EP0036954B1 - Conteneur pour le transport et le stockage de matières radioactives - Google Patents
Conteneur pour le transport et le stockage de matières radioactives Download PDFInfo
- Publication number
- EP0036954B1 EP0036954B1 EP81101461A EP81101461A EP0036954B1 EP 0036954 B1 EP0036954 B1 EP 0036954B1 EP 81101461 A EP81101461 A EP 81101461A EP 81101461 A EP81101461 A EP 81101461A EP 0036954 B1 EP0036954 B1 EP 0036954B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- graphite
- container according
- container
- inner lining
- neutron
- 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
Links
- 239000000941 radioactive substance Substances 0.000 title description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 19
- 229910002804 graphite Inorganic materials 0.000 claims description 14
- 239000010439 graphite Substances 0.000 claims description 14
- 239000000463 material Substances 0.000 claims description 12
- 239000000203 mixture Substances 0.000 claims description 4
- 239000011358 absorbing material Substances 0.000 claims description 3
- 230000005855 radiation Effects 0.000 claims description 3
- 239000012857 radioactive material Substances 0.000 claims description 3
- 239000011230 binding agent Substances 0.000 claims description 2
- 239000003758 nuclear fuel Substances 0.000 claims description 2
- 239000000843 powder Substances 0.000 claims description 2
- 239000011347 resin Substances 0.000 claims description 2
- 229920005989 resin Polymers 0.000 claims description 2
- 239000007770 graphite material Substances 0.000 claims 2
- 229910052580 B4C Inorganic materials 0.000 claims 1
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims 1
- 239000002927 high level radioactive waste Substances 0.000 claims 1
- 230000009972 noncorrosive effect Effects 0.000 claims 1
- 230000000694 effects Effects 0.000 description 3
- 229910000831 Steel Inorganic materials 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 230000006378 damage Effects 0.000 description 2
- 238000000465 moulding Methods 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000005266 casting Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000002131 composite material Substances 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 235000019353 potassium silicate Nutrition 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 230000005258 radioactive decay Effects 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- NTHWMYGWWRZVTN-UHFFFAOYSA-N sodium silicate Chemical compound [Na+].[Na+].[O-][Si]([O-])=O NTHWMYGWWRZVTN-UHFFFAOYSA-N 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 230000003685 thermal hair damage Effects 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Images
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
- G21F5/00—Transportable or portable shielded containers
- G21F5/06—Details of, or accessories to, the containers
-
- 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
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
Definitions
- the invention relates to a container for transport and / or storage of radioactive materials, the ⁇ - and n-emit radiation, and generate significant residual heat, consisting of a container body with shielding function ⁇ - and n-radiation and an inner liner.
- Containers that are used for the transport and / or storage of spent fuel elements must safely contain the radioactivity of the goods brought in and demonstrate in rigorous tests that this is guaranteed even in extreme accident situations. At the same time, however, they must also shield the gamma and neutron beams released during the radioactive decay reactions and dissipate the heat of decay to the outside. The shielding function must remain largely intact even after an accident, its integrity must be easily verifiable.
- Known shielding containers usually consist of a metallic base container with the required mechanical strength and the wall thickness required to shield the gamma rays, usually made of steel, and an outer shell made of neutron shielding material, mostly with organic substances high hydrogen content or in the form of a water jacket.
- a disadvantage of these constructions is that even slight collisions of the container, as can also occur during routine operation, can damage the neutron shielding and afterwards require extensive repair of the entire container. In the event of a serious accident, characterized by high impact forces and exposure to fire, this neutron shielding can fail completely and the dose rate in the vicinity of the container can increase.
- DE-B2-2 040 348 also describes a container in which the neutron shield is arranged in the base body under the outer skin.
- a container is also known from DE-A-2 019 446, in which neutron shielding material is arranged in the y absorption layer. Both container designs have the disadvantage that the neutron shielding layer is not freely accessible and cannot be inspected and, if necessary, repaired after an accident. Even in the event of a fire, this neutron shielding material is endangered and can easily be destroyed or ineffective.
- a container for the transport and / or storage of radioactive substances, in particular for irradiated nuclear fuel elements and highly active waste consisting of a base body with a shielding function for ⁇ and n radiation and an inner lining made of corrosion-resistant Material which has a further n-shield that is resistant to the effects of external accidents, in order to maintain sufficient shielding effect in the event of loss or damage to the outer n-shield.
- this additional shielding should not hinder the dissipation of the decay heat from the interior of the container.
- the n-shield should be easily accessible and easy to repair.
- n-shield in the form of a graphite-based material is additionally arranged between the inner lining and the base body.
- the inventive position of the additional n-shield within the solid base body ensures the best possible protection against mechanical and thermal damage, the shield is easily accessible, inspectable and repairable.
- the use of graphite according to the invention provides additional n-shielding and at the same time fulfills the requirement of good thermal conductivity. Furthermore, there is excellent resistance to elevated temperatures, such as those which occur during normal operation of the container and in particular when exposed to an accident fire.
- the moderating properties of graphite have the additional advantage that neutron activation of the container body is largely prevented.
- the n-shielding layers on the outside of the base body and the inner n-shielding according to the invention can be dimensioned such that, depending on the requirements, the inner or outer shielding layer makes the predominant contribution to shielding against neutron beams under normal operating conditions.
- I and 111 illustrate the invention in more detail schematically and by way of example.
- the transport and / or storage container consists of a base body 1, for example made of steel, on which cooling fins 2 and an outer n-shield 3 are arranged in a manner known per se.
- the interior 4 of the container for receiving the radioactive material is formed by the inner lining 5 made of corrosion-resistant material, for example stainless steel, and a shielding cover 6, which also carries n-shielding material 3 on its outside.
- the cover zone is protected against mechanical and thermal influences by a protective hood 7.
- n-shielding layer 8 made of a graphite-based material as a further neutron shield orderly.
- This graphite-based shielding layer 8 preferably consists of a mixture of graphite powder and a hardening binder, such as, for example, water glass or, above all, a casting resin.
- This mixture can either be introduced as such into the annular gap between the base body 1 and the inner lining 5 and hardened, or it can advantageously be prefabricated graphite moldings 9, z. B. in the manner of composite plasters that are adapted to the gap dimensions can be used. These shaped pieces can also be covered with a metallic jacket 10, preferably made of neutron-absorbing material. It is also possible to press a stampable graphite mass into the annular gap.
- the function of the inner lining 5 can be taken over in a particularly advantageous manner by the metallic shells 10 which surround the graphite shaped pieces 9.
- the separate inner lining 5 can then be omitted partially or completely.
- the GraphicsGro t formstük- ke 9 are particularly low attached to the inside of the base body 1, for example by guide rails 12.
- the shielding layer 8 can be easily adapted to the respective requirements by changing graphite moldings 9 of different thicknesses.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Laminated Bodies (AREA)
- Filling Or Discharging Of Gas Storage Vessels (AREA)
- Packages (AREA)
Claims (10)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19803012256 DE3012256A1 (de) | 1980-03-29 | 1980-03-29 | Behaelter zum transport und/oder lagerung radioaktiver stoffe |
| DE3012256 | 1980-03-29 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| EP0036954A1 EP0036954A1 (fr) | 1981-10-07 |
| EP0036954B1 true EP0036954B1 (fr) | 1984-06-06 |
Family
ID=6098736
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP81101461A Expired EP0036954B1 (fr) | 1980-03-29 | 1981-02-28 | Conteneur pour le transport et le stockage de matières radioactives |
Country Status (4)
| Country | Link |
|---|---|
| US (1) | US4453081A (fr) |
| EP (1) | EP0036954B1 (fr) |
| DE (1) | DE3012256A1 (fr) |
| ES (1) | ES8305147A1 (fr) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2722214C1 (ru) * | 2019-09-13 | 2020-05-28 | Общество с ограниченной ответственностью "Керамические технологии" | Контейнер для хранения, транспортирования и захоронения радиоактивных отходов |
Families Citing this family (29)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3012256A1 (de) * | 1980-03-29 | 1981-10-15 | Transnuklear Gmbh, 6450 Hanau | Behaelter zum transport und/oder lagerung radioaktiver stoffe |
| DE3149945A1 (de) * | 1981-12-17 | 1983-07-21 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Behaelter fuer die langzeitlagerung von abgebrannten kernreaktorbrennelementen |
| EP0116412A1 (fr) * | 1983-01-18 | 1984-08-22 | Kabushiki Kaisha Kobe Seiko Sho | Récipient pour matériaux radioactifs et méthode pour sa fabrication |
| DE3324291C2 (de) * | 1983-07-06 | 1986-10-23 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Verfahren zum Befüllen von Metallbehältern mit einer radioaktiven Glasschmelze und Vorrichtung zur Aufnahme einer radioaktiven Glasschmelze |
| HU191255B (en) * | 1984-03-05 | 1987-01-28 | Eroemue- Es Halozattervezoe Vallalat,Hu | Container for transporting radioactive matters |
| DE3445124C1 (de) * | 1984-12-11 | 1986-01-23 | Nukem Gmbh, 6450 Hanau | Auskleidung fuer Bohrloecher in Salzstoecken |
| US4751021A (en) * | 1985-12-30 | 1988-06-14 | Aar Corporation | Bendable sheet material |
| DE3620737C1 (de) * | 1986-06-20 | 1987-10-01 | Wiederaufarbeitung Von Kernbre | Doppelbehaeltersystem zum Transport und zur Lagerung von radioaktiven Stoffen |
| US4868400A (en) * | 1987-09-02 | 1989-09-19 | Chem-Nuclear Systems, Inc. | Ductile iron cask with encapsulated uranium, tungsten or other dense metal shielding |
| GB8729504D0 (en) * | 1987-12-18 | 1988-02-03 | British Nuclear Fuels Plc | Transport & storage flask |
| US5406600A (en) * | 1993-10-08 | 1995-04-11 | Pacific Nuclear Systems, Inc. | Transportation and storage cask for spent nuclear fuels |
| JP3342994B2 (ja) * | 1995-08-04 | 2002-11-11 | 株式会社神戸製鋼所 | 放射性物質の輸送兼貯蔵用容器 |
| US5944190A (en) * | 1997-05-30 | 1999-08-31 | Mallinckrodt Inc. | Radiopharmaceutical capsule safe |
| RU2146402C1 (ru) * | 1998-01-13 | 2000-03-10 | Бабаянц Геннадий Иванович | Контейнер для твердых радиоактивных отходов |
| US6332906B1 (en) | 1998-03-24 | 2001-12-25 | California Consolidated Technology, Inc. | Aluminum-silicon alloy formed from a metal powder |
| US5965829A (en) * | 1998-04-14 | 1999-10-12 | Reynolds Metals Company | Radiation absorbing refractory composition |
| US6495846B1 (en) * | 1999-02-25 | 2002-12-17 | James A. Vaughan | Apparatus and method for nuclear waste storage |
| US7165672B2 (en) * | 2002-10-17 | 2007-01-23 | Mallinckrodt Inc. | Polymer pharmaceutical pig and associated method of use and associated method of production |
| USD488864S1 (en) | 2002-11-06 | 2004-04-20 | Mallinckrodt Inc. | Radioactive container |
| ATE385607T1 (de) * | 2002-12-24 | 2008-02-15 | Nuklear Service Gmbh Gns | Transport- und lagerbehälter für wärmeentwickelnde radioaktive stoffe, insbesondere abgebrannte kernreaktorbrennelemente oder haw-glaskokillen |
| RU2251165C2 (ru) * | 2003-07-14 | 2005-04-27 | Военная академия Ракетных войск стратегического назначения им. Петра Великого | Устройство для транспортировки и/или хранения взрыво-, радиационно и токсикологически опасного груза |
| US8044377B2 (en) * | 2006-12-18 | 2011-10-25 | Medi-Physics, Inc. | Shielded container |
| US8535604B1 (en) | 2008-04-22 | 2013-09-17 | Dean M. Baker | Multifunctional high strength metal composite materials |
| FR2952468B1 (fr) * | 2009-11-10 | 2012-01-13 | Tn Int | Emballage pour le transport et/ou entreposage de matieres radioactives comprenant des elements de protection radiologique empiles radialement |
| DE102010000974A1 (de) | 2010-01-18 | 2011-07-21 | ALD Vacuum Technologies GmbH, 63450 | Form-, strahlungs- und temperaturstabiler Körper, geeignet zum Transport und/oder zur Lagerung von radioaktiven Abfällen |
| FR2961005B1 (fr) * | 2010-06-02 | 2015-12-11 | Tn Int | Emballage pour le transport et/ou entreposage de matieres radioactives, comprenant des moyens de conduction thermique ameliores |
| US20190066858A1 (en) | 2017-08-31 | 2019-02-28 | Nac International Inc. | Containment cask for drum containing radioactive hazardous waste |
| US12059511B2 (en) | 2018-04-16 | 2024-08-13 | Martha Elizabeth Hightower Baker | Dissolvable compositions that include an integral source of electrolytes |
| US11602788B2 (en) | 2018-05-04 | 2023-03-14 | Dean Baker | Dissolvable compositions and tools including particles having a reactive shell and a non-reactive core |
Family Cites Families (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH492656A (de) * | 1966-08-09 | 1970-06-30 | Marxen Friedrich | Gegen radioaktive Strahlen, insbesondere Gamma- und Neutronenstrahlen, abschirmender Baustoff und Verfahren zu seiner Herstellung |
| FR1568883A (fr) * | 1968-02-09 | 1969-05-30 | ||
| DE1807421A1 (de) * | 1968-04-19 | 1969-11-06 | Atomic Power Construction Ltd | Biologische Abschirmung fuer einen Kernreaktor |
| DE2040348B2 (de) * | 1969-08-13 | 1976-10-21 | Ausscheidung in: 20 65 863 Transnucleaire, Societe pour les Transports de l'Industrie Nucleaire, Paris | Behaelter fuer die lagerung und den transport von radioaktiven materialien |
| FR2074726A7 (en) * | 1970-01-22 | 1971-10-08 | Robatel Slpi | Composite packaging material esp - for radio chemicals |
| FR2208165B1 (fr) * | 1972-11-28 | 1975-09-12 | Robatel Slpi | |
| DE2631769B2 (de) * | 1976-07-15 | 1979-08-02 | Steag Kernenergie Gmbh, 4300 Essen | Vorrichtung für die Endlagerung von radioaktiven Abfallstoffen verschiedener Aktivitäten |
| DE2740933C2 (de) * | 1977-09-10 | 1982-11-25 | GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen | Transport- bzw. Lagerbehälter für radioaktive Stoffe, insbesondere bestrahlte Kernreaktorbrennelemente |
| US4225467A (en) * | 1977-11-25 | 1980-09-30 | The Carborundum Company | Neutron absorbing article and method for manufacture of such article |
| DE3012256A1 (de) * | 1980-03-29 | 1981-10-15 | Transnuklear Gmbh, 6450 Hanau | Behaelter zum transport und/oder lagerung radioaktiver stoffe |
-
1980
- 1980-03-29 DE DE19803012256 patent/DE3012256A1/de not_active Withdrawn
-
1981
- 1981-02-28 EP EP81101461A patent/EP0036954B1/fr not_active Expired
- 1981-03-05 ES ES500105A patent/ES8305147A1/es not_active Expired
- 1981-03-27 US US06/248,440 patent/US4453081A/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2722214C1 (ru) * | 2019-09-13 | 2020-05-28 | Общество с ограниченной ответственностью "Керамические технологии" | Контейнер для хранения, транспортирования и захоронения радиоактивных отходов |
Also Published As
| Publication number | Publication date |
|---|---|
| EP0036954A1 (fr) | 1981-10-07 |
| DE3012256A1 (de) | 1981-10-15 |
| ES8305147A1 (es) | 1983-03-16 |
| US4453081A (en) | 1984-06-05 |
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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 |
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| AK | Designated contracting states |
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| GRAA | (expected) grant |
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| AK | Designated contracting states |
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|
| 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 |
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| 26N | No opposition filed | ||
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Ref country code: SE Effective date: 19890301 |
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| BERE | Be: lapsed |
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| GBPC | Gb: european patent ceased through non-payment of renewal fee | ||
| PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
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| REG | Reference to a national code |
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| EUG | Se: european patent has lapsed |
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