EP0057429B1 - 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
EP0057429B1
EP0057429B1 EP82100591A EP82100591A EP0057429B1 EP 0057429 B1 EP0057429 B1 EP 0057429B1 EP 82100591 A EP82100591 A EP 82100591A EP 82100591 A EP82100591 A EP 82100591A EP 0057429 B1 EP0057429 B1 EP 0057429B1
Authority
EP
European Patent Office
Prior art keywords
container
layers
storage
transporting
layer
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
EP82100591A
Other languages
German (de)
English (en)
Other versions
EP0057429A2 (fr
EP0057429A3 (en
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

    • 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 multilayered transport and storage container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, the container consisting of three or more layers of different metals or metal alloys, which from the outside inward in the electrochemical voltage series become more and more noble (positive).
  • Irradiated, spent fuel elements are processed either immediately after temporary storage in the water basin 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 cleavage products are by known methods, usually using large amounts of valuable materials, such as. B. lead and copper, conditioned and in suitable geological formations practically 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. In addition, 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.
  • Steel containers for receiving spent fuel elements are known from DE-A-2804828, on the inner and / or outer surface of which aluminum layers of 0.5 to 2 mm thickness are located. These containers are also not sufficiently corrosion-resistant for long-term storage.
  • the container has at least three layers, of which the outer layer is made of cast iron, the next inner layer of nickel or a nickel alloy and the inner layer of copper or a copper alloy. This ensures that, even if there is a partial corrosive breakthrough through the outer layer, the subsequent 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, as well as the service life of the second jacket etc. can be calculated. With this arrangement, it is possible to manufacture the outer jacket from relatively inexpensive material, such as cast iron, to make the container for its suitability as a transport container to give the necessary rigidity for the 9 m drop test.
  • the repository container consists of the outer jacket (1) with a welded 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). An excessively large potential spacing is not desirable so as not to accelerate too much in the event of local element formation as the outer sheath goes into solution.
  • the second inner container (3) must again be nobler in material than the first inner jacket (2). Here nickel-copper alloys come into consideration.
  • 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.
  • 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. Above all, bronzes, especially tin-rich ones, have proven themselves as corrosion-resistant materials.

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)
  • Details Of Rigid Or Semi-Rigid Containers (AREA)
  • Electroplating Methods And Accessories (AREA)

Claims (2)

1. Récipient de transport et de stockage à couches multiples pour le stockage de longue durée de déchets radio-actifs, en particulier d'éléments combustibles déjà brûlés dans des formations géologiques appropriées, dans lequel les couches (1, 2, 3) sont formées de métaux ou d'alliages différents qui sont de plus en plus nobles (positifs) de l'extérieur vers l'intérieur dans l'échelle des potentiels électrochimiques, caractérisé en ce que le récipient possède au moins trois couches parmi lesquelles la couche externe (1) est formée de fonte, la couche immédiatement interne (2) de Nickel ou d'un alliage de Nickel et la couche interne (3) de Cuivre ou d'un alliage de Cuivre.
2. Récipient de transport et de stockage selon la revendication 1, caractérisé en ce que la différence de potentiel électrochimique des couches métalliques (1, 2, 3) voisines se situe dans la zone de 50 à 500 mV.
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 EP0057429A2 (fr) 1982-08-11
EP0057429A3 EP0057429A3 (en) 1985-12-11
EP0057429B1 true 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)

Families Citing this family (13)

* 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
DE3610862A1 (de) * 1986-04-01 1987-10-08 Kernforschungsz Karlsruhe Laengszylindrischer behaelter fuer die endlagerung von einer oder mehreren mit hochradioaktiven abfaellen gefuellten kokillen
US4891165A (en) * 1988-07-28 1990-01-02 Best Industries, Inc. Device and method for encapsulating radioactive materials
WO1990001208A1 (fr) * 1988-07-28 1990-02-08 Best Industries, Inc. Procede et dispositif d'encapsulation de materiaux radioactifs
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
SE531261C2 (sv) * 2007-05-25 2009-02-03 Olle Grinder Kapsel avsedd för slutförvaring av utbränt kärnbränsle
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

Family Cites Families (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3610290A (en) * 1968-10-22 1971-10-05 Texas Instruments Inc Metal laminates and tubing embodying such laminates
US4208453A (en) * 1969-06-30 1980-06-17 Alloy Surfaces Company, Inc. Modified diffusion coating of the interior of a steam boiler tube
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
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
JPS5428738A (en) * 1977-08-08 1979-03-03 Usui Kokusai Sangyo Kk Double plated band steel for use in making corrosion resistant overlapped steel pipes
DE2804828A1 (de) * 1978-02-04 1979-08-09 Nukem Gmbh Stahlbehaelter zur aufnahme abgebrannter brennelemente
US4192765A (en) * 1978-02-15 1980-03-11 John N. Bird Container for radioactive nuclear waste materials
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

Also Published As

Publication number Publication date
EP0057429A2 (fr) 1982-08-11
US4562001A (en) 1985-12-31
EP0057429A3 (en) 1985-12-11
JPS57178189A (en) 1982-11-02
CA1166027A (fr) 1984-04-24
DE3103526C2 (de) 1985-11-14
DE3103526A1 (de) 1982-08-12
DE3279552D1 (en) 1989-04-20

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