EP0082267B1 - Moulded body for encapsulating radioactive wastes, and process for manufacturing this body - Google Patents

Moulded body for encapsulating radioactive wastes, and process for manufacturing this body Download PDF

Info

Publication number
EP0082267B1
EP0082267B1 EP82109825A EP82109825A EP0082267B1 EP 0082267 B1 EP0082267 B1 EP 0082267B1 EP 82109825 A EP82109825 A EP 82109825A EP 82109825 A EP82109825 A EP 82109825A EP 0082267 B1 EP0082267 B1 EP 0082267B1
Authority
EP
European Patent Office
Prior art keywords
graphite
nickel
waste
radioactive
manufacturing
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
EP82109825A
Other languages
German (de)
French (fr)
Other versions
EP0082267A1 (en
Inventor
Karl Gerhard Dr. Dipl.-Chem. Hackstein
Milan Dr. Dipl.-Ing. Hrovat
Hans Dr. Dipl.-Chem. Huschka
Lothar Rachor
Thomas Dr. 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.)
Nukem GmbH
Original Assignee
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 Nukem GmbH filed Critical Nukem GmbH
Publication of EP0082267A1 publication Critical patent/EP0082267A1/en
Application granted granted Critical
Publication of EP0082267B1 publication Critical patent/EP0082267B1/en
Expired legal-status Critical Current

Links

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 shaped body made of graphite with nickel sulfide as a binder for the safe long-term incorporation of radioactive and toxic waste and a method for producing such shaped bodies.
  • Spent fuel elements from nuclear reactors have to be disposed of for a final disposal after a certain period of time.
  • Two ways have been investigated worldwide, namely the reprocessing of the fuel elements with the return of the fuels to the fuel element production as well as the separation and final storage of the fission products (highly active waste) and alternatively the direct final storage of the spent elements. 1
  • highly active waste is generated that must be safely stored in suitable geological formations for 1000 years and more.
  • Other, highly radioactive and highly toxic waste must also be kept away from the biosphere.
  • Nickel sulfide (DE-A No. 2917437) is preferably used as the binder.
  • Such moldings are very dense and have good resistance to corrosion and leaching, in particular to salt solutions, which in some cases has not yet proven to be optimal.
  • the nickel sulfide is predominantly in the form of Ni 3 S 2 . At least 80% of the introduced nickel sulfide is preferably present as defined Ni 3 S 2 in the graphite matrix.
  • Molded graphite bodies containing radioactive or toxic waste and containing Ni 3 S 2 as binders have an extremely high resistance to corrosion and leaching out of salt solutions.
  • the shaped articles contain, in addition to the embedded waste, 25 to 90% by weight of nickel sulfide (Ni 3 S 2 ), in particular 45 to 60% by weight of nickel sulfide (Ni s S z ), the rest of the graphite.
  • Ni 3 S 2 nickel sulfide
  • Ni s S z nickel sulfide
  • These moldings are produced by pressing a mixture of radioactive and / or toxic waste, graphite, sulfur and nickel powder at temperatures above 100 ° C., 35 to 45 g of sulfur powder being added to 100 g of nickel powder and pressing at temperatures between 400 and 500 ° C because the sulfur can sublimate from the molding compound to a small extent, depending on the process.
  • the graphite-Ni 3 S 2 matrix Because of the extremely high long-term stability of the graphite-Ni 3 S 2 matrix, it can also be used to integrate long-life a-lamps, such as plutonium.

Description

Die Erfindung betrifft einen Formkörper aus Graphit mit Nickelsulfid als Bindemittel zur sicheren Langzeiteinbindung von radioaktiven und toxischen Abfällen und ein Verfahren zur Herstellung solcher Formkörper.The invention relates to a shaped body made of graphite with nickel sulfide as a binder for the safe long-term incorporation of radioactive and toxic waste and a method for producing such shaped bodies.

Abgebrannte Brennelemente aus Kernreaktoren müssen nach einer gewissen Zeit der Zwischenlagerung einer Endbeseitigung zugeführt werden. Weltweit wurden dazu zwei Wege untersucht, nämlich die Wiederaufarbeitung der Brennelemente mit Rückführung der Brennstoffe in die Brennelementfertigung sowie Abtrennung und Endlagerung der Spaltprodukte (hochaktiver Abfall) und alternativ die direkte Endlagerung der abgebrannten Elemente. 1 jedem Fall entsteht hochaktiver Abfall, der 1000 Jahre und mehr sicher in geeignete geologische Formationen eingelagert werden muss. Auch sonstiger, hochradioaktiver und hochtoxischer Abfall muss sicher von der Biosphäre ferngehalten werden.Spent fuel elements from nuclear reactors have to be disposed of for a final disposal after a certain period of time. Two ways have been investigated worldwide, namely the reprocessing of the fuel elements with the return of the fuels to the fuel element production as well as the separation and final storage of the fission products (highly active waste) and alternatively the direct final storage of the spent elements. 1 In every case, highly active waste is generated that must be safely stored in suitable geological formations for 1000 years and more. Other, highly radioactive and highly toxic waste must also be kept away from the biosphere.

Zum sicheren Langzeiteinschluss solcher radioaktiver und toxischer Abfälle sind zahlreiche Behältertypen vorgeschlagen worden, die die geforderten Bedingungen, wie dichter Einschluss bei den auftretenden Drücken und Temperaturen oder Korrosionsfestigkeit gegen Salzlaugen, gut erfüllen. Als Behältermaterial werden vielerlei metallische und nichtmetallische Werkstoffe verwendet.For the safe long-term containment of such radioactive and toxic waste, numerous types of containers have been proposed which well meet the required conditions, such as tight containment at the pressures and temperatures that occur or corrosion resistance against brine. Various metallic and non-metallic materials are used as container material.

Da Graphit eine hervorragende Korrosionsbeständigkeit besitzt, ist vorgeschlagen worden (DE-A Nr. 2942092), Behälter mit einer Korrosionsschutzschicht aus Graphit zu versehen. Da Graphitformkörper der für die Aufnahme eines Brennelementes notwendigen Abmessungen weder gas- noch flüssigkeitsdicht herzustellen sind, ist eine anschliessende Beschichtung mit Pyrokohlenstoff oder Siliciumkarbid vorgesehen. Nach dem Einfüllen des Brennelements soll der beschichtete Behälter mit einem gleichermassen beschichteten Deckel gas- und flüssigkeitsdicht verschlossen werden. Hierbei sollen Graphitdichtungen bzw. geeignete Klebemittel zum Einsatz kommen. Ein wesentlicher Nachteil dieses Behälterkonzepts ist der ausserordentlich hohe technische Aufwand, der für die Herstellung und Beschichtung von Behältern mit grossen Abmessungen notwendig ist. Ausserdem lassen sich solche grossen Formkörper nicht in den geforderten Qualitätsansprüchen beschichten.Since graphite has excellent corrosion resistance, it has been proposed (DE-A No. 2942092) to provide containers with a corrosion protection layer made of graphite. Since graphite moldings of the dimensions required for accommodating a fuel assembly cannot be made gas-tight or liquid-tight, a subsequent coating with pyrocarbon or silicon carbide is provided. After the fuel element has been filled in, the coated container is to be closed in a gastight and liquid-tight manner with an equally coated lid. Here graphite seals or suitable adhesives should be used. A major disadvantage of this container concept is the extraordinarily high technical effort that is necessary for the production and coating of containers with large dimensions. In addition, such large moldings cannot be coated in the required quality requirements.

Es ist auch bekannt, zur Einbindung von radioaktiven und toxischen Abfällen Formkörper aus einer Kohlenstoffmatrix herzustellen, indem man Graphitpulver mit einem Bindemittel presst. Als Bindemittel verwendet man hierbei vorzugsweise Nickelsulfid (DE-A Nr. 2917437). Solche Formkörper sind sehr dicht und besitzen eine gute Korrosions- und Auslaugebeständigkeit, insbesondere gegenüber Salzlösungen, die sich allerdings in manchen Fällen als noch nicht optimal erwies.It is also known to produce molded articles from a carbon matrix for the incorporation of radioactive and toxic waste by pressing graphite powder with a binder. Nickel sulfide (DE-A No. 2917437) is preferably used as the binder. Such moldings are very dense and have good resistance to corrosion and leaching, in particular to salt solutions, which in some cases has not yet proven to be optimal.

Es war daher Aufgabe der vorliegenden Erfindung, einen Formkörper aus Graphit mit Nickelsulfid als Bindemittel zur sicheren Langzeiteinbindung von radioaktiven und toxischen Abfällen zu schaffen, der eine möglichst hohe Korrosions- und Auslaugebeständigkeit aufweist.It was therefore an object of the present invention to provide a shaped body made of graphite with nickel sulfide as a binder for the safe long-term incorporation of radioactive and toxic waste, which has the highest possible resistance to corrosion and leaching.

Diese Aufgabe wurde erfindungsgemäss dadurch gelöst, dass das Nickelsulfid überwiegend als Ni3S2 vorliegt. Vorzugsweise liegen mindestens 80% des eingebrachten Nickelsulfids als definiertes Ni3S2 in der Graphitmatrix vor.This object was achieved according to the invention in that the nickel sulfide is predominantly in the form of Ni 3 S 2 . At least 80% of the introduced nickel sulfide is preferably present as defined Ni 3 S 2 in the graphite matrix.

Mit radioaktiven oder toxischen Abfällen versetzte Graphitformkörper, die als Bindemittel Ni3S2 enthalten, besitzen eine extrem hohe Korrosions- und Auslaugebeständigkeit gegenüber Salzlösungen.Molded graphite bodies containing radioactive or toxic waste and containing Ni 3 S 2 as binders have an extremely high resistance to corrosion and leaching out of salt solutions.

Als günstig hat es sich herausgestellt, wenn die Formkörper neben den eingebetteten Abfällen 25 bis 90 Gew.-% Nickelsulfid (Ni3S2), insbesondere 45 bis 60 Gew.-% Nickelsulfid (NisSz), Rest Graphit enthalten. Die Sicherheit der Einbindung von Abfällen gegen chemisches oder mechanisches Herauslösen lässt sich weiterhin verbessern, wenn man die Abfälle in einem Kern einbettet, der von einer abfallfreien Schale aus dem gleichen Material umgeben ist.It has proven to be advantageous if the shaped articles contain, in addition to the embedded waste, 25 to 90% by weight of nickel sulfide (Ni 3 S 2 ), in particular 45 to 60% by weight of nickel sulfide (Ni s S z ), the rest of the graphite. The security of the integration of waste against chemical or mechanical extraction can be further improved if the waste is embedded in a core which is surrounded by a waste-free shell made of the same material.

Die Herstellung dieser Formkörper erfolgt durch Pressen eines Gemisches aus radioaktiven und/ oder toxischen Abfällen, Graphit-, Schwefel- und Nickelpulver bei Temperaturen oberhalb 100° C, wobei auf 100 g Nickelpulver 35 bis 45 g Schwefelpulver zugesetzt werden und das Pressen bei Temperaturen zwischen 400 und 500° C erfolgt, da der Schwefel je nach Verfahrensführung zu einem geringen Teil aus der Pressmasse absublimieren kann.These moldings are produced by pressing a mixture of radioactive and / or toxic waste, graphite, sulfur and nickel powder at temperatures above 100 ° C., 35 to 45 g of sulfur powder being added to 100 g of nickel powder and pressing at temperatures between 400 and 500 ° C because the sulfur can sublimate from the molding compound to a small extent, depending on the process.

Wegen der extrem hohen Langzeitbeständigkeit der Graphit-Ni3S2-Matrix kann diese auch zum Einbinden langlebiger a-Strahler, wie beispielsweise Plutonium, verwendet werden.Because of the extremely high long-term stability of the graphite-Ni 3 S 2 matrix, it can also be used to integrate long-life a-lamps, such as plutonium.

Folgendes Beispiel soll die Erfindung näher erläutern:

  • Als Ausgangspulver wurde eine Mischung aus 43,7 Gew.-% Feinpudernaturgraphit, 15 Gew.-% feingemahlenem Schwefel und 41,3 Gew.-% Nikkelmetallpulver durch Trockenmischen hergestellt. In diese Mischung wurden aktive Abfälle eingebettet.
The following example is intended to explain the invention in more detail:
  • A mixture of 43.7% by weight of fine powder natural graphite, 15% by weight of finely ground sulfur and 41.3% by weight of nickel metal powder was prepared as the starting powder by dry mixing. Active waste was embedded in this mixture.

Der fertiggepresste Formkörper hatte folgende Eigenschaften:

  • Matrixdichte: 3,36 g/cm3
  • Dichte: 97% der theoretischen Dichte
  • Wärmeleitfähigkeit: 0,8 W/cm - ° K
  • Linear thermischer Ausdehnungskoeffizient: 9,2µm/m·°K
  • Druckfestigkeit: 107 MN/m2
The finished molded body had the following properties:
  • Matrix density: 3.36 g / cm 3
  • Density: 97% of the theoretical density
  • Thermal conductivity: 0.8 W / cm - ° K
  • Linear coefficient of thermal expansion: 9.2µm / m · ° K
  • Compressive strength: 107 MN / m 2

Die Auslaugebeständigkeit in Salzlösungen war sehr gut.The resistance to leaching in salt solutions was very good.

Claims (5)

1. Moulding consisting of graphite with nickel sulphide as binder for the safe long-term containment of radioactive and toxic waste materials, characterised in that the nickel sulphide is predominantly in the form of Ni3S2.
2. Moulding according to Claim 1, characterised in that at least 80% of the nickel sulphide is in the form of Ni3S2.
3. Moulding according to Claims 1 and 2, characterised in that, in addition to the embedded waste materials, it consists of from 25 to 90% by weight of nickel sulphide and the remainder of graphite.
4. Moulding according to Claims 1 to 3, characterised in that it consists of a core, in which the waste materials are embedded, and of a waste material-free shell of the same material.
5. Process for the production of mouldings according to Claims 1 to 4 by pressing a mixture of radioactive and/or toxic waste, graphite, sulphur and nickel powders at a temperature of above 100°C, characterised in that from 35 to 45 g sulphur powder are added per 100 g of nickel powder and pressing takes place at a temperature of from 400 to 500° C.
EP82109825A 1981-11-11 1982-10-23 Moulded body for encapsulating radioactive wastes, and process for manufacturing this body Expired EP0082267B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3144764 1981-11-11
DE19813144764 DE3144764A1 (en) 1981-11-11 1981-11-11 MOLDED BODY FOR INCLUDING RADIOACTIVE WASTE AND METHOD FOR THE PRODUCTION THEREOF (II)

Publications (2)

Publication Number Publication Date
EP0082267A1 EP0082267A1 (en) 1983-06-29
EP0082267B1 true EP0082267B1 (en) 1985-04-10

Family

ID=6146116

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82109825A Expired EP0082267B1 (en) 1981-11-11 1982-10-23 Moulded body for encapsulating radioactive wastes, and process for manufacturing this body

Country Status (8)

Country Link
US (1) US4560502A (en)
EP (1) EP0082267B1 (en)
JP (1) JPS5887500A (en)
BR (1) BR8206479A (en)
CA (1) CA1170824A (en)
DE (2) DE3144764A1 (en)
ES (1) ES8402672A1 (en)
FI (1) FI74835C (en)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
AT385435B (en) * 1986-03-07 1988-03-25 Oesterr Forsch Seibersdorf METHOD AND DEVICE FOR EMBEDDING AND, IF NECESSARY, REACTIVATING, IN PARTICULAR, TOXIC AND / OR RADIOACTIVE SUBSTANCES OR. DISEASE
US5360632A (en) * 1993-08-10 1994-11-01 Phillips Petroleum Company Reduced leaching of arsenic and/or mercury from solid wastes
GB0415335D0 (en) * 2004-07-08 2004-08-11 British Nuclear Fuels Plc Method for the handling and minimisation of waste
EA021732B1 (en) 2008-11-10 2015-08-31 Алд Вакуум Текнолоджиз Гмбх Matrix material composed of graphite and inorganic binders and suitable for final storage of radioactive waste, method for the manufacture thereof, and processing and use thereof
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
DE102012112643A1 (en) 2012-12-19 2014-06-26 Ald Vacuum Technologies Gmbh Graphite matrix, useful for the preparation of a molded body to store radioactive waste, comprises graphite and a metallic binder
DE102012112642A1 (en) 2012-12-19 2014-06-26 Ald Vacuum Technologies Gmbh Graphite matrix, useful for manufacturing a molded body to store radioactive waste, comprises graphite and glass ceramic
DE102012112648B4 (en) 2012-12-19 2016-08-04 Ald Vacuum Technologies Gmbh Graphite matrix with crystalline binder

Family Cites Families (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2990352A (en) * 1950-02-21 1961-06-27 Finniston Harold Montague Metal sheathed bodies
US2969294A (en) * 1954-03-18 1961-01-24 James J Shyne Method of impregnating uranium in graphite
GB1051776A (en) * 1963-10-17
US3361638A (en) * 1967-04-07 1968-01-02 Atomic Energy Commission Usa Pyrolytic graphite and nuclear fuel particles coated therewith
US3753854A (en) * 1969-07-04 1973-08-21 Nukem Gmbh Production of a fuel carbide with a jacket of fuel nitride,sulfide orphosphide
US3866043A (en) * 1970-04-20 1975-02-11 Central Electr Generat Board Coated particle fuel for nuclear reactors and to the manufacture of such fuel
DE2362088A1 (en) * 1973-12-14 1975-06-26 Hobeg Hochtemperaturreaktor GRAPHITE BALL BURNER FOR HIGH-TEMPERATURE REACTORS AND PROCESS FOR ITS PROCESSING AFTER RADIATION
US4134941A (en) * 1973-12-14 1979-01-16 Hobeg Hochtemperaturreaktor-Brennelement Gmbh Spherical fuel elements made of graphite for temperature reactors and process for reworking it after the irradiation
GB1468233A (en) * 1974-02-08 1977-03-23 Atomic Energy Authority Uk Preparation for storage of fission products
SU571143A1 (en) * 1976-03-24 1980-01-25 Предприятие П/Я Р-6575 Method of manufacturing matrix for radioactive sources
DE2654536C2 (en) * 1976-12-02 1978-10-19 Hobeg Hochtemperaturreaktor-Brennelement Gmbh, 6450 Hanau Process for the production of spherical fuel elements for high-temperature reactors
US4257912A (en) * 1978-06-12 1981-03-24 Westinghouse Electric Corp. Concrete encapsulation for spent nuclear fuel storage
DE2917437C2 (en) * 1979-04-28 1983-11-17 Nukem Gmbh, 6450 Hanau Procedure for incorporating radioactive and toxic waste
DE2942092C2 (en) * 1979-10-18 1985-01-17 Steag Kernenergie Gmbh, 4300 Essen Final storage containers for radioactive waste, in particular irradiated nuclear reactor fuel elements
DE3103557A1 (en) * 1981-02-03 1982-12-09 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover "TRANSPORT AND STORAGE CONTAINERS FOR RADIOACTIVE WASTE"

Also Published As

Publication number Publication date
DE3144764A1 (en) 1983-05-26
BR8206479A (en) 1983-09-27
ES517239A0 (en) 1984-02-01
JPS5887500A (en) 1983-05-25
CA1170824A (en) 1984-07-17
FI74835B (en) 1987-11-30
EP0082267A1 (en) 1983-06-29
ES8402672A1 (en) 1984-02-01
FI823334L (en) 1983-05-12
DE3263020D1 (en) 1985-05-15
FI74835C (en) 1988-03-10
US4560502A (en) 1985-12-24
FI823334A0 (en) 1982-09-29

Similar Documents

Publication Publication Date Title
EP0082267B1 (en) Moulded body for encapsulating radioactive wastes, and process for manufacturing this body
DE2917437A1 (en) METHOD FOR CONDITIONING RADIOACTIVE AND TOXIC WASTE
DE102010003289B4 (en) Containers for the storage of radioactive waste and process for its production
EP0081084A1 (en) Moulded body for encapsulating radioactive wastes, and process for manufacturing this body
EP0081660B1 (en) Moulded body for encapsulating spent nuclear fuel elements, and process for manufacturing this body
GB2041912A (en) Moulded bodies containing radioactive waste
DE102009044963B4 (en) Graphite matrix blocks with inorganic binder suitable for storage of radioactive waste and method of making the same
EP0365162A3 (en) Nuclear fuel and method of making compacts with precise amounts thereof
EP0057430A1 (en) Container for transporting and storing radioactive wastes
DE3048001A1 (en) METHOD FOR THE PRODUCTION OF REAL-END BEARING TIRES, RADIOACTIVE MATERIALS WITH WASTE FASTENING PRODUCTS WITH INCREASED RADIATION RESISTANCE OR. REDUCED RADIOLYSE GAS FORMATION FROM THE CATEGORY OF RADIOACTIVE WASTE SHAPED BODIES STRENGTHENED WITH HYDRAULICALLY SETTING, HARDENING, INORGANIC MATERIALS
DE3046539A1 (en) METHOD AND DEVICE FOR PRODUCING TRITIUM
DE3731848A1 (en) Method for encapsulating waste materials
DE2856875C2 (en) Method of filling the interstices in a subterranean cavity containing radioactive waste
DE3532155C1 (en) Ultimately disposable bundle and method for producing it
EP0930620B1 (en) Storage container for the intermediate and/or final storage of spent fuel assemblies
DE1162694B (en) Process for coating components that are to be or are to be protected against neutron radiation
DE3212507A1 (en) Casks for the storage of radioactive substances having a ceramic corrosion-protective layer surrounding the substances
AT236542B (en) Reactor fuel element with a graphitic carbon shell
AT274977B (en) Nuclear fuel particles
DE2601767A1 (en) METHOD OF MANUFACTURING NUCLEAR FUEL BODIES
DE102012112648B4 (en) Graphite matrix with crystalline binder
DE1158641B (en) Process for the production of fuel elements for nuclear reactors
DE1934031C3 (en) Carbidic nuclear fuel particles and processes for their manufacture
DE1955581C3 (en) Process for the production of ceramic fuel bodies for nuclear reactor fuel elements
DE102010000974A1 (en) Form stable body for use as neutron absorber rod in transport container for transporting and/or storing e.g. fuel element in research plant in nuclear power station, has neutron absorber reacted to carbide in elementary form

Legal Events

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

Free format text: ORIGINAL CODE: 0009012

17P Request for examination filed

Effective date: 19821023

AK Designated contracting states

Designated state(s): BE CH DE FR GB LI SE

GRAA (expected) grant

Free format text: ORIGINAL CODE: 0009210

AK Designated contracting states

Designated state(s): BE CH DE FR GB LI SE

REF Corresponds to:

Ref document number: 3263020

Country of ref document: DE

Date of ref document: 19850515

ET Fr: translation filed
PLBE No opposition filed within time limit

Free format text: ORIGINAL CODE: 0009261

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

Free format text: STATUS: NO OPPOSITION FILED WITHIN TIME LIMIT

26N No opposition filed
PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: GB

Effective date: 19881023

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: SE

Effective date: 19881024

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: LI

Effective date: 19881031

Ref country code: CH

Effective date: 19881031

Ref country code: BE

Effective date: 19881031

BERE Be: lapsed

Owner name: NUKEM G.M.B.H.

Effective date: 19881031

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: FR

Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES

Effective date: 19890630

REG Reference to a national code

Ref country code: CH

Ref legal event code: PL

PG25 Lapsed in a contracting state [announced via postgrant information from national office to epo]

Ref country code: DE

Effective date: 19890701

GBPC Gb: european patent ceased through non-payment of renewal fee
REG Reference to a national code

Ref country code: FR

Ref legal event code: ST

EUG Se: european patent has lapsed

Ref document number: 82109825.8

Effective date: 19890619