EP0057430A1 - Récipient de transport et de stockage pour déchets radioactifs - Google Patents

Récipient de transport et de stockage pour déchets radioactifs Download PDF

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Publication number
EP0057430A1
EP0057430A1 EP82100593A EP82100593A EP0057430A1 EP 0057430 A1 EP0057430 A1 EP 0057430A1 EP 82100593 A EP82100593 A EP 82100593A EP 82100593 A EP82100593 A EP 82100593A EP 0057430 A1 EP0057430 A1 EP 0057430A1
Authority
EP
European Patent Office
Prior art keywords
container
transport
storage
graphite block
pressed
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Withdrawn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
EP82100593A
Other languages
German (de)
English (en)
Inventor
Horst Dr. Dipl.Chem. Vietzke
Hans Dr. Dipl.Chem. Huschka
Milan Dr. Dipl.Ing. Hrovat
Thomas Dipl.Chem. Schmidt-Hansberg
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
Nukem GmbH
Original Assignee
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Nukem 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 Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH, Nukem GmbH filed Critical Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Publication of EP0057430A1 publication Critical patent/EP0057430A1/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Withdrawn legal-status Critical Current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
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • G21F9/36—Disposal of solid waste by packaging; by baling

Definitions

  • the invention relates to a transport and storage container for long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of an outer container and an inner container.
  • Irradiated, spent fuel elements are processed after temporary storage in water basins either immediately or after a limited further interim storage.
  • the nuclear fuels and broods are separated from the fission products and returned to the fuel cycle.
  • the fission products are conditioned using known processes, usually using large quantities of valuable materials such as lead and copper, and are virtually no longer removable in suitable geological formations.
  • it is being considered (reports from the Nuclear Research Center Düsseldorf KFK 2535 and 2650) not to reprocess the irradiated fuel elements in the foreseeable future, to initially dispense with the fuels present in them and, after an appropriate decay time in the storage facilities provided for this purpose, to re-use the fuel elements if necessary removably to be disposed of.
  • the storage times can be several generations up to several thousand years, whereby the risk potential of the radioactive inventory during this time, following the known physical laws, is reduced extremely according to its composition.
  • Containers made of alloyed and unalloyed steel, copper and corundum are used as packaging for radioactive materials and irradiated fuel elements beaten.
  • the steel containers are either not sufficiently corrosion-resistant or, like copper, are very expensive.
  • Corundum containers are generally suitable, but the experience required for their manufacture is lacking.
  • the fuel elements for packaging would have to be disassembled into small corundum containers for manufacturing reasons, which is associated with considerable effort.
  • Such containers only partially meet the conditions of long-term storage, such as tight containment under pressure and temperature, and corrosion against brine, or they must be made very thick-walled. In addition, they are usually not suitable as a transport container at the same time, so that the waste must be reloaded from the transport container into the final storage container at considerable expense.
  • Containers used for the transport and storage of radioactive waste usually consist of an outer container and an inner container. Both parts of the container are generally made of metal. Compliance with the long storage times requires expensive materials because they have to be installed as corrosion barriers.
  • the inner container consists of a monolithic graphite block in which the radioactive waste is embedded.
  • This monolithic graphite block can be easily manufactured by known processes and cannot be attacked by corrosion.
  • graphite powder with sulfur as a binder can be pressed up to approximately 120 ° C. into blocks in which the theoretical density is almost reached. If metal powders such as Ni, Mn, Fe, Zn, Pb and Sn are added to the mixture, which form insoluble sulfides with the sulfur at a somewhat higher temperature, the graphite block does not soften even at higher temperatures. Since no higher temperatures are required during production, spent fuel rods or fuel elements can be used embed in cans in such a graphite block. Such a monolithic graphite block, possibly still covered with a steel sleeve, then serves as an inner container for a transport container of a known type.
  • metal powders such as Ni, Mn, Fe, Zn, Pb and Sn
  • this transport container with the graphite block it contains is stored in deep geological layers, for example in rock salt, then the outer metal jacket, which is made of cheap cast iron, for example, can be destroyed by corrosion because the inner graphite block is corrosion-resistant and can absorb the full rock pressure .
  • the outer metal jacket which is made of cheap cast iron, for example, can be destroyed by corrosion because the inner graphite block is corrosion-resistant and can absorb the full rock pressure .
  • the figure schematically shows a transport and storage container according to the invention in an exemplary embodiment.
  • the container consists of an outer container (1), for example made of cast iron, and a monolithic graphite block (2) as an inner container in which the radioactive waste, which is preferably located in cans (3), is embedded.
  • the waste can advantageously be pressed into the graphite block as fuel elements open or in tins. However, it is also possible to introduce it into bores or other cavities in the graphite block.
  • the outer container (1) is closed with a lid (4). All materials known for this purpose can be used as the material for the outer container and lid.
  • the monolithic graphite block with a metallic coating in order to close any pores that may still be present or to improve the heat transfer to the outer container, e.g. galvanic or de-energized ..
  • a hexagonal graphite block with a key width of 360 mm and a length of 4 m is pre-pressed with 210 channels in the inactive area.
  • 210 spent fuel rods are then introduced into the channels of the block, the block is provided at the top and bottom with a graphite disc, which has also been pre-pressed, and is finished pressed in a hot press.
  • a mixture of 43.3% graphite powder, 36.7% nickel powder and 20 sulfur flowers is used as the press powder.
  • a 4-column press with 3 hydraulic drives is used to deform the block.
  • the stroke of the hexagonal lower punch extends almost over the entire (4 m) die length.
  • 210 polished steel rods are used to form the channels, which can be inserted through the die from below.
  • the pressing is done in sections.
  • hexagonal discs 180 mm thick are pre-pressed, which will later serve as the base and cover.
  • the pre-pressed parts are then transported to a hot cell and inserted into a hot press. First, a pre-pressed disc (as the base) is placed on the die, on which the 4 m long block is placed. Then spent fuel rods (210 pieces) are inserted into the channels.
  • the upper space up to the fuel rod is filled with press powder and the pre-pressed upper cover is put on.
  • the press block by heating and radiant heat reaches 120 0 C, starting with the final pressing at 50 MN / m 2.
  • the temperature is increased further while maintaining the pressure and, when using nickel powder, must reach 400 to 450 ° C. so that the sulfur is quantitatively set as NiS.
  • the resulting, high-density graphite block can already be ejected from the die.
  • This graphite block is used in a transport container made of cast iron for transport, to the intermediate or final storage facility. Final storage is also possible without the outer container by inserting the graphite block directly into the borehole of a salt mine.
  • Example 1 While in Example 1 the fuel assembly has to be disassembled into individual rods beforehand, direct embedding of entire fuel assemblies ( ⁇ 235 fuel rods) is also possible.
  • the end pieces are sawn off from a biblis fuel assembly to keep the overall length small.
  • a steel cylinder with an inner diameter of 230 mm and a length of 4.30 m is used to hold the fuel assembly hull.
  • the ends of the cylinder consist of spherical caps, which are welded tightly to the cylinder. This fuel assembly should withstand an external pressure of 300 bar.
  • this fuel assembly is inserted into a graphite cylinder prefabricated according to Example 1 with only one hollow channel, inserted into the hot press at the open ends with pre-pressed lids and pressed as in Example 1.

Landscapes

  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
EP82100593A 1981-02-03 1982-01-28 Récipient de transport et de stockage pour déchets radioactifs Withdrawn EP0057430A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3103557 1981-02-03
DE19813103557 DE3103557A1 (de) 1981-02-03 1981-02-03 "transport- und lagerbehaelter fuer radioaktive abfaelle"

Publications (1)

Publication Number Publication Date
EP0057430A1 true EP0057430A1 (fr) 1982-08-11

Family

ID=6123917

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82100593A Withdrawn EP0057430A1 (fr) 1981-02-03 1982-01-28 Récipient de transport et de stockage pour déchets radioactifs

Country Status (3)

Country Link
EP (1) EP0057430A1 (fr)
JP (1) JPS57178190A (fr)
DE (1) DE3103557A1 (fr)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2151068A (en) * 1983-12-09 1985-07-10 Kernforschungsanlage Juelich Process for storing fuel elements
US4560502A (en) * 1981-11-11 1985-12-24 Nukem Gmbh Molded body for embedding radioactive waste and process for its production
US4626382A (en) * 1983-07-06 1986-12-02 Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh Method of producing a glass block containing radioactive fission products and apparatus therefor
WO2003096355A1 (fr) * 2002-05-10 2003-11-20 Pebble Bed Modular Reactor (Proprietary) Limited Procede et appareil utilises pour l'elimination du combustible nucleaire epuise

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
ATE385607T1 (de) * 2002-12-24 2008-02-15 Nuklear Service Gmbh Gns Transport- und lagerbehälter für wärmeentwickelnde radioaktive stoffe, insbesondere abgebrannte kernreaktorbrennelemente oder haw-glaskokillen
DE102009044963B4 (de) * 2008-11-10 2011-06-22 ALD Vacuum Technologies GmbH, 63450 Blöcke aus Graphit-Matrix mit anorganischem Bindemittel geeignet zur Lagerung von radioaktiven Abfällen und Verfahren zur Herstellung derselben
US8502009B2 (en) 2008-11-26 2013-08-06 Ald Vacuum Technologies Gmbh Matrix material comprising graphite and an inorganic binder suited for final disposal of radioactive waste, a process for producing the same and its processing and use
DE102010003289B4 (de) * 2010-03-25 2017-08-24 Ald Vacuum Technologies Gmbh Gebinde zur Lagerung von radioaktiven Abfällen und Verfahren zu seiner Herstellung

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3828197A (en) * 1973-04-17 1974-08-06 Atomic Energy Commission Radioactive waste storage
US3993579A (en) * 1975-10-22 1976-11-23 The United States Of America As Represented By The United States Energy Research And Development Administration Method of encapsulating solid radioactive waste material for storage
GB2048554A (en) * 1979-04-28 1980-12-10 Nukem Gmbh Process for conditioning radioactive and/or toxic waste
DE2942092A1 (de) * 1979-10-18 1981-04-30 Steag Kernenergie Gmbh, 4300 Essen Vorrichtung fuer die aufbewahrung von radioaktiven abfallstoffen, insbesondere von bestrahlten kernreaktorbrennelementen

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3828197A (en) * 1973-04-17 1974-08-06 Atomic Energy Commission Radioactive waste storage
US3993579A (en) * 1975-10-22 1976-11-23 The United States Of America As Represented By The United States Energy Research And Development Administration Method of encapsulating solid radioactive waste material for storage
GB2048554A (en) * 1979-04-28 1980-12-10 Nukem Gmbh Process for conditioning radioactive and/or toxic waste
DE2942092A1 (de) * 1979-10-18 1981-04-30 Steag Kernenergie Gmbh, 4300 Essen Vorrichtung fuer die aufbewahrung von radioaktiven abfallstoffen, insbesondere von bestrahlten kernreaktorbrennelementen

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4560502A (en) * 1981-11-11 1985-12-24 Nukem Gmbh Molded body for embedding radioactive waste and process for its production
US4626382A (en) * 1983-07-06 1986-12-02 Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh Method of producing a glass block containing radioactive fission products and apparatus therefor
GB2151068A (en) * 1983-12-09 1985-07-10 Kernforschungsanlage Juelich Process for storing fuel elements
WO2003096355A1 (fr) * 2002-05-10 2003-11-20 Pebble Bed Modular Reactor (Proprietary) Limited Procede et appareil utilises pour l'elimination du combustible nucleaire epuise

Also Published As

Publication number Publication date
DE3103557A1 (de) 1982-12-09
JPS57178190A (en) 1982-11-02

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PUAI Public reference made under article 153(3) epc to a published international application that has entered the european phase

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AK Designated contracting states

Designated state(s): BE DE FR GB SE

17P Request for examination filed

Effective date: 19820925

STAA Information on the status of an ep patent application or granted ep patent

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18W Application withdrawn

Withdrawal date: 19840426

RIN1 Information on inventor provided before grant (corrected)

Inventor name: SCHMIDT-HANSBERG, THOMAS, DIPL.CHEM.

Inventor name: VIETZKE, HORST, DR. DIPL.CHEM.

Inventor name: HUSCHKA, HANS, DR. DIPL.CHEM.

Inventor name: HROVAT, MILAN, DR. DIPL.ING.