EP0072429A1 - 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
EP0072429A1
EP0072429A1 EP82106184A EP82106184A EP0072429A1 EP 0072429 A1 EP0072429 A1 EP 0072429A1 EP 82106184 A EP82106184 A EP 82106184A EP 82106184 A EP82106184 A EP 82106184A EP 0072429 A1 EP0072429 A1 EP 0072429A1
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.)
Granted
Application number
EP82106184A
Other languages
German (de)
English (en)
Other versions
EP0072429B1 (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 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.
  • spent fuel elements After being temporarily stored in the water basin, irradiated, spent fuel elements are processed either immediately or after a limited period of intermediate storage, during which the nuclear fuels and broods are separated from the fission products and returned to the fuel cycle.
  • 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 not either sufficiently corrosion-resistant or, like copper, 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 sealing 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.
  • 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 grater. 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.
  • the invention was therefore based on the object of creating 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 container protective layer applied to the outer surface, the outer protective layer being suitable for any base body that is as cheap as possible, having the highest possible corrosion protection and offering protection against mechanical damage, and preventing fission products from escaping from the repository.
  • the protective layer consists of a well-adhering plastic in which a filler which has swellable, ion-exchangeable and adsorptive properties in the presence of water is incorporated.
  • 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.
  • polytetrafluoroethylene, polycarbonate, epoxy resins, phenol formaldehyde resins or acrylate rubber can also be used as the plastic component.
  • a 1-3 cm thick layer of polyurethane for example, is applied to the outside of the closed final storage container, which contains spent fuel elements or individual rods, the two-component system of the polyurethane containing 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 tight coating which 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 exist in the repository formations provided for 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. a crack, the filler is exposed. This swells in the presence of water to 4-7 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 thus 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)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physics & Mathematics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Dispersion Chemistry (AREA)
  • Chemical & Material Sciences (AREA)
  • Laminated Bodies (AREA)
  • Processing Of Solid Wastes (AREA)
  • Details Of Rigid Or Semi-Rigid Containers (AREA)
  • Wrappers (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Packages (AREA)
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 true EP0072429A1 (fr) 1983-02-23
EP0072429B1 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)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2176925A (en) * 1985-06-19 1987-01-07 Us Energy Waste disposal package
FR2629625A1 (fr) * 1988-03-31 1989-10-06 Westinghouse Electric Corp Procede et appareil pour attenuer la diffusion de gaz a travers une 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
WO2005006349A1 (fr) * 2003-06-27 2005-01-20 Polybern Gmbh Amelioration apportee a un procede de confinement de dechets speciaux
WO2013060326A1 (fr) 2011-10-28 2013-05-02 Graef Volkmar Système de conteneurs pour le stockage intermédiaire ou définitif de déchets radioactifs et/ou toxiques
WO2015124773A1 (fr) * 2014-02-24 2015-08-27 Cura Ingenieurgesellschaft Mbh Récipient pour le stockage des déchets radioactifs

Families Citing this family (6)

* 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
DE102011051991A1 (de) * 2011-07-20 2013-01-24 Siempelkamp Nukleartechnik Gmbh Verfahren zur Ertüchtigung eines Abfallbehälters
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

Citations (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
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
US3935467A (en) * 1973-11-09 1976-01-27 Nuclear Engineering Co., Inc. Repository for fissile materials
US3951859A (en) * 1972-12-30 1976-04-20 Toyo Jozo Co., Ltd. Molecular sieving particle and preparation thereof
DE2065863A1 (de) * 1969-08-13 1976-09-23 Transnucleaire Behaelter fuer radioaktive materialien
FR2473213A1 (fr) * 1980-01-07 1981-07-10 Ecopo Dispositif de confinement a long terme de dechets radioactifs ou toxiques et son procede de fabrication

Patent Citations (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
DE2065863A1 (de) * 1969-08-13 1976-09-23 Transnucleaire Behaelter fuer radioaktive 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
FR2473213A1 (fr) * 1980-01-07 1981-07-10 Ecopo Dispositif de confinement a long terme de dechets radioactifs ou toxiques et son procede de fabrication

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
SPRECHSAAL, Band 113, Nr. 10, Oktober 1980, Seiten 753-764, Coburg, DE. *

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2176925A (en) * 1985-06-19 1987-01-07 Us Energy Waste disposal package
FR2629625A1 (fr) * 1988-03-31 1989-10-06 Westinghouse Electric Corp Procede et appareil pour attenuer la diffusion de gaz a travers une 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
WO2005006349A1 (fr) * 2003-06-27 2005-01-20 Polybern Gmbh Amelioration apportee a un procede de confinement de dechets speciaux
WO2013060326A1 (fr) 2011-10-28 2013-05-02 Graef Volkmar Système de conteneurs pour le stockage intermédiaire ou définitif de déchets radioactifs et/ou toxiques
DE102011085480A1 (de) 2011-10-28 2013-05-02 Volkmar Gräf Behältersystem zur endlagerung von radioaktivem abfall und/oder giftmüll
WO2015124773A1 (fr) * 2014-02-24 2015-08-27 Cura Ingenieurgesellschaft Mbh Récipient pour le stockage des déchets radioactifs

Also Published As

Publication number Publication date
DE3132704A1 (de) 1983-03-10
CA1170845A (fr) 1984-07-17
ES280865Y (es) 1985-08-01
JPS5840000A (ja) 1983-03-08
DE3263122D1 (en) 1985-05-23
BR8204782A (pt) 1983-08-02
DE3132704C2 (de) 1985-12-19
EP0072429B1 (fr) 1985-04-17
ES280865U (es) 1985-02-01

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