EP0072429B1 - Conteneur pour le stockage à long terme de déchets radioactifs - Google Patents

Conteneur pour le stockage à long terme de déchets radioactifs Download PDF

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Publication number
EP0072429B1
EP0072429B1 EP82106184A EP82106184A EP0072429B1 EP 0072429 B1 EP0072429 B1 EP 0072429B1 EP 82106184 A EP82106184 A EP 82106184A EP 82106184 A EP82106184 A EP 82106184A EP 0072429 B1 EP0072429 B1 EP 0072429B1
Authority
EP
European Patent Office
Prior art keywords
container
protective layer
long
term storage
radioactive waste
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
EP82106184A
Other languages
German (de)
English (en)
Other versions
EP0072429A1 (fr
Inventor
Jürgen Dr. Dipl.-Chem. Hofmann
Hans Dipl.-Chem. Pirk
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 EP0072429A1 publication Critical patent/EP0072429A1/fr
Application granted granted Critical
Publication of EP0072429B1 publication Critical patent/EP0072429B1/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
    • 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
    • G21F1/00—Shielding characterised by the composition of the materials
    • G21F1/02—Selection of uniform shielding materials
    • G21F1/10—Organic substances; Dispersions in organic carriers

Definitions

  • the invention relates to a container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of a container body and a protective layer applied to the outer surface, the protective layer being made of a plastic from the group consisting of polyurethane, polytetrafluoroethylene, polycarbonate, Epoxy resins, phenol formaldehyde resins and acrylate rubber.
  • 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.
  • Very complex concepts are known in some cases for storing the irradiated fuel elements in metal, concrete in salt, sand or in rock caverns.
  • Containers made of alloyed and unexposed 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 must be reloaded from the transport container into the final storage container at considerable expense.
  • Repository containers for spent fuel elements have also been proposed, which consist of alloyed and unalloyed steels with galvanic protective layers selected according to the electrochemical voltage series. These known externally applied protective layers are often sensitive to mechanical loads, they can be partially destroyed and, in the event of a malfunction, corrosion can proceed from these damaged areas.
  • a storage concept for radioactive waste is known from US-A-3935467, in which a large number of smaller containers containing the waste are accommodated in a larger, corrosion-resistant container. The spaces between these containers are filled with a shock-absorbing polyurethane foam. This polyurethane foam cannot perform corrosion-inhibiting and fission product retention functions.
  • the invention was therefore based on the object of providing a container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, consisting of a container base body and a protective layer applied to the outer surface, the outer protective layer being made of a plastic from the Group of polyurethanes, polytetrafluoroethylene, polycarbonate, epoxy resins, phenol formaldehyde resins and acrylic rubber and is suitable for any cheap basic container body, has the highest possible protection against corrosion and offers protection against mechanical damage, and prevents leakage products from escaping from the repository.
  • the object is achieved in that a filler which has swellable, ion-exchange and adsorptive properties in the presence of water is incorporated in the protective layer.
  • Layered silicates of the montmorillonite type have proven particularly useful as fillers. Bentonite is preferably used for this, while polyurethane has proven to be particularly suitable as the plastic component.
  • the two-component system of the polyurethane contains bentonite as a filler in one component.
  • the two components of the polyurethane system After the two components of the polyurethane system have reacted on the surface of the repository, the latter has a well-adhering and dense coating that contains bentonite in a homogeneous distribution.
  • the coating has a surprisingly high mechanical resistance to pressure and shock and thus reliably prevents damage to the body of the container.
  • this polyurethane coating with the filler it contains against brine as it would be present in the repository formations intended in Germany in the event of a fault, is absolutely corrosion-resistant.
  • the bentonite preferably contained in the polyurethane as a filler offers additional protection and forms a second barrier. If the plastic layer is damaged, e.g. B. a crack, the filler is exposed. This swells in the presence of water to 4 to 7 times its volume and thus seals the crack that has formed.
  • the layered silicate filling offers protection against the discharge of fission products from a damaged repository.
  • Bentonite has both adsorptive and ion exchange properties. Fission products emerging from the final storage container would thus be bound to the bentonite both by adsorption and by ion exchange and be prevented from entering the biosphere.
  • the protective layer according to the invention offers multiple protection and significantly increases the safety of the final storage of spent fuel elements.
  • the figure shows schematically an exemplary embodiment of the container according to the invention.
  • a protective layer (2) consisting of a well-adhering plastic and a swellable filler is applied to the container body (1).

Landscapes

  • Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Dispersion Chemistry (AREA)
  • Chemical & Material Sciences (AREA)
  • Environmental & Geological Engineering (AREA)
  • Laminated Bodies (AREA)
  • Processing Of Solid Wastes (AREA)
  • Wrappers (AREA)
  • Details Of Rigid Or Semi-Rigid Containers (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Packages (AREA)

Claims (3)

1. Récipient pour le stockage de longue durée de déchets radioactifs, en particulier d'éléments combustibles consumés dans des formations géologiques appropriées, constitué d'un corps de base de ce récipient et d'une couche protectrice appliquée sur la surface extérieure, où la couche protectrice (2) est constituée d'une matière plastique du groupe des polyuréthane, po- lytétrafluoréthylène, polycarbonate, résines époxy, résines phénol-formol et caoutchouc d'acrylate; récipient caracttérisé en ce qu'il est incorporé dans la couche protectrice (2), une charge capable de gonfler en présente d'eau, et d'assurer un échange d'ions, présentant des propriétés adsorbantes.
2. Récipient suivant la revendication 1, caractérisé en ce que la charge est un silicate feuilleté du type de la montmorillonite.
3. Récipient suivant les revendications 1 et 2, caractérisé en ce que l'on utilise, comme silicate feuilleté, la bentonite.
EP82106184A 1981-08-19 1982-07-10 Conteneur pour le stockage à long terme de déchets radioactifs Expired EP0072429B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3132704 1981-08-19
DE3132704A DE3132704C2 (de) 1981-08-19 1981-08-19 Behälter zur Langzeitlagerung radioaktiver Abfälle

Publications (2)

Publication Number Publication Date
EP0072429A1 EP0072429A1 (fr) 1983-02-23
EP0072429B1 true EP0072429B1 (fr) 1985-04-17

Family

ID=6139600

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82106184A Expired EP0072429B1 (fr) 1981-08-19 1982-07-10 Conteneur pour le stockage à long terme de déchets radioactifs

Country Status (6)

Country Link
EP (1) EP0072429B1 (fr)
JP (1) JPS5840000A (fr)
BR (1) BR8204782A (fr)
CA (1) CA1170845A (fr)
DE (2) DE3132704C2 (fr)
ES (1) ES280865Y (fr)

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
HU191255B (en) * 1984-03-05 1987-01-28 Eroemue- Es Halozattervezoe Vallalat,Hu Container for transporting radioactive matters
JPS6190995U (fr) * 1984-11-19 1986-06-13
DE3447278A1 (de) * 1984-12-22 1986-06-26 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Langzeitbestaendige korrosionsschutzumhuellung fuer dicht verschlossene gebinde mit hochradioaktivem inhalt
DE3520450A1 (de) * 1985-06-07 1986-12-11 Gattys Technique S.A., Freiburg/Fribourg Strahlenschutzbehaelter zum transport und zur lagerung radioaktiver materialien und verfahren zu seiner herstellung
GB2176925A (en) * 1985-06-19 1987-01-07 Us Energy Waste disposal package
GB2217631A (en) * 1988-03-31 1989-11-01 Westinghouse Electric Corp Method for attenuating gas diffusion through a structure
DE3927815C2 (de) * 1989-08-23 1999-12-23 Sipra Patent Beteiligung Plüsch- oder Florstrickware und Rundstrickmaschine zu deren Herstellung
EP1124234A1 (fr) * 2000-02-11 2001-08-16 Jesse Yang Méthode pour le scellementet l'emballage des déchets toxiques
DE10329170A1 (de) * 2003-06-27 2005-01-13 Polybern Gmbh Verbessertes Verfahren zum Einschluss von Sonderabfall
DE102011051991A1 (de) * 2011-07-20 2013-01-24 Siempelkamp Nukleartechnik Gmbh Verfahren zur Ertüchtigung eines Abfallbehälters
DE102011085480A1 (de) 2011-10-28 2013-05-02 Volkmar Gräf Behältersystem zur endlagerung von radioaktivem abfall und/oder giftmüll
DE102014002390B3 (de) * 2014-02-24 2015-05-13 Cura Ingenieurgesellschaft Mbh Behälter zur Lagerung von radioaktivem Abfall
FR3030864B1 (fr) * 2014-12-22 2020-04-24 Tn International Utilisation d'une composition elastomerique chargee pour la fabrication d'un joint pour emballage de matiere radioactive, joint et emballage associes

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1350579A (fr) * 1963-03-18 1964-01-24 Substance sorbante et son procédé de fabrication
DE2065863B2 (de) * 1969-08-13 1981-07-16 Transnucléaire, Société pour les Transports de l'Industrie Nucléaire, Paris Behälter für die Lagerung und den Transport von radioaktiven Materialien
FR2199479A1 (en) * 1972-09-15 1974-04-12 Peabody Gci Absorbent/filter for gas or liquid - with powder absorber sandwiched between fibrous or open-cellular sheets, esp. used as continuous band
US3951859A (en) * 1972-12-30 1976-04-20 Toyo Jozo Co., Ltd. Molecular sieving particle and preparation thereof
US3935467A (en) * 1973-11-09 1976-01-27 Nuclear Engineering Co., Inc. Repository for fissile materials
FR2473213B1 (fr) * 1980-01-07 1986-03-21 Ecopo Dispositif de confinement a long terme de dechets radioactifs ou toxiques et son procede de fabrication

Also Published As

Publication number Publication date
CA1170845A (fr) 1984-07-17
DE3132704C2 (de) 1985-12-19
JPS5840000A (ja) 1983-03-08
DE3263122D1 (en) 1985-05-23
DE3132704A1 (de) 1983-03-10
EP0072429A1 (fr) 1983-02-23
ES280865Y (es) 1985-08-01
ES280865U (es) 1985-02-01
BR8204782A (pt) 1983-08-02

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