EP0057429A2 - Conteneur multi-couches pour le transport et le stockage de déchets radioactifs - Google Patents

Conteneur multi-couches pour le transport et le stockage de déchets radioactifs Download PDF

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Publication number
EP0057429A2
EP0057429A2 EP82100591A EP82100591A EP0057429A2 EP 0057429 A2 EP0057429 A2 EP 0057429A2 EP 82100591 A EP82100591 A EP 82100591A EP 82100591 A EP82100591 A EP 82100591A EP 0057429 A2 EP0057429 A2 EP 0057429A2
Authority
EP
European Patent Office
Prior art keywords
container
transport
layer
storage
corrosion
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.)
Granted
Application number
EP82100591A
Other languages
German (de)
English (en)
Other versions
EP0057429A3 (en
EP0057429B1 (fr
Inventor
Horst Dr. Dipl.Chem. Vietzke
Hans Dr. Dipl.Chem. Huschka
Elmar Dr. Dipl.Ing. Schlich
Günther Dr. Luthardt
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 EP0057429A2 publication Critical patent/EP0057429A2/fr
Publication of EP0057429A3 publication Critical patent/EP0057429A3/de
Application granted granted Critical
Publication of EP0057429B1 publication Critical patent/EP0057429B1/fr
Expired legal-status Critical Current

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/34Disposal of solid waste
    • G21F9/36Disposal of solid waste by packaging; by baling

Definitions

  • the invention relates to a multilayered transport and storage container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations.
  • spent fuel elements are processed after temporary storage in the water basin either immediately or after a limited further interim storage.
  • the nuclear fuel and nuclear fuel are separated from the fission products and the back B rennstoffnik- running supplied.
  • the fission products are conditioned by known methods, usually using large amounts of valuable materials, such as lead and copper, and in practical geological formations they are virtually no longer removable.
  • Containers made of alloyed and unalloyed steel, copper and corundum are proposed as packaging for radioactive materials and irradiated fuel elements.
  • 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 at the pressures and temperatures that occur, and corrosion against brine, or they must be made very thick-walled.
  • they are usually not suitable as a transport container at the same time, so that the waste has to be reloaded from the transport container into the final storage container at considerable expense.
  • the container consists of two or more layers of different metals or metal alloys, which become more and more noble (positive) from outside to inside in the electrochemical voltage series. This ensures that even if there is a partial corrosive breakthrough through the outer layer, the next inner layer can only be attacked when the outer layer has completely dissolved. This means that the resistance time value can be calculated and the service life against corrosion is retained even in the event of unforeseeable malfunctions.
  • the time for the dissolution of the second jacket can also be calculated. Based on the removal rates per time and area, the service life of the outer jacket in a certain corrosive medium can be calculated, as can the service life of the second jacket and so on.
  • the outer jacket from relatively inexpensive material such as iron; To produce graphite cast iron to give the container the necessary rigidity for the 9 m drop test for its suitability as a transport container.
  • the repository container consists of the outer jacket (1) with a welded-on or joined lid (5). Alloyed cast iron, preferably cast iron, is used as the material.
  • the first inner jacket (2) located in this outer container consists of nickel or a nickel alloy, which is more noble in the electrochemical series than the outer jacket (1). Too large a potential gap is not desirable so as not to accelerate the dissolution of the outer jacket too much in the event of local element formation.
  • the second inner container (3) must again be nobler in material than the first inner jacket (2). Nickel-copper alloys are advantageously used here.
  • the interior (4) is filled with spent fuel or highly active waste. All three container layers are self-contained, which can be done, for example, by welding.
  • the electrochemical potentials of the adjacent layers are not too far apart. They are preferably not more than 50 to 500 m V apart.
  • the container with further linings inside or on the surface of the container, or to insert an inner container made of a suitable material. For example, it is possible to insert a monolithic graphite block as an inner container.
  • the layer thicknesses of the outer layers are in the range of 5 to 20 cm, those of the other noble layers in the range of 5 to 50 mm.
  • Bronzes, in particular tin-rich ones, have proven to be corrosion-resistant materials.
  • alloy components and their effects on the potentials, but also on the corrosion behavior, such as e.g. Crevice corrosion, to be taken into account When determining the order of the metal layers according to the invention, alloy components and their effects on the potentials, but also on the corrosion behavior, such as e.g. Crevice corrosion, to be taken into account.

Landscapes

  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Laminated Bodies (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Electroplating Methods And Accessories (AREA)
  • Details Of Rigid Or Semi-Rigid Containers (AREA)
EP82100591A 1981-02-03 1982-01-28 Conteneur multi-couches pour le transport et le stockage de déchets radioactifs Expired EP0057429B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3103526 1981-02-03
DE3103526A DE3103526C2 (de) 1981-02-03 1981-02-03 Mehrschichtiger Transport- und Lagerbehälter für radioaktive Abfälle

Publications (3)

Publication Number Publication Date
EP0057429A2 true EP0057429A2 (fr) 1982-08-11
EP0057429A3 EP0057429A3 (en) 1985-12-11
EP0057429B1 EP0057429B1 (fr) 1989-03-15

Family

ID=6123895

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82100591A Expired EP0057429B1 (fr) 1981-02-03 1982-01-28 Conteneur multi-couches pour le transport et le stockage de déchets radioactifs

Country Status (5)

Country Link
US (1) US4562001A (fr)
EP (1) EP0057429B1 (fr)
JP (1) JPS57178189A (fr)
CA (1) CA1166027A (fr)
DE (2) DE3103526C2 (fr)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0244599A1 (fr) * 1986-04-01 1987-11-11 Kernforschungszentrum Karlsruhe Gmbh Récipient cylindrique pour le stockage final d'une ou de plusieurs coquilles remplies de déchets radioactifs
EP2160736A4 (fr) * 2007-05-25 2016-03-30 Swedish Metallurg And Mining Ab Réceptacle final de combustible nucléaire épuisé

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4935943A (en) * 1984-08-30 1990-06-19 The United States Of America As Represented By The United States Department Of Energy Corrosion resistant storage container for radioactive material
DE3445124C1 (de) * 1984-12-11 1986-01-23 Nukem Gmbh, 6450 Hanau Auskleidung fuer Bohrloecher in Salzstoecken
WO1990001208A1 (fr) * 1988-07-28 1990-02-08 Best Industries, Inc. Procede et dispositif d'encapsulation de materiaux radioactifs
US4891165A (en) * 1988-07-28 1990-01-02 Best Industries, Inc. Device and method for encapsulating radioactive materials
US4861520A (en) * 1988-10-28 1989-08-29 Eric van't Hooft Capsule for radioactive source
US5899882A (en) * 1994-10-27 1999-05-04 Novoste Corporation Catheter apparatus for radiation treatment of a desired area in the vascular system of a patient
US5683345A (en) * 1994-10-27 1997-11-04 Novoste Corporation Method and apparatus for treating a desired area in the vascular system of a patient
US5611429A (en) * 1995-04-05 1997-03-18 Phillips; Paul B. Medical syringe disposal
US6544606B1 (en) * 2000-01-11 2003-04-08 Nac International Systems and methods for storing fissile materials
NO20044434D0 (no) * 2004-10-19 2004-10-19 Nuclear Prot Products As Lang-tids lagringscontainer og fremgangsmate for fremstilling av denne
CN111739672B (zh) * 2020-05-13 2023-12-22 中国核电工程有限公司 一种降低氚渗透速率的结构

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2021229A1 (fr) * 1968-10-22 1970-07-17 Texas Instruments Inc
US4031921A (en) * 1975-09-09 1977-06-28 The United States Of America As Represented By The United States Energy Research And Development Administration Hydrogen-isotope permeation barrier
FR2399916A1 (fr) * 1977-08-08 1979-03-09 Usui Kokusai Sangyo Kk Bande d'acier a placage stratifie, notamment pour la fabrication de tubes d'acier anticorrosion a double paroi
DE2804828A1 (de) * 1978-02-04 1979-08-09 Nukem Gmbh Stahlbehaelter zur aufnahme abgebrannter brennelemente
EP0004133A1 (fr) * 1978-02-15 1979-09-19 Bird, John M.Dr., Conteneur pour déchets radioactifs et méthode pour contenir de déchets radioactifs pour une periode de temps etendu

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4208453A (en) * 1969-06-30 1980-06-17 Alloy Surfaces Company, Inc. Modified diffusion coating of the interior of a steam boiler tube
US4290847A (en) * 1975-11-10 1981-09-22 Minnesota Mining And Manufacturing Company Multishell microcapsules
FR2375695A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour le traitement de dechets radioactifs
JPS6051070B2 (ja) * 1977-07-21 1985-11-12 株式会社東芝 核燃料要素およびその製造方法
US4337167A (en) * 1978-02-15 1982-06-29 Bird John M Container for radioactive nuclear waste materials
JPS5589792A (en) * 1978-12-28 1980-07-07 Tokyo Shibaura Electric Co Nuclear fuel rod
US4362696A (en) * 1979-05-21 1982-12-07 The United States Of America As Represented By The United States Department Of Energy Corrosion-resistant fuel cladding allow for liquid metal fast breeder reactors
US4292528A (en) * 1979-06-21 1981-09-29 The Carborundum Company Cask for radioactive material and method for preventing release of neutrons from radioactive material
US4338215A (en) * 1979-09-24 1982-07-06 Kennecott Corporation Conversion of radioactive wastes to stable form for disposal
JPS5662955A (en) * 1979-10-26 1981-05-29 Hitachi Ltd Manufacture of nuclear fuel cladding pipe

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2021229A1 (fr) * 1968-10-22 1970-07-17 Texas Instruments Inc
US4031921A (en) * 1975-09-09 1977-06-28 The United States Of America As Represented By The United States Energy Research And Development Administration Hydrogen-isotope permeation barrier
FR2399916A1 (fr) * 1977-08-08 1979-03-09 Usui Kokusai Sangyo Kk Bande d'acier a placage stratifie, notamment pour la fabrication de tubes d'acier anticorrosion a double paroi
DE2804828A1 (de) * 1978-02-04 1979-08-09 Nukem Gmbh Stahlbehaelter zur aufnahme abgebrannter brennelemente
EP0004133A1 (fr) * 1978-02-15 1979-09-19 Bird, John M.Dr., Conteneur pour déchets radioactifs et méthode pour contenir de déchets radioactifs pour une periode de temps etendu

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0244599A1 (fr) * 1986-04-01 1987-11-11 Kernforschungszentrum Karlsruhe Gmbh Récipient cylindrique pour le stockage final d'une ou de plusieurs coquilles remplies de déchets radioactifs
EP2160736A4 (fr) * 2007-05-25 2016-03-30 Swedish Metallurg And Mining Ab Réceptacle final de combustible nucléaire épuisé

Also Published As

Publication number Publication date
DE3279552D1 (en) 1989-04-20
CA1166027A (fr) 1984-04-24
US4562001A (en) 1985-12-31
DE3103526A1 (de) 1982-08-12
DE3103526C2 (de) 1985-11-14
EP0057429A3 (en) 1985-12-11
JPS57178189A (en) 1982-11-02
EP0057429B1 (fr) 1989-03-15

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