EP0059419A1 - Dispositif de stockage de matériaux radioactifs comportant plusieurs récipients en matière anticorrosive maintenue ensemble par une couche et méthode de fabrication du récipient - Google Patents

Dispositif de stockage de matériaux radioactifs comportant plusieurs récipients en matière anticorrosive maintenue ensemble par une couche et méthode de fabrication du récipient Download PDF

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Publication number
EP0059419A1
EP0059419A1 EP82101368A EP82101368A EP0059419A1 EP 0059419 A1 EP0059419 A1 EP 0059419A1 EP 82101368 A EP82101368 A EP 82101368A EP 82101368 A EP82101368 A EP 82101368A EP 0059419 A1 EP0059419 A1 EP 0059419A1
Authority
EP
European Patent Office
Prior art keywords
container
containers
matrix
receiving
package
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.)
Withdrawn
Application number
EP82101368A
Other languages
German (de)
English (en)
Inventor
Heinz Ing. Grad. Bienek
Wolfgang Dipl.-Ing. Von Heesen
Wilhelm Dr.-Ing. Wick
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.)
Steag Kernenergie GmbH
Original Assignee
Steag Kernenergie GmbH
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 Steag Kernenergie GmbH filed Critical Steag Kernenergie GmbH
Publication of EP0059419A1 publication Critical patent/EP0059419A1/fr
Withdrawn legal-status Critical Current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

Definitions

  • the invention relates to a device for storing radioactive substances with a plurality of the same inner containers (modules) with a corrosion protection jacket for receiving the radioactive substances, in particular a plurality of irradiated fuel rods, which inner containers are put together in a substantially sealed package to form a container package, and with one Keep the container in the package together and surround the package.
  • the jacket is composed of individual building blocks parallel to the direction of extension of the inner container, which are arranged such that they can move with respect to one another or are non-positive and / or positive sig are united with each other, for example by gluing or by tongue and groove engagement.
  • the cross section of the individual components is very small compared to the cross section of the container.
  • the jacket is a one-piece matrix container with a receiving bore for each inner container.
  • the casing When constructing the casing as a one-piece matrix container, the complicated construction of the casing from individual components is eliminated. Through a suitable choice of the material for the one-piece matrix container, it is possible that undesired thermal stresses do not come into play and, on the other hand, there is sufficient heat dissipation from the individual inner containers to the outside. Because of the one-piece nature of the matrix container, a dangerous exposure of the individual inner container to rock movements is excluded, particularly when the arrangement is used as a repository device.
  • the one-piece jacket not only increases the mechanical strength and manageability of the inner container package, but also improves the corrosion resistance for final storage.
  • These materials are particularly suitable for the final storage of radioactive substances in salt domes; with other repository conditions, e.g. in granite cavities, the materials can be different and adapted accordingly.
  • the strength and heat dissipation can be controlled by suitable material selection, but also the neutron and gamma shielding.
  • the matrix container is preferably a prefabricated component, the receiving bores of which are each closed by a sealing plug.
  • the prefabricated container can be a monolithic block or can be constructed from a plurality of bored disks which are connected to form an integral matrix body, e.g. glued.
  • the preferred material for the matrix containers is: carbon, also in graphite form, oxide ceramics, glass, cement, bitumen, concrete.
  • a gas-tight seal of the sealing plugs with respect to the matrix container can be achieved, for example, according to DE patent application P 31 07 611: "Process for the gas-tight sealing of ceramic containers for the storage of radioactive substances”.
  • the gap between the inner wall of a mounting hole and the outer wall of each in the receptacle bore inserted inner container is expediently closed by a closing means.
  • the gaps are cast, e.g. with glass, metal.
  • the gaps can be filled with a particulate material, preferably by blowing and / or shaking.
  • the materials come e.g. Carbon, also in graphite form, carbon compounds, oxide ceramics in question and the particle size can go down to fine powder. The particle size must ensure that the gaps are filled safely for heat dissipation.
  • a coating preferably a glass coating
  • the coatings can be applied to both the module and the bores of the matrix container before inserting the inner container to be filled with radioactive substance, ie can be carried out outside of hot cells.
  • the concentric gap should be blown with a sealing powder, in particular carbon in graphite form.
  • the gap between the end plug and the matrix container cannot be closed by potting or melting previously applied coatings, as described in the above-mentioned patent application P 31 07 611, in particular because the matrix container and / or the end plug, which is also preferably made of the the matrix container is made of preferred materials, is not wettable by the melts used, it is recommended to grind the end plugs of the matrix container to fit dimensions and possibly to be provided with additional seals and mechanical safeguards.
  • the matrix container is a container which directly and on all sides encloses the outer walls of the inner container and is made from a casting, melting or sintered mass.
  • the short name "cast container" is chosen.
  • the inner containers are used by suitable spacers as a package in the center of a mold having a base. They are positioned by means of suitable spacers with respect to the mold and with one another in a contactless or touching manner. The remaining cavities are poured out and a sufficient layer of the potting material is introduced above the inner container. It is possible for the casting mold to remain as a metallic container skin after the casting compound has solidified, which is then welded gas-tight to a cover.
  • Low-melting glass, glass ceramics, cement or bitumen are particularly suitable as casting compounds.
  • inhomogeneous casting compounds such as concrete, can also be used.
  • the invention is also directed to methods for constructing the device according to claim 1.
  • one method is characterized in that the inner containers are introduced into the receiving bores of a prefabricated matrix container and the openings of the receiving bores are then closed by end plugs.
  • the gaps between the inner walls of the receiving bores and the outer walls of the inner container are also preferably closed filled the openings.
  • the inner containers are first positioned in a casting mold against one another and opposite the casting mold and then cast on all sides with a casting compound.
  • FIG. 1 shows a side view of a device according to the invention, shown as a partial section
  • FIG. 1 a perspective view, shown as a partial section, of a container not closed by a lid, the matrix container also being prefabricated, and
  • FIG. 1 An inner container 1 is also shown in partial section in FIG. 1, although the inner structure is not part of the present invention with the exception of the fact that a plurality of fuel rods 2 are arranged inside the inner container 1 and that the inner container has a corrosion protection jacket 3.
  • FIG. 1 does not show the fuel rods themselves, but rather containment tubes, into which the individual fuel rods are introduced according to patent application P 3 0 41 22o.
  • the fuel rods 2 are not stored directly in the corrosion protection jacket 3, but are previously introduced into a metallic container 4 which is held in the corrosion protection jacket 3 by means of a frictional engagement arrangement 5 according to patent application P 3 0 48 38o.
  • the corrosion protection jacket 3 which is closed at the upper end by a cover 7, which may be protected by a sealing compound 6, which can either be provided with a one-piece base at the lower end or is closed with a further cover.
  • the closed corrosion protection jacket 3 is intended to oppose the packaged radioactive substances, which are present in large quantities, in particular several fuel rods Protect aggressive media and, in the event of the final storage of these materials in geological formations, are sufficient to absorb the mountain pressure. Furthermore, the materials used and the geometries used must ensure the dissipation of the decay heat of the packaged radioactive substances so that the temperature in the inner container 1 is kept so low that the radioactive substances and the packaging itself are not changed in their chemical and mechanical properties.
  • the inner containers 1 are introduced into prepared receiving bores 8 of a prefabricated one-piece matrix container 9.
  • the receiving bores do not necessarily have to be circular-cylindrical, but a circular-cylindrical cross section is preferred.
  • spacers 10 are provided between the outer wall of the inner container and the inner wall of the receiving bores, which keep the inner container at a uniform distance from the matrix container.
  • the receiving bores are closed at their lower end and have at their upper end At the end of a stepped insertion opening 11.
  • a sealing compound VM for which the material used for the matrix container is preferably used becomes.
  • the matrix container 9 can itself be provided with handling means.
  • the matrix container itself is, however, introduced into a metal container 13 consisting of a base 14, a jacket 15 and a cover 16. After all of the receiving bores 8 have been filled, the jacket is welded to the cover 16, which in turn carries manipulation devices 17. From Figures 1 and 3 it can be seen that before A sufficient layer thickness of potting compound preferably remains between the upper end of the inner container 1 and the associated end plug.
  • a casting mold consisting of a metallic base 18 and a metallic shell 19 connected to the base
  • the inner containers with spacers 20 are positioned one below the other and opposite the casting mold. Potting compound is then poured into the casting mold until the containers on all sides, i.e. also at the upper end, are surrounded with sufficient material thickness.
  • the mold becomes part of the device.
  • a cover with handling devices is welded onto the jacket 19 in a manner comparable to the embodiments according to FIGS. 1-3.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Details Of Rigid Or Semi-Rigid Containers (AREA)
EP82101368A 1981-02-27 1982-02-24 Dispositif de stockage de matériaux radioactifs comportant plusieurs récipients en matière anticorrosive maintenue ensemble par une couche et méthode de fabrication du récipient Withdrawn EP0059419A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3107505 1981-02-27
DE19813107505 DE3107505A1 (de) 1981-02-27 1981-02-27 Vorrichtung zum lagern radioaktiver substanzen mit einer mehrzahl einen korrosionsschutzmantel aufweisenden gleichen innenbehaeltern und einem die behaelter in einem paket zusammenhaltenden mantel

Publications (1)

Publication Number Publication Date
EP0059419A1 true EP0059419A1 (fr) 1982-09-08

Family

ID=6125963

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82101368A Withdrawn EP0059419A1 (fr) 1981-02-27 1982-02-24 Dispositif de stockage de matériaux radioactifs comportant plusieurs récipients en matière anticorrosive maintenue ensemble par une couche et méthode de fabrication du récipient

Country Status (2)

Country Link
EP (1) EP0059419A1 (fr)
DE (1) DE3107505A1 (fr)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0116412A1 (fr) * 1983-01-18 1984-08-22 Kabushiki Kaisha Kobe Seiko Sho Récipient pour matériaux radioactifs et méthode pour sa fabrication
DE4037805A1 (de) * 1990-11-28 1992-06-04 Siempelkamp Gmbh & Co Transport- und lagerbehaelter fuer bestrahlte kernreaktor-brennelemente

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3447278A1 (de) * 1984-12-22 1986-06-26 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Langzeitbestaendige korrosionsschutzumhuellung fuer dicht verschlossene gebinde mit hochradioaktivem inhalt
DE19757843C1 (de) * 1997-12-24 1999-08-12 Nuklear Service Gmbh Gns Lagerbehälter für die Zwischen- und/oder Endlagerung abgebrannter Brennelemente

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3117625A (en) * 1961-03-16 1964-01-14 Stanray Corp Filling material for heat exchangers
FR2358730A1 (fr) * 1976-07-15 1978-02-10 Steag Kernenergie Gmbh Dispositif de stockage final de dechets radio-actifs
FR2375696A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour enfermer du combustible nucleaire use ou des dechets de combustible nucleaire
FR2384327A1 (fr) * 1977-03-14 1978-10-13 Transnucleaire Transports Ind Emballage pour le transport des elements combustibles irradies

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3117625A (en) * 1961-03-16 1964-01-14 Stanray Corp Filling material for heat exchangers
FR2358730A1 (fr) * 1976-07-15 1978-02-10 Steag Kernenergie Gmbh Dispositif de stockage final de dechets radio-actifs
FR2375696A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour enfermer du combustible nucleaire use ou des dechets de combustible nucleaire
FR2384327A1 (fr) * 1977-03-14 1978-10-13 Transnucleaire Transports Ind Emballage pour le transport des elements combustibles irradies

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
ELECTRICAL WORLD, Band 102, Nr. 12, 15. Dezember 1974, Seiten 45-46, New York, USA "Special containers designed for nuclear fuel" *

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0116412A1 (fr) * 1983-01-18 1984-08-22 Kabushiki Kaisha Kobe Seiko Sho Récipient pour matériaux radioactifs et méthode pour sa fabrication
US4752437A (en) * 1983-01-18 1988-06-21 Kabushiki Kaisha Kobe Seiko Sho Packaging of radioactive materials
DE4037805A1 (de) * 1990-11-28 1992-06-04 Siempelkamp Gmbh & Co Transport- und lagerbehaelter fuer bestrahlte kernreaktor-brennelemente

Also Published As

Publication number Publication date
DE3107505A1 (de) 1982-09-16

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Effective date: 19830815

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Inventor name: BIENEK, HEINZ, ING. GRAD.

Inventor name: WICK, WILHELM, DR.-ING.

Inventor name: VON HEESEN, WOLFGANG, DIPL.-ING.