the end face and to be able to carry it out without modifications.
  • the upper end wall is welded onto the respective fuel rod sleeve 93.
  • a suction pipe 103 is provided in the circular storage space 81 in order to be able to remove the water from the container 73 after loading.
  • inclined guide webs 105 are attached in the upper region. These upper guide webs 105 interact with inclined run-up surfaces 106, which are introduced into the respectively adjacent partition wall of a pair of partition walls 78 ', 79' or 87 ', 89' of the insert basket 75 '.
  • inclined guide surfaces 109 are attached at the lower end of the insert basket 75 'in the vicinity of the bottom of the storage container 73'. The guide webs 105 and the guide surfaces 109 are intended to press the fuel rod liners 93 'against the inner wall 81' of the container when they are inserted.

Description

Die Erfindung betrifft einen Lagerbehälter der im Oberbegriff des Anspruches 1 bezeichneten Art.The invention relates to a storage container referred to in the preamble of claim 1.

Für den Transport und die Lagerung von bestrahlten Kernreaktorbrennelementen werden Abschirmtransport- und Lagerbehälter aus sphärolithischem Gußeisen oder Stahl benutzt. Der Innenraum der Behälter kann einen runden oder quadratischen Querschnitt aufweisen. Behälter mit kreisförmigem Innenraum haben den Vorteil, daß sie einfacher gefertigt werden können und eine sehr gute Lagerraumausnutzung bieten. In diesen Lagerbehältern werden die bestrahlten Brennelemente in speziellen Einsatzkörben aufgenommenShielded transport and storage containers made of spherulitic cast iron or steel are used for the transport and storage of irradiated nuclear reactor fuel elements. The interior of the container can have a round or square cross section. Containers with a circular interior have the advantage that they can be manufactured more easily and offer very good storage space utilization. The irradiated fuel elements are accommodated in special insert baskets in these storage containers

Neben der Aufnahme von vollständigen Brennelementen wurde bereits vorgeschlagen, die Brennelemente zu zerlegen und die vereinzelten Brennstäbe dieser Brennelemente in einen Lagerbehälter in dichter Packung einzugeben. Es ist dadurch eine wesentliche Platzersparnis möglich. In einem Lagerbehälter kann so eine größere Anzahl von Brennelementen untergebracht werden (EP-PS-0 005 623).In addition to the inclusion of complete fuel assemblies, it has already been proposed to disassemble the fuel assemblies and to put the individual fuel rods of these fuel assemblies in a storage container in a tight packing. This makes it possible to save a significant amount of space. A larger number of fuel elements can be accommodated in a storage container (EP-PS-0 005 623).

Nach einem bekannten Vorschlag des Standes der Technik werden die aus den Brennelementen ausgebauten Brennstäbe in dichter Packung in Büchsen eingefüllt, die geometrisch etwa einem Brennelement entsprechen (DE-OS-3 222 822). Die gefüllten Büchsen werden in die an sich für die Brennelemente ausgebildeten Aufnahmeschächte des Einsatzkorbes eingesetzt.According to a known proposal of the prior art, the fuel rods removed from the fuel assemblies are filled in tightly packed cans which geometrically correspond to a fuel assembly (DE-OS-3 222 822). The filled cans are inserted into the receiving shafts of the insert basket which are designed for the fuel elements.

Ein wesentliches technisches Problem der Lagerung von vereinzelten Brennstäben in möglichst dichter Packung in einem Lagerbehälter stellt die Temperaturbeherrschung dieses Lagergebindes dar. Aufgrund der Nachzerfallswärme des radioaktiven Brennstoffes besteht die Möglichkeit, daß sich die Temperatur innerhalb des Gebindes unzulässig erhöht. Die Wärmeabfuhr aus dem Inneren der Brennstabpackung bereitet Probleme. Dieses Wärmeabfuhrproblem kann daher zu Begrenzungen der Packungsdichte oder zu einer längeren vorherigen Abklingzeit der Brennelemente bis zum Einbringen in den Lagerbehälter führen.A major technical problem in the storage of individual fuel rods in the densest possible packing in a storage container is the temperature control of this storage container. Due to the heat of decay of the radioactive fuel, there is a possibility that the temperature inside the container will increase inadmissibly. The heat dissipation from the inside of the fuel rod pack creates problems. This heat dissipation problem can therefore lead to limitations in the packing density or to a longer previous decay time of the fuel elements before they are introduced into the storage container.

Der Erfindung liegt die Aufgabe zugrunde, einen Behälter der eingangs beschriebenen Art derart auszubilden, daß eine gute Wärmeabfuhr aus dem Lagergebinde erreicht und eine unzulässige Wärmebeeinträchtigung der Brennstäbe verhindert wird.The invention has for its object to provide a container of the type described in such a way that good heat dissipation from the storage container is achieved and an inadmissible heat impairment of the fuel rods is prevented.

Die Aufgabe wird erfindungsgemäß dadurch gelöst, daß die einzelnen Büchsen im Einsatzkorb kreisförmig angeordnet sind, daß der Querschnitt der Büchsen kreissegmentförmig ist, daß die Büchsen auf ihren oberen Stirnseiten mit Niederhaltefedern beaufschlagt werden und daß die Büchsensegmente in radialer Ausdehnung zur Mitte derart begrenzt sind, daß in der Mitte des Einsatzkorbes ein leerer quadratischer Schacht gebildet wird.The object is achieved in that the individual sleeves in the insert basket are arranged in a circle, that the cross section of the sleeves is in the form of a segment of a circle, that the sleeves are loaded with hold-down springs on their upper end faces, and that the sleeve segments are limited in radial extension to the center in such a way that an empty square shaft is formed in the middle of the insert basket.

Die kreissegmentförmige Ausbildung der jeweiligen Brennstabbüchse ergibt eine gute Anpassung an den runden Lagerraumquerschnitt. Die gebogenen Rückenflächen der Brennstabbüchsen liegen passend an der kreisförmigen Innenwand des Behälters und sorgen dadurch für einen guten Wärmeübergang zwischen Büchsen und Lagerbehälter. Durch die Niederhaltefedern wird die jeweilige Brennstabbüchse in achsparalleler Richtung gegen den Boden des Lagerbehälters gedrückt, so daß auch dort die gute Wärmeübertragung gewährleistet ist. Der in der Lagerraummitte entstehende leere quadratische Schacht gibt die Möglichkeit, den bei der Vereinzelung der Brennstäbe anfallenden Schrott, d. h. die Abstandshalter und ähnliches, in der Mitte einzubringen. Dieses Strukturmaterial der zerlegten Brennelemente weist eine erheblich geringere Wärmeleistung als die Brennstäbe auf. Außerdem ist es unempfindlich gegen Wärmeeinfluß. Es kann ungeschützt Wärmeerhöhungen ertragen. Im Gegensatz dazu dürfen die bestrahlten Brennstäbe die genehmigungsbehördlich vorgeschriebenen Temperaturwerte nicht überschreiten, da ansonsten Leckagen entstehen könnten. Ein Entweichen von Spaltgasen oder anderen radioaktivem Inventar wäre die Folge.The circular segment-shaped design of the respective fuel rod bushing results in a good adaptation to the round storage space cross section. The curved back surfaces of the fuel rod liners fit the circular inner wall of the container and thus ensure good heat transfer between the liners and the storage container. By means of the hold-down springs, the respective fuel rod sleeve is pressed against the bottom of the storage container in the direction parallel to the axis, so that good heat transfer is also guaranteed there. The empty square shaft that arises in the middle of the storage room enables the scrap that is produced when the fuel rods are separated, i. H. the spacers and the like to put in the middle. This structural material of the disassembled fuel elements has a considerably lower heat output than the fuel rods. It is also insensitive to the effects of heat. It can endure heat increases without protection. In contrast, the irradiated fuel rods must not exceed the temperature values prescribed by the approval, otherwise leakages could occur. This would result in the escape of fission gases or other radioactive inventory.

Eine vorteilhafte Ausgestaltung der Erfindung wird durch die im Anspruch 2 genannten Merkmale gekennzeichnet. Die doppelwandigen Trennsegmente ergeben jeweils einen Hohlraum zwischen zwei nebeneinander angeordneten Brennstabbüchsen. Durch diese Aufteilung des kreisförmigen Lagerraumes können Brennstabbüchsen mit der selben Konfiguration eingesetzt werden. Dabei wird in vorteilhafter Weise jeweils eine Brennstabbüchse die Brennstäbe eines Brennelementes aufnehmen. Darüber hinaus ergeben die Hohlräume in den Trennsegmenten die Möglichkeit, neutronenabsorbierende Stoffe oder wärmeleitende Stoffe einzubringen. Das wesentliche dieser Ausgestaltung der Erfindung wird darin gesehen, daß die Brennstabbüchsen gleiche Konfigurationen aufweisen können.An advantageous embodiment of the invention is characterized by the features mentioned in claim 2. The double-walled separating segments each create a cavity between two fuel rod liners arranged side by side. This division of the circular storage space allows fuel rod liners with the same configuration to be used. In this case, one fuel rod can each receive the fuel rods of a fuel assembly in an advantageous manner. In addition, the cavities in the separating segments offer the possibility of introducing neutron-absorbing substances or heat-conducting substances. The essence of this embodiment of the invention is seen in the fact that the fuel rod liners can have the same configurations.

Eine weitere vorteilhafte Ausgestaltung der Erfindung wird in den Merkmalen des Unteranspruches 3 gekennzeichnet. Die schrägen Mhrungsstege, die mit den schrägen Auflaufflächen im Einsatzkorb zusammenarbeiten, und die unteren Führungsflächen beheben ein möglicherweise vorhandenes Spiel zwischen den gebogenen Rückenflächen der Brennstabbüchsen und der kreisförmigen Innenwand des Lagerbehälters.A further advantageous embodiment of the invention is characterized in the features of subclaim 3. The sloping muzzle bars, which work together with the sloping run-up surfaces in the insert basket, and the lower guide surfaces eliminate any play that may exist between the curved back surfaces of the fuel rod liners and the circular inner wall of the storage container.

Durch die Erfindung wird ein, Lagerbehälter zur Aufnahme von vereinzelten Brennstäben geschaffen, in den Brennstäbe eingelagert werden können, die eine höhere Nachwärmeleistung haben. Die Brennstäbe können daher nach der Herausnahme der Brennelemente aus dem Reaktorlagerbecken und ihrem Vereinzeln direkt in den für die Endlagerung vorgesehenen Behälter verbracht werden. Eine weitere Zwischenlagerung zum Abnehmen der Temperatur ist nicht notwendig.The invention provides a storage container for receiving individual fuel rods, in which fuel rods can be stored, which have a higher heat output. After the fuel elements have been removed from the reactor storage pool and separated, the fuel rods can therefore be brought directly into the container intended for final storage. Another intermediate storage to decrease the temperature is not necessary.

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

  • Fig. 1 einen Längsschnitt eines in einem Abschirmtransportbehälter angeordneten Endlagerbehälters,
  • Fig. 2 einen Querschnitt gemäß Linie 11 - II in Fig. 1,
  • Fig. 3 eine zweite Ausführungsform eines runden Einsatzkorbes mit kreissegmentförmigen Brennstabbüchsen,
  • Fig. 4 eine Teildraufsicht auf die Anordnung einer Brennstabbüchse in ihrem Aufnahmeschacht eines Einsatzkorbes einer weiteren Ausführungsform,
  • Fig. 5 eine geschnittene Ansicht der Fig. 4 gemäß Linie V-V,
  • Fig. 6 die in Fig. 5 dargestellte Brennstabbüchse in vollständig in den Einsatzkorb eingesetzter Lage.
Based on the drawing, a Embodiment explained in more detail. It shows
  • 1 shows a longitudinal section of an end storage container arranged in a shielding transport container,
  • 2 shows a cross section along line 11 - II in FIG. 1,
  • 3 shows a second embodiment of a round insert basket with fuel rod liners in the form of segments of a circle,
  • 4 shows a partial top view of the arrangement of a fuel rod can in its receiving shaft of an insert basket of a further embodiment,
  • 5 is a sectional view of FIG. 4 along line VV,
  • Fig. 6, the fuel rod can shown in Fig. 5 in the fully inserted position in the insert basket.

Ein Endlagerbehälter 11 aus Stahl (Fig. 1 und 2) weist einen kreisförmigen Lagerraum 13 zur Aufnahme von einzelnen Brennstäben 15 einiger bestrahlter Kernreaktorbrennelemente auf. Die Brennstäbe 15 sind in vier kreissegmentförmige Brennstabbüchsen 17 dicht gepackt. Diese Büchsen 17 sind nach ihrem Beladen verschlossen. Die Brennstabbüchsen 17 sind in einem sich in dem kreisförmigen Lagerraum 13 befindlichen Einsatzkorb 19 eingesetzt. Dieser Einsatzkorb 19 weist im Querschnitt gesehen einen mittig angeordneten quadratischen Schacht 21 auf, von dessen Ecken diagonale Trennwände 23 zur Behälterinnenwand 24 des Lagerraumes 13 streben. Dadurch werden vier Aufnahmeschächte 25 gebildet, in denen sich die Brennstabbüchsen 17 befinden.A final storage container 11 made of steel (FIGS. 1 and 2) has a circular storage space 13 for receiving individual fuel rods 15 of some irradiated nuclear reactor fuel elements. The fuel rods 15 are packed tightly in four fuel rod liners 17 in the form of segments of a circle. These cans 17 are closed after loading. The fuel rod liners 17 are inserted into an insert basket 19 located in the circular storage space 13. Seen in cross section, this insert basket 19 has a centrally arranged square shaft 21, from the corners of which diagonal partition walls 23 strive toward the container inner wall 24 of the storage space 13. As a result, four receiving shafts 25 are formed, in which the fuel rod liners 17 are located.

Die Brennstabbüchsen 17 sind kreissegmentförmig ausgebildet. Ihre gegen die Behälterinnenwand 24 anliegenden Rückwände 27 sind jeweils bogenförmig ausgebildet. Die Krümmung der Rückwände 27 entspricht der Krümmung der Behälterinnenwand 24. Die radial verlaufenden Seitenflächen 29 der Büchsen 17 liegen parallel zu den Trennwänden 23. Die nach innen abschließende Wand 31, die gitterförmig ausgebildet ist, jeder Brennstabbüchse 17 verläuft parallel zu der jeweiligen Seite des quadratischen Mittelschachtes 21.The fuel rod liners 17 are designed in the shape of a segment of a circle. Their rear walls 27 abutting against the inner wall 24 of the container are each arc-shaped. The curvature of the rear walls 27 corresponds to the curvature of the inner container wall 24. The radially extending side surfaces 29 of the liners 17 lie parallel to the partition walls 23. The inwardly closing wall 31, which is designed in the form of a lattice, each fuel rod liner 17 runs parallel to the respective side of the square one Middle shaft 21.

Die Brennstabbüchsen 17 sind an ihrem Übergang von den radialen Seitenflächen 29 zu ihrer bogenförmigen Rückwand 27 abgeflacht ausgebildet.The fuel rod liners 17 are flattened at their transition from the radial side surfaces 29 to their arcuate rear wall 27.

Jede Brennstabbüchse 17 kann die Brennstäbe von zwei zerlegten bestrahlten Kernreaktorbrennelementen aufnehmen. Die Beladung wird im Liegen der Brennstabbüchse 17 vorgenommen. Die Brennstabbüchse 17 liegt dabei auf der Rückwand 27. Die gitterförmige Wand 31 ist noch nicht eingesetzt. Über diesen offenen Bereich werden die Brennstäbe in die Brennstabbüchse 17 geladen. Die Wand 31 wird nach dem Beladen eingeschweißt.Each fuel rod can 17 can receive the fuel rods from two disassembled irradiated nuclear reactor fuel elements. The loading is carried out while the fuel rod liner 17 is lying down. The fuel rod liner 17 lies on the rear wall 27. The grid-shaped wall 31 has not yet been inserted. The fuel rods are loaded into the fuel rod sleeve 17 via this open area. The wall 31 is welded in after loading.

Die Beladeöffnung des Endlagerbehälters 11 ist mit einem stufenförmigen Deckel 33 (Fig. 1) verschlossen, der unter Einschluß einer hier nicht gezeigten Dichtung mit Schraubbolzen 35 auf einen entsprechenden Vorsprung 37 der Beladeöffnung geschraubt ist. Über diesem aufgeschraubten Deckel 33 ist ein weiterer Verschlußdeckel 41 angeordnet, der in die Beladeöffnung eingesetzt und mit der Behälterwand 43 verschweißt ist.The loading opening of the final storage container 11 is closed with a step-shaped cover 33 (FIG. 1), which is screwed onto a corresponding projection 37 of the loading opening, including a seal (not shown here) with screw bolts 35. A further closure cover 41 is arranged above this screwed cover 33, which is inserted into the loading opening and welded to the container wall 43.

Der Endlagerbehälter 11 ist in der gezeigten Darstellung (Fig. 1 und 2) in einen Abschirmtransportbehälter 45 gesetzt. Die Beladeöffnung des Abschirmtransportbehälters 45 ist über einen aufgeschraubten Verschlußdeckel 47 gesichert. In der Innenwand des Abschirmtransportbehälters 45 ist zur Neutronenabschirmung eine Polyäthylenschicht 49 eingesetzt. Der Abschirmtransportbehälter 45 ist mit am Au- ßenumfang befestigten Tragzapfen 51 versehen.The repository container 11 is placed in a shield transport container 45 in the illustration shown (FIGS. 1 and 2). The loading opening of the shielding transport container 45 is secured by a screwed-on closure cap 47. A polyethylene layer 49 is used in the inner wall of the shielding transport container 45 for neutron shielding. The shielding transport container 45 is provided with support pins 51 fastened to the outer circumference.

Die gefüllten Brennstabbüchsen 17 weisen auf ihren oberen Stirnseiten 53 jeweils einen Handhabungsklotz 55 auf, an den geeignete Hebezeuge angreifen können. Die oberen Stirnseiten 53 der Brennstabbüchsen 17 werden durch Niederhaltefedern 57 beaufschlagt, die sich an dem angeschraubten Deckel 33 abstützen.The filled fuel rod liners 17 each have a handling block 55 on their upper end faces 53, to which suitable lifting devices can engage. The upper end faces 53 of the fuel rod liners 17 are acted upon by hold-down springs 57 which are supported on the screwed-on cover 33.

Die Wirkungsweise der vorstehend beschriebenen Vorrichtungen ist wie folgt.The operation of the devices described above is as follows.

Die vereinzelten Brennstäbe 15 werden in die segmentförmigen Brennstabbüchsen 17 eingebracht. Nach dem Beladen werden die Brennstabbüchsen 17 geschlossen. Ober den Randhabungsklotz 55 werden die Brennstabbüchsen 17 erfaßt und in jeweils einen Aufnahmeschacht 25 des Einsatzkorbes 19 eingesetzt. Auf die obere Stirnseite 53 der Brennstabbüchsen 17 werden Niederhaltefedern 57 gelegt, die beim Anschrauben des ersten Verschlußdeckels 33 gegen die Brennstabbüchsen 17 pressen und dadurch ein ständiges Anliegen der Brennstabbüchsen 17 gegen den Behälterboden bewirken. Die Brennstabbüchsen 17 liegen mit ihren bogenförmigen Rückwänden 27 an der Behälterinnenwand 24 an. Eine gute Wärmeübertragung zum Behälterkörper ist gewährleistet.The individual fuel rods 15 are introduced into the segment-shaped fuel rod liners 17. After loading, the fuel rod liners 17 are closed. The fuel rod liners 17 are gripped above the edge handling block 55 and inserted into a receiving shaft 25 of the insert basket 19. Hold-down springs 57 are placed on the upper end face 53 of the fuel rod liners 17, which press against the fuel rod liners 17 when the first sealing cap 33 is screwed on and thereby cause the fuel rod liners 17 to bear against the bottom of the container. The fuel rod liners 17 rest with their arc-shaped rear walls 27 on the inner wall 24 of the container. Good heat transfer to the container body is guaranteed.

In der Mitte des Lagerbehälters 11 wird der leere quadratische Mittelschacht 21 mit Brennelementstrukturteilen 63 gefüllt, die bei dem Zerlegen der Brennelemente separiert wurden. Dabei handelt es sich um die Kopf- und Fußstücke sowie die Abstandshalter mit den Steuerstabführungsrohren. Die Brennelementstrukturteile sind kompaktiert.In the middle of the storage container 11, the empty square central shaft 21 is filled with fuel element structural parts 63 which were separated when the fuel elements were disassembled. These are the head and foot pieces as well as the spacers with the control rod guide tubes. The fuel assembly structural parts are compacted.

In der Fig. 3 wird der Querschnitt eines kreisförmigen Lagerraumes 71 eines Endlagerbehälter 73 einer modifizierten Ausführung gezeigt. In dem Lagerraum 71 ist ein modifizierter Einsatzkorb 75 eingesetzt, der in der Mitte des Lagerraumes 71 ebenfalls einen quadratischen Mittelschacht 77 aufweist. Dieser quadratische Mittelschacht 77 wird durch von den Ecken ausgehenden Trennwandpaaren 78, 79 gehalten, die sich radial gegen die Behälterinnenwand 81 abstützen. Die Trennwände 78 und 79 je eines Paares sind durch eine bogenförmigen Rückwand 83 miteinander verbunden. Von der Mitte der Seitenflächen 85 des quadratischen Mittelschachtes 77 verläuft ebenfalls jeweils ein Trennwandpaar 87, 89 zur Behälterinnenwand 81, deren Trennwände 87 und 89 jeweils an ihren Enden von einer kurzen Rückwand 91 miteinander verbunden sind. Die der Behälterinnenwand 81 zugewandten Rückwände 83 und 91 der Trennwandpaare 78, 79 bzw. 87, 89 sind dabei bogenförmig ausgebildet.3 shows the cross section of a circular storage space 71 of a final storage container 73 of a modified embodiment. A modified insert basket 75 is inserted in the storage space 71 and likewise has a square central shaft 77 in the middle of the storage space 71. This square central shaft 77 is held by partitions 78, 79 which extend from the corners and which are supported radially against the inner wall 81 of the container. The partitions 78 and 79 each of a pair are by an arcuate rear wall 83 connected to each other. A pair of dividing walls 87, 89 likewise runs from the center of the side surfaces 85 of the square central shaft 77 to the container inner wall 81, the dividing walls 87 and 89 of which are each connected at their ends by a short rear wall 91. The rear walls 83 and 91 of the pairs of dividing walls 78, 79 and 87, 89 facing the inner wall 81 of the container are formed in an arc shape.

Zwischen je einem Trennwandpaar 78, 79 einer Ecke und einem Trennwandpaar 87, 89 einer Seitenmitte ist je eine kreissegmentförmige Brennstabbüchse 93 angeordnet. Diese Brennstabbüchsen 93 weisen jeweils eine bogenförmige Rückwand 95 auf. Die radialen Seitenflächen 97 der Brennstabbüchsen 95 verlaufen parallel zu den jeweils benachbarten Trennwänden der Trennwandpaare 78, 79 bzw. 87, 89. Die innere Abschlußfläche 99 der Brennstabbüchsen 93 ist leicht gekrümmt ausgebildet.Between each of a pair of partitions 78, 79 in a corner and a pair of partitions 87, 89 in one side center is arranged a fuel rod sleeve 93 in the form of a segment of a circle. These fuel rod liners 93 each have an arcuate rear wall 95. The radial side surfaces 97 of the fuel rod liners 95 run parallel to the respectively adjacent partitions of the partition wall pairs 78, 79 and 87, 89. The inner end surface 99 of the fuel rod liners 93 is slightly curved.

In diesem in Fig. 3 gezeigten Ausführungsbeispiel sind acht Brennstabbüchsen 93 kreisförmig angeordnet. Jede Brennstabbüchse 93 kann die Brennstäbe 101 eines vereinzelten Brennelementes aufnehmen. Die Beladung der Brennstabbüchsen dieser Ausführungsform geschieht stirnseitig. Der Querschnitt der Brennstabbüchsen 93 ist in wünschenswerter Weise stets gleich ausgebildet, um das Verfahren zur stirnseitigen Beladung der Brennstabbüchsen 93 nicht zu komplizieren und ohne Abwandlungen durchführen zu können. Die obere Stirnwand wird nach dem Beladen auf die jeweilige Brennstabbüchse 93 aufgeschweißt.In this exemplary embodiment shown in FIG. 3, eight fuel rod liners 93 are arranged in a circle. Each fuel rod liner 93 can accommodate the fuel rods 101 of an individual fuel assembly. The fuel rod liners of this embodiment are loaded on the end face. The cross section of the fuel rod liners 93 is desirably always the same, so as not to complicate the method for loading the fuel rod liners 93 on the end face and to be able to carry it out without modifications. After loading, the upper end wall is welded onto the respective fuel rod sleeve 93.

Für eine nasse Beladung der Brennstabbüchsen 93, d. h. eine Beladung unter Wasser ist im kreisförmigen Lagerraum 81 ein Saugrohr 103 vorgesehen, um das Wasser nach der Beladung aus dem Behälter 73 entfernen zu können.For a wet loading of the fuel rod liners 93, i. H. a loading under water, a suction pipe 103 is provided in the circular storage space 81 in order to be able to remove the water from the container 73 after loading.

In den Fig. 4 bis 6 wird eine weitere Ausführungsform des Einsatzkorbes und der Brennstabbüchsen gemäß Fig. 3 gezeigt. Gleiche Teile erhielten gleiche mit einem Hochstrich versehene Bezugszeichen.4 to 6 show a further embodiment of the insert basket and the fuel rod liners according to FIG. 3. Identical parts were given the same reference numerals with a prime.

Auf den radialen Seitenflächen 79' jeder Brennstabbüchse 93' sind im oberen Bereich schräge Führungsstege 105 angebracht. Diese oberen Führungsstege 105 wirken mit schrägen Auflaufflächen 106 zusammen, die in der jeweils benachbarten Trennwand eines Trennwandpaares 78', 79' bzw. 87', 89' des Einsatzkorbes 75' eingebracht sind. Am unteren Ende des Einsatzkorbes 75' in der Nähe des Bodens des Lagerbehälters 73' sind nach außen verlaufende schräge Führungsflächen 109 angebracht. Die Führungsstege 105 und die Führungsflächen 109 sollen die Brennstabbüchsen 93' beim Einsetzen gegen die Behälterinnenwand 81' drücken.On the radial side surfaces 79 'of each fuel rod liner 93', inclined guide webs 105 are attached in the upper region. These upper guide webs 105 interact with inclined run-up surfaces 106, which are introduced into the respectively adjacent partition wall of a pair of partition walls 78 ', 79' or 87 ', 89' of the insert basket 75 '. At the lower end of the insert basket 75 'in the vicinity of the bottom of the storage container 73', outwardly inclined guide surfaces 109 are attached. The guide webs 105 and the guide surfaces 109 are intended to press the fuel rod liners 93 'against the inner wall 81' of the container when they are inserted.

BezugszeichenlisteReference symbol list

  • 11 Endlagerbehälter11 repository
  • 13 kreisförmiger Lagerraum13 circular storage room
  • 15 Brennstäbe15 fuel rods
  • 17 Brennstabbüchsen17 fuel rod cans
  • 19 Einsatzkorb19 insert basket
  • 21 quadratischer Mittelschacht21 square central shaft
  • 23 diagonale Trennwände23 diagonal partitions
  • 24 Behälterinnenwand24 inner container wall
  • 25 Aufnahmeschächte25 slots
  • 27 bogenförmige Rückwände27 arched rear walls
  • 29 radiale Seitenflächen29 radial side surfaces
  • 31 Gitterwände31 grid walls
  • 33 stufenförmiger Deckel33 stepped lid
  • 35 Schraubbolzen35 bolts
  • 37 Vorsprung37 head start
  • 41 Verschlußdeckel41 sealing cover
  • 43 Behälterwand43 container wall
  • 45 Abschirmtransportbehälter45 shielded transport containers
  • 47 Verschlußdeckel47 sealing cover
  • 49 Polyäthylenschicht49 polyethylene layer
  • 51 Tragzapfen51 trunnion
  • 53 obere Stirnseiten53 upper faces
  • 55 Handhabungsklotz55 handling blocks
  • 57 Niederhaltefedern57 hold-down springs
  • 63 Brennelementstrukturteile63 fuel assembly structural parts
  • 71 kreisförmiger Lagerraum71 circular storage room
  • 73 Endlagerbehälter73 repository
  • 75 Einsatzkorb75 insert basket
  • 77 quadratischer Mittelschacht77 square central shaft
  • 78 Trennwand78 partition
  • 79 Trennwand79 partition
  • 81 Behälterinnenwand81 inner container wall
  • 83 Rückwand83 rear wall
  • 85 Seitenflächen85 side panels
  • 87 Trennwand87 partition
  • 89 Trennwand89 partition
  • 91 Rückwand91 rear wall
  • 93 Brennstabbüchse93 fuel rod can
  • 95 bogenförmige Rückwand95 arched rear wall
  • 97 radiale Seitenflächen97 radial side faces
  • 99 innere Abschlußfläche99 inner end surface
  • 101 Brennstäbe101 fuel rods
  • 103 Saugrohr103 intake manifold
  • 93' Brennstabbüchse93 'fuel rod can
  • 97' radiale Seitenfläche97 'radial side surface
  • 105 schräge Führungsstege105 sloping guide bars
  • 106 schräge Auflaufflächen106 sloping ramp surfaces
  • 75' Einsatzkorb75 'insert basket
  • 73' Lagerbehälter73 'storage container
  • 109 Führungsflächen109 guide surfaces

Claims (3)

1. A storage tank to accommodate isolated fuel rods of irradiated nuclear reactor fuel elements, having a storage area which is circular in section, in which an insert basket is fitted to receive the fuel rods loaded into containers, characterised in that the individual fuel rod containers (17, 93, 93') are arranged circularly in the insert basket (19, 75, 75'), in that the section of the containers is circularly segmented, in that the containers (17, 93, 93') are loaded on their upper front sides with retaining springs (57), in that the fuel rod containers (17, 93, 93') are restricted in their radial extension by means such that in the centre of the insert basket (19, 75, 75'), an empty quadrilateral central core (21, 77) is formed.
2. A storage tank according to Claim 1, characterised in that, the insert basket (75) having a quadrilateral central core (77) has, from the central core (77) to the tank inner wall (81), dividing walls (78, 79, 87, 89) two of which together form a dividing segment (87, 89 or 78, 79), and in that between the two dividing segments (78, 79, and 87, 89) a receiving compartment is formed for a fuel rod container (93).
3. A storage tank according to Claim 1, characterised in that, the fuel rod containers (93') have on their radial side surfaces (97') in the upper area, slanting guide rods (105), which work in conjunction with correspondingly slanting abutting surfaces (106) in the adjacent dividing walls of the insert basket (75'), in that at the base of the outside of the central core (77), the fuel rod containers (93') are arranged outside pressing guide surfaces (109).
EP85110053A 1984-08-17 1985-08-09 Storage container for isolated fuel rods of irradiated nuclear reactor fuel elements Expired EP0171773B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3430243A DE3430243C2 (en) 1984-08-17 1984-08-17 Storage container for holding individual fuel rods from irradiated nuclear reactor fuel elements
DE3430243 1984-08-17

Publications (3)

Publication Number Publication Date
EP0171773A2 EP0171773A2 (en) 1986-02-19
EP0171773A3 EP0171773A3 (en) 1987-04-15
EP0171773B1 true EP0171773B1 (en) 1989-11-15

Family

ID=6243246

Family Applications (1)

Application Number Title Priority Date Filing Date
EP85110053A Expired EP0171773B1 (en) 1984-08-17 1985-08-09 Storage container for isolated fuel rods of irradiated nuclear reactor fuel elements

Country Status (4)

Country Link
US (1) US4680159A (en)
EP (1) EP0171773B1 (en)
CA (1) CA1234433A (en)
DE (2) DE3430243C2 (en)

Families Citing this family (22)

* 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
US4908515A (en) * 1985-12-27 1990-03-13 Nus Corporation Method of efficiently storing spent nuclear fuel rods in a cylindrical container
DE3620737C1 (en) * 1986-06-20 1987-10-01 Wiederaufarbeitung Von Kernbre Double container system for the transport and storage of radioactive substances
DE3802966A1 (en) * 1987-10-02 1989-04-20 Wiederaufarbeitung Von Kernbre METHOD AND DEVICE FOR TREATING A FUEL ELEMENT SKELETON, FREE OF FUEL STICKS, OF AN IRRADIATED NUCLEAR REACTOR FUEL ELEMENT
US4926046A (en) * 1988-12-12 1990-05-15 Westinghouse Electric Corp. Volumetrically efficient container apparatus
DE3933530C2 (en) * 1989-10-07 1995-05-11 Gorleben Brennelementlager Bearing bush for receiving individual fuel rods from nuclear reactor fuel elements
US5180540A (en) * 1991-03-25 1993-01-19 B&W Fuel Company Fuel rod consolidation structure
FR2709116B1 (en) * 1993-08-20 1995-10-27 Cogema Storage device for cylindrical objects, for fast loading and unloading.
JP3516978B2 (en) * 1994-04-15 2004-04-05 株式会社東芝 Fuel assembly transport container
US5615240A (en) * 1994-10-27 1997-03-25 General Electric Company Nuclear fuel bundle packaging apparatus
US5651038A (en) * 1996-02-06 1997-07-22 Sierra Nuclear Corporation Sealed basket for pressurized water reactor fuel assemblies
US20010011711A1 (en) * 1996-05-03 2001-08-09 Graham Nicholson Container for nuclear fuel transportation
GB9609304D0 (en) * 1996-05-03 1996-07-10 British Nuclear Fuels Plc Improvements in and relating to fuel transportation
FR2758646B1 (en) * 1997-01-21 2000-07-13 Toshiba Kk CONTAINER AND METHOD FOR TRANSPORTING NUCLEAR FUEL ASSEMBLIES
FR2760562B1 (en) * 1997-03-05 1999-05-28 Toshiba Kk APPARATUS AND METHOD FOR PROTECTING AND TRANSPORTING NUCLEAR FUEL ASSEMBLIES
DE59902780D1 (en) * 1999-06-19 2002-10-24 Gnb Gmbh Transport and / or storage containers for radioactive heat-generating elements
EP1122745A1 (en) * 1999-12-15 2001-08-08 GNB Gesellschaft für Nuklear-Behälter mbH Container for shipping and/or storing radioactive heat releasing materials and method for producing the same
EP1306857B1 (en) * 2001-10-23 2006-05-24 GNS Gesellschaft für Nuklear-Service mbH Grasp trunnion for a container adapted for receiving radioactive substances
EP2788988B1 (en) 2011-12-08 2017-03-29 Atomic Energy of Canada Limited/ Énergie Atomique du Canada Limitée Apparatus for holding radioactive objects
US9831006B2 (en) 2013-02-13 2017-11-28 Bwxt Mpower, Inc. Shipping container for unirradiated nuclear fuel assemblies
JP6759037B2 (en) * 2016-09-30 2020-09-23 三菱重工業株式会社 Storage method and storage container for used fuel assemblies
TWI795484B (en) 2017-12-20 2023-03-11 美商Ｔｎ美國有限責任公司 Modular basket assembly for fuel assemblies

Family Cites Families (25)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2984399A (en) * 1957-07-30 1961-05-16 Vanant Company Inc Packaging strip having accordion pleated cushions
US3020037A (en) * 1958-10-15 1962-02-06 Bache John Kenneth Spring cushioning devices
GB924013A (en) * 1960-05-24 1963-04-18 Atomic Energy Authority Uk Improvements in or relating to shielded containers for nuclear fuel elements
FR1290757A (en) * 1960-06-08 1962-04-13 Atomic Energy Commission Transport container for radioactive material
US3111586A (en) * 1961-08-25 1963-11-19 Baldwin Lima Hamilton Corp Air-cooled shipping container for nuclear fuel elements
FR2113805B1 (en) * 1970-11-17 1976-03-19 Transnucleaire
US4002238A (en) * 1975-01-17 1977-01-11 Minnesota Mining And Manufacturing Company Magnetic tape cartridge with removable spool
US3967748A (en) * 1975-06-03 1976-07-06 Thermo Seal Drinking receptacle valve means
GB1554605A (en) * 1976-08-25 1979-10-24 Atomic Energy Authority Uk Assembly for the transport of fuel elements
FR2424610A1 (en) * 1978-04-28 1979-11-23 Lemer & Cie Removable partitioning for radioactive products container - partic. for making uniform the temp. of irradiated fuel rods during storage and transport
US4474727A (en) * 1978-05-15 1984-10-02 Westinghouse Electric Corp. Arrangement for storing spent nuclear fuel rods at a reactor site
DE2828138A1 (en) * 1978-06-27 1980-01-10 Amtrust Ag Transport container for irradiated fuel elements - has removable basket to support elements in container or cooling pool
GB2055671B (en) * 1979-07-18 1982-11-17 British Nuclear Fuels Ltd Transport and storage of irradiated nuclear fuel elements
FR2462004A1 (en) * 1979-07-18 1981-02-06 British Nuclear Fuels Ltd Nuclear fuel transport insert - with five square cells in pentagonal pattern and neutron absorbent in walls
ATE3678T1 (en) * 1979-08-20 1983-06-15 Elektrowatt Ingenieurunternehmung Ag TRANSPORT CONTAINER FOR RADIOACTIVE MATERIAL.
DE3012310A1 (en) * 1980-03-29 1981-10-08 Transnuklear Gmbh, 6450 Hanau INSERT BASKET FOR RADIOACTIVE MATERIAL IN TRANSPORT AND / OR STORAGE CONTAINERS
DD150811A1 (en) * 1980-04-22 1981-09-16 Frank Drechsler CLOSURE DEVICE FOR A COVER OF AN SCREEN TANK
DE3038592C2 (en) * 1980-10-13 1985-03-28 Kraftwerk Union AG, 4330 Mülheim Storage with shielded containers
US4446063A (en) * 1980-10-29 1984-05-01 British Nuclear Fuels Limited Disposal of radioactive waste
DE3148528A1 (en) * 1980-12-22 1982-07-15 Steag Kernenergie Gmbh, 4300 Essen DEVICE FOR STORING WHEEL COACTIVE MATERIAL
US4399366A (en) * 1981-04-24 1983-08-16 Bucholz James A Separator assembly for use in spent nuclear fuel shipping cask
US4457888A (en) * 1982-02-22 1984-07-03 Combustion Engineering, Inc. Nuclear poison box base construction
DE3222822A1 (en) * 1982-06-18 1983-12-29 GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen Arrangement for transporting and storing fuel rods of spent fuel elements
JPS59182392A (en) * 1983-03-31 1984-10-17 三井造船株式会社 Method of storing radioactive material to cask for radioactive material
US4535250A (en) * 1984-05-30 1985-08-13 The United States Of America As Represented By The United States Department Of Energy Container for radioactive materials

Also Published As

Publication number Publication date
EP0171773A2 (en) 1986-02-19
DE3430243C2 (en) 1986-11-27
EP0171773A3 (en) 1987-04-15
DE3430243A1 (en) 1986-02-27
US4680159A (en) 1987-07-14
CA1234433A (en) 1988-03-22
DE3574306D1 (en) 1989-12-21

Similar Documents

Publication Publication Date Title
EP0171773B1 (en) Storage container for isolated fuel rods of irradiated nuclear reactor fuel elements
DE3017767C2 (en) Protective container for the transport, storage and radiation shielding of fuel element containers loaded with spent reactor fuel elements
DE69837440T2 (en) APPARATUS, SUITABLE FOR THE TRANSPORT AND STORAGE OF NUCLEAR BARS AND METHOD OF USE OF THE APPARATUS
DE3212707A1 (en) TRANSPORT AND STORAGE CONTAINER FOR FUEL FUEL
DE3620737C1 (en) Double container system for the transport and storage of radioactive substances
DE2821780A1 (en) Transport coffin for radioactive cpd., esp. irradiated fuel elements - has ventilation openings at opposite ends and internal sealed capsules
DE1083445B (en) Fuel element for nuclear reactors
DE60015277T2 (en) CONTAINER FOR THE TRANSPORT OF Uranium Oxide
DE2822397A1 (en) STORAGE MODULE FOR NUCLEAR FUEL UNITS
EP0741904B1 (en) Fuel-element storage and transport rack
DE4138030A1 (en) CONTROL STICK FOR CORE REACTORS
DE3125211C2 (en) Storage container and process for its manufacture
WO1997035321A1 (en) Method of removing a component from the pressure vessel of a nuclear reactor
DE2828138A1 (en) Transport container for irradiated fuel elements - has removable basket to support elements in container or cooling pool
DE19748222C1 (en) Preparation of irradiated fuel rods for decay storage in cooling pond
EP0148404B1 (en) Liquid-cooled nuclear reactor, in particular a boiling water reactor
EP0043096B1 (en) Device for the storage of radioactive materials
DE60318625T2 (en) CONTAINERS FOR STORING / TRANSPORTING UNBREADED RADIOACTIVE MATERIALS, SUCH AS, NUCLEAR FUEL ASSEMBLIES
EP0057430A1 (en) Container for transporting and storing radioactive wastes
DE3244727A1 (en) Method and flask system for transferring or transporting fuel elements from a nuclear power station to a storage site
DE3150622A1 (en) Container unit for spent nuclear reactor fuel elements
DE3131125C2 (en) Shielding transport and / or shielding storage containers for irradiated nuclear reactor fuel elements
DE1921528C3 (en) Process for binding the excess reactivity of nuclear reactors
DE2108855A1 (en) Canister for atomic wastes
DE2315460A1 (en) FUEL CHANGE IN NUCLEAR REACTORS

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 DE FR GB LI SE

17P Request for examination filed

Effective date: 19860826

PUAL Search report despatched

Free format text: ORIGINAL CODE: 0009013

AK Designated contracting states

Kind code of ref document: A3

Designated state(s): BE CH DE FR GB LI SE

17Q First examination report despatched

Effective date: 19881103

GRAA (expected) grant

Free format text: ORIGINAL CODE: 0009210

AK Designated contracting states

Kind code of ref document: B1

Designated state(s): BE CH DE FR GB LI SE

GBT Gb: translation of ep patent filed (gb section 77(6)(a)/1977)
REF Corresponds to:

Ref document number: 3574306

Country of ref document: DE

Date of ref document: 19891221

ET Fr: translation filed
PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: DE

Payment date: 19900717

Year of fee payment: 6

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: SE

Payment date: 19900724

Year of fee payment: 6

Ref country code: FR

Payment date: 19900724

Year of fee payment: 6

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: GB

Payment date: 19900808

Year of fee payment: 6

Ref country code: BE

Payment date: 19900808

Year of fee payment: 6

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
PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: CH

Payment date: 19901123

Year of fee payment: 6

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: GB

Effective date: 19910809

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: SE

Effective date: 19910810

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: LI

Effective date: 19910831

Ref country code: CH

Effective date: 19910831

Ref country code: BE

Effective date: 19910831

BERE Be: lapsed

Owner name: DEUTSCHE G.- FUR WIEDERAUFARBEITUNG VON KERNBRENN

Effective date: 19910831

GBPC Gb: european patent ceased through non-payment of renewal fee
PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: FR

Effective date: 19920430

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: DE

Effective date: 19920501

REG Reference to a national code

Ref country code: FR

Ref legal event code: ST

EUG Se: european patent has lapsed

Ref document number: 85110053.7

Effective date: 19920306