CA1175163A - Storage of irradiated fuel assemblies - Google Patents
Storage of irradiated fuel assembliesInfo
- Publication number
- CA1175163A CA1175163A CA000317031A CA317031A CA1175163A CA 1175163 A CA1175163 A CA 1175163A CA 000317031 A CA000317031 A CA 000317031A CA 317031 A CA317031 A CA 317031A CA 1175163 A CA1175163 A CA 1175163A
- Authority
- CA
- Canada
- Prior art keywords
- fuel assemblies
- gas
- burned
- radiation
- tight
- 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
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/06—Magazines for holding fuel elements or control elements
- G21C19/07—Storage racks; Storage pools
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Drying Of Solid Materials (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
Abstract
Abstract of the Disclosure Method for storing irradiated fuel assemblies before reprocessing thereof which includes depositing the irradiated fuel assemblies in a water-filled spent-fuel container and, after a period of time during which decay eat in the fuel assemblies has been reduced to an amount removable by dry cooling, transfering the fuel assemblies to a drying device and, after drying off the fuel assemblies from water of the spent-fuel container adhering there-to, depositing the dried fuel assemblies in a shielded dry storage container.
Description
The invention relates to a method of storing irradiated fuel assemblies before reprocessing thereof, and apparatus for performing the method.
It has become known heretofore to store burned up or irradiated fuel assemblies in water-filled spent-fuel containers or pits until the reprocessing thereof can be undertaken, after an adequate decay period for the decay power or heat thereof has expired. With increasing numbers oE nuclear power plants and the operating periods thereof, spent fuel assemblies accumulate to an ever increasing extent and must be stored in the aforedes-cribed manner. It is readily apparent that the storage capacity necessary therefor must be continuously expanded, which is not only accompanied by an ever increasing space requirement but pri-marily also a requirement for suitable purifying or cleaning equip-ment Eor the container or pit water, as well as cooling devices for removing the decay power or heat of the spent fuel assemblies.
It is self-evident that, in this regard, as in other aspects of reactor engineering or technology, redundant operational, measur-ing and monitoring systems must be installed which, in the course of time, calls for an exceptionally great and costly technical expenditure. Furthermore, electrical energy is consumed and weak-ly radioactive waste is produced in a by-no-means inconsiderable amount in the course of removing the heat and keeping the coolant pure and clean.
It is accordingly an object of the invention to provide a method and apparatus for storing burned-up or irradiated fuel assemblies wherein the aforedescribed expense is kept consider-ably lower than heretofore.
With the foregoing and other objects in view, thereis provided in accordance with the invention, an apparatus for storing burned-up nuclear reactor fuel assemblies comprising:
a water container for holding irradiated fuel assemblies unloaded from a nuclear reactor, and associated with the water container a packing station for encapsulating the burned-up reactor fuel assemblies removed from the water container in gas-tight capsules and a gas-tight dry storage chamber comprising a gas-tight contain-ment having an interior defined by a radiation-shielding surround-ing a support structure for the gas-tight capsules containing the burned-up reactor fuel assemblies and a coolant gas contained i~ the interior, cooling pipe means embedded in the radiation-shielding of the gas-tight containment, a cooling medium flowing through the cooling pipe means for assisting the conduction of heat from the interior of the containment through the radiation-shielding and the containment, and means for radiation-shielding and gas tightly closing an opening in the gas-tight containment for loading and unloading the capsules containing the burned-up fuel assemblies.
This means that the irradiated or burned-up fuel assem-blies need not spend the entire decay period thereof in the water-filled spent-fuel pit or container, but rather only a consider-ably shorter period i.e. about 1/10 of the period spent heretofore, and that they can then be stored in the dry storage chamber or container because the residual decay heat has by then become so little that it can be removed by radiation or convection cooling
It has become known heretofore to store burned up or irradiated fuel assemblies in water-filled spent-fuel containers or pits until the reprocessing thereof can be undertaken, after an adequate decay period for the decay power or heat thereof has expired. With increasing numbers oE nuclear power plants and the operating periods thereof, spent fuel assemblies accumulate to an ever increasing extent and must be stored in the aforedes-cribed manner. It is readily apparent that the storage capacity necessary therefor must be continuously expanded, which is not only accompanied by an ever increasing space requirement but pri-marily also a requirement for suitable purifying or cleaning equip-ment Eor the container or pit water, as well as cooling devices for removing the decay power or heat of the spent fuel assemblies.
It is self-evident that, in this regard, as in other aspects of reactor engineering or technology, redundant operational, measur-ing and monitoring systems must be installed which, in the course of time, calls for an exceptionally great and costly technical expenditure. Furthermore, electrical energy is consumed and weak-ly radioactive waste is produced in a by-no-means inconsiderable amount in the course of removing the heat and keeping the coolant pure and clean.
It is accordingly an object of the invention to provide a method and apparatus for storing burned-up or irradiated fuel assemblies wherein the aforedescribed expense is kept consider-ably lower than heretofore.
With the foregoing and other objects in view, thereis provided in accordance with the invention, an apparatus for storing burned-up nuclear reactor fuel assemblies comprising:
a water container for holding irradiated fuel assemblies unloaded from a nuclear reactor, and associated with the water container a packing station for encapsulating the burned-up reactor fuel assemblies removed from the water container in gas-tight capsules and a gas-tight dry storage chamber comprising a gas-tight contain-ment having an interior defined by a radiation-shielding surround-ing a support structure for the gas-tight capsules containing the burned-up reactor fuel assemblies and a coolant gas contained i~ the interior, cooling pipe means embedded in the radiation-shielding of the gas-tight containment, a cooling medium flowing through the cooling pipe means for assisting the conduction of heat from the interior of the containment through the radiation-shielding and the containment, and means for radiation-shielding and gas tightly closing an opening in the gas-tight containment for loading and unloading the capsules containing the burned-up fuel assemblies.
This means that the irradiated or burned-up fuel assem-blies need not spend the entire decay period thereof in the water-filled spent-fuel pit or container, but rather only a consider-ably shorter period i.e. about 1/10 of the period spent heretofore, and that they can then be stored in the dry storage chamber or container because the residual decay heat has by then become so little that it can be removed by radiation or convection cooling
-2-5~3 with gases. As a result, the storage e~pense of burned-up or irradiated fuel assemblies can be reduced considerably without compromising the reliability or safety of the storage facility.
In addition to the provision of an active component in the form of the cooling pipe means embedded in the shielding, a passive component in the Eorm of surface-enlarging elements disposed on the interior surface of the radiation-shielding may also be provided to assist in transEer of heat.
The dry storage chamber may have an access opening that is closed by a double rotating cover.
Preferably, a drying device is associated with the water container for drying the burned-up reactor fuel assemblies removed from the water container before encapsulating in gas-tight cap-sules in the pac~ing station.
The apparatus preferably includes, in combination with the dry storage container, sluice and manipulating devices for transporting ~he fuel assemblies from a water-filled spent-fuel container through the drying and packing -2a-.~.
~., ~ 7S~L63 devices to a location within the dry storage container.
Although the invention is illustrated and described herein as embodied in storage of irradiated fuel assemblies, it is nevertheless not intended to be limited to the details shown, since various modifications and structural changes may be made therein without departing from the spirit of the invention and within the scope and range of equivalents of the claims.
The construction and method of operation of the invention, however, together with additional objects and advantages thereof will be best under-stood from the following description of specific embodiments when read in connec~ion with the single figure of the drawing which is a diagrammatic view of apparatus for performing the method of storing irradiated fuel assemblies in accordance with the invention.
Referring now to the drawing, there are shown, in the figure thereof, fuel assemblies 2 stored in a water-filled spent-fuel container 4 which is provided, for this purpose, with a non-illustrated inner support structure which, due to the geometrical shape thereof and/or due to absorber materials introduced therein reliably prevents the fuel assemblies stored therein from becoming critical. The container water is provided with non-B
1~'75~3 illustrated purifying or cleaning devices as well as cooling devices. In thisway, initially present and still very great decay heat is removed and can, under certain conditions, be further used also for other technical purposes.
This liberated decay heat of the fuel assemblies decreases with increasing storage time so that, beginning with a given point of time, water cooling by the inventive method of the instant application, is no longer necessary.
At this juncture, it should also be noted that the fuel assemblies 2 provided also with so-called bearing bushings or capsules, can be deposited in the storage container or pit 4. After decay or decrease of the decay heat to a value removable by dry cooling, the fuel assemblies 2 are remotely handled, for example, individually removed from the storage container 4 with the aid of a crane installation S, ~1 or with non-illustrated manipulating equipment and inserted into a drying device 5. Due to the remaining decay heat as well as due to gas, such as air or nitrogen, for example, fed in through a line 52 and discharging ~hrough a line 53, the container water ad-hering to the fuel assemblies 2 is dried up. Then, after taking off the cover 51, the fuel assemblies 2 are removed from the drying chamber 5,and, also again remotely handled are delivered to a packing station 6 closed off from ~he outside. The fuel assemblies are inserted into canisters 3 which are gas-tightly closed by a cover 31. The interior space of the thus-closed canisters
In addition to the provision of an active component in the form of the cooling pipe means embedded in the shielding, a passive component in the Eorm of surface-enlarging elements disposed on the interior surface of the radiation-shielding may also be provided to assist in transEer of heat.
The dry storage chamber may have an access opening that is closed by a double rotating cover.
Preferably, a drying device is associated with the water container for drying the burned-up reactor fuel assemblies removed from the water container before encapsulating in gas-tight cap-sules in the pac~ing station.
The apparatus preferably includes, in combination with the dry storage container, sluice and manipulating devices for transporting ~he fuel assemblies from a water-filled spent-fuel container through the drying and packing -2a-.~.
~., ~ 7S~L63 devices to a location within the dry storage container.
Although the invention is illustrated and described herein as embodied in storage of irradiated fuel assemblies, it is nevertheless not intended to be limited to the details shown, since various modifications and structural changes may be made therein without departing from the spirit of the invention and within the scope and range of equivalents of the claims.
The construction and method of operation of the invention, however, together with additional objects and advantages thereof will be best under-stood from the following description of specific embodiments when read in connec~ion with the single figure of the drawing which is a diagrammatic view of apparatus for performing the method of storing irradiated fuel assemblies in accordance with the invention.
Referring now to the drawing, there are shown, in the figure thereof, fuel assemblies 2 stored in a water-filled spent-fuel container 4 which is provided, for this purpose, with a non-illustrated inner support structure which, due to the geometrical shape thereof and/or due to absorber materials introduced therein reliably prevents the fuel assemblies stored therein from becoming critical. The container water is provided with non-B
1~'75~3 illustrated purifying or cleaning devices as well as cooling devices. In thisway, initially present and still very great decay heat is removed and can, under certain conditions, be further used also for other technical purposes.
This liberated decay heat of the fuel assemblies decreases with increasing storage time so that, beginning with a given point of time, water cooling by the inventive method of the instant application, is no longer necessary.
At this juncture, it should also be noted that the fuel assemblies 2 provided also with so-called bearing bushings or capsules, can be deposited in the storage container or pit 4. After decay or decrease of the decay heat to a value removable by dry cooling, the fuel assemblies 2 are remotely handled, for example, individually removed from the storage container 4 with the aid of a crane installation S, ~1 or with non-illustrated manipulating equipment and inserted into a drying device 5. Due to the remaining decay heat as well as due to gas, such as air or nitrogen, for example, fed in through a line 52 and discharging ~hrough a line 53, the container water ad-hering to the fuel assemblies 2 is dried up. Then, after taking off the cover 51, the fuel assemblies 2 are removed from the drying chamber 5,and, also again remotely handled are delivered to a packing station 6 closed off from ~he outside. The fuel assemblies are inserted into canisters 3 which are gas-tightly closed by a cover 31. The interior space of the thus-closed canisters
3 is advantageously filled with an inert gas. The thus-pac~ed fuel assemblies 2 are then, again remotely handled delivered into a dry storage container 7 wherein the closed canisters 3 containing the fuel assemblies 2 are inserted into a support structure 35 which can be constructed similarly to that in the wet fuel assembly-storage pit 4. The support structure 35 thus serves as the mechanical holder or support for the fuel element canisters 3 inserted therein as well as for preventing a distribution or arrangement thereof that would become critical. When the decay heat of these inserted fuel assemblies 2 has ~1~5~L63 also become so little that no water cooling is necessary anymore, the radio-active radiation thereof is nevertheless great enough that the dry storage chamber 7 has to be surrounded by radiation shielding 71. Cooling pipes 72 are embedded in the shielding 71 and are traversed by a coolant passing through union fittings or connection pieces 78 and 7~. Natural circulatory flow produced in the interior of the dry storage chamber 7 absorbs the heat from the fuel assemblies 2 and surrenders it to the shielding 71. The inner wall surface of the shielding 71 can be provided with surface-enlarging elements such as ribs 80 or the likel for e:~ample, so that heat transfer is thereby improved or facilita~ed.
In addition, cooling gas can be introduced through a line 76 into the storage chamber 7, and discharged therefrom through a line 77. This heat carrier i.e. either the coolant flowing through the cooling coils 72 or this cooling gas, can be used again for heating up the drying apparatus 5 so that only a part thereof has to be discharged and can possibly also be used further as process heat.
Non-illustrated sluices or locks can be provided for introducing the fuel assemblies 2 into the drying storage chamber 7, or also, as shown in the figure, a double rotating plug or cover 74, 73 as is generally known from nuclear power plant technology. A blower 75 for effecting improved circula-tion of the volume of cooling gas and thereby cooling of the fuel assembly canisters 3, can additionally be provided on the plug or cover 73.
The closure for this dry storage container 7 must obviously be of gas-tight construction, and also the radiation shielding 71, as well, must be provided with at least an outer dense skin in order to prevent external contamination due to possibly damaged or faulty canisters 3.
Naturally, this dry storage container 7 and also the intermediate station for performing the method according to the invention are provided with 5 _ ~i~S~63 non-illustrated monitoring devices of conventional construction so that any distuTbances that might possibly occur can be detected in time and suitably remedied.
Of course, other possible constructions for the apparatus accord-ing to the invention are conceivable, such as~ for example, the outer dense skin and the shielding can be so disposed that the heat at the fuel assemblies carried by natural convection to the outer structure passes through the latter by heat conduction and is discharged by natural convection to the outside.
....
In addition, cooling gas can be introduced through a line 76 into the storage chamber 7, and discharged therefrom through a line 77. This heat carrier i.e. either the coolant flowing through the cooling coils 72 or this cooling gas, can be used again for heating up the drying apparatus 5 so that only a part thereof has to be discharged and can possibly also be used further as process heat.
Non-illustrated sluices or locks can be provided for introducing the fuel assemblies 2 into the drying storage chamber 7, or also, as shown in the figure, a double rotating plug or cover 74, 73 as is generally known from nuclear power plant technology. A blower 75 for effecting improved circula-tion of the volume of cooling gas and thereby cooling of the fuel assembly canisters 3, can additionally be provided on the plug or cover 73.
The closure for this dry storage container 7 must obviously be of gas-tight construction, and also the radiation shielding 71, as well, must be provided with at least an outer dense skin in order to prevent external contamination due to possibly damaged or faulty canisters 3.
Naturally, this dry storage container 7 and also the intermediate station for performing the method according to the invention are provided with 5 _ ~i~S~63 non-illustrated monitoring devices of conventional construction so that any distuTbances that might possibly occur can be detected in time and suitably remedied.
Of course, other possible constructions for the apparatus accord-ing to the invention are conceivable, such as~ for example, the outer dense skin and the shielding can be so disposed that the heat at the fuel assemblies carried by natural convection to the outer structure passes through the latter by heat conduction and is discharged by natural convection to the outside.
....
Claims (4)
PROPERTY OR PRIVILEGE IS CLAIMED ARE DEFINED AS FOLLOWS:
1. Apparatus for dry storing burned-up reactor fuel assemblies comprising a water container for holding the burned-up fuel assemblies unloaded from a nuclear reactor, and associated with the water container a packing station for encapsulating the burned-up reactor fuel assemblies removed from the water con-tainer in gas-tight capsules and a gas-tight dry storage chamber comprising a gas-tight containment having an interior defined by a radiation-shielding sur-rounding a support structure for the gas-tight capsules containing the burned-up reactor fuel assemblies and a coolant gas contained in the interior, cooling pipe means embedded in the radiation-shielding of the gas-tight containment, a cooling medium flowing through the cooling pipe means for assisting the conduc-tion of heat from the interior of the containment through the radiation-shield-ing and the containment, and means for radiation-shielding and gas tightly clos-ing an opening in the gas-tight containment for loading and unloading the cap-sules containing the burned-up fuel assemblies.
2. Apparatus according to claim 1 wherein a drying device is associated with the water container for drying the burned-up reactor fuel assemblies re-moved from the water container before encapsulating in gas-tight capsules in the packing station.
3. Apparatus according to claim 1 wherein surface enlarging elements are disposed on the interior surface of the radiation-shielding.
4. Apparatus according to claim 1, 2 or 3 wherein the means for radiation-shielding and gas-tightly closing the opening in the containment comprises a double rotating cover.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE2753034A DE2753034C2 (en) | 1977-11-28 | 1977-11-28 | Equipment for the storage of spent nuclear reactor fuel elements and methods for the operation of this equipment |
| DEP2753034.3 | 1977-11-28 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1175163A true CA1175163A (en) | 1984-09-25 |
Family
ID=6024810
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA000317031A Expired CA1175163A (en) | 1977-11-28 | 1978-11-28 | Storage of irradiated fuel assemblies |
Country Status (12)
| Country | Link |
|---|---|
| JP (1) | JPS54116599A (en) |
| AR (1) | AR218945A1 (en) |
| AT (1) | AT365841B (en) |
| BR (1) | BR7807768A (en) |
| CA (1) | CA1175163A (en) |
| CH (1) | CH636722A5 (en) |
| DE (1) | DE2753034C2 (en) |
| ES (1) | ES475479A1 (en) |
| FR (1) | FR2410339A1 (en) |
| GB (1) | GB2009484B (en) |
| IT (1) | IT1100293B (en) |
| SE (1) | SE433144B (en) |
Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2928051A1 (en) * | 1977-11-28 | 1981-01-29 | Kraftwerk Union Ag | Dry store for nuclear fuel elements - cooled by heat pipes through radiation screen exposed to natural cooling draught |
| DE2919797C2 (en) * | 1979-05-16 | 1984-02-16 | Kraftwerk Union AG, 4330 Mülheim | Storage facility for the storage of spent fuel |
| DE2929467C2 (en) * | 1979-07-20 | 1985-04-25 | Kraftwerk Union AG, 4330 Mülheim | Storage building for spent nuclear reactor fuel elements |
| EP0028442A3 (en) * | 1979-10-31 | 1981-10-21 | The English Electric Company Limited | Storage arrangements for nuclear fuel elements |
| DE3017767C2 (en) * | 1980-05-09 | 1984-11-15 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Protective container for the transport, storage and radiation shielding of fuel element containers loaded with spent reactor fuel elements |
| FR2502829B1 (en) * | 1981-03-30 | 1988-05-13 | English Electric Co Ltd | NUCLEAR FUEL STORAGE SYSTEM |
| US4800062A (en) * | 1987-02-23 | 1989-01-24 | Nuclear Packaging, Inc. | On-site concrete cask storage system for spent nuclear fuel |
| CN106782713B (en) * | 2017-01-05 | 2019-05-24 | 中国原子能科学研究院 | The cooling storage device of passive spentnuclear fuel |
Family Cites Families (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3375169A (en) * | 1966-08-23 | 1968-03-26 | Atomic Power Dev Ass Inc | Method for minimizing corrosion of reactor elements |
| CH490725A (en) * | 1967-04-21 | 1970-05-15 | Commissariat Energie Atomique | Nuclear reactor fuel reloading facility |
| DE1639396B2 (en) * | 1968-01-27 | 1972-11-23 | Siemens AG, 1000 Berlin u. 8000 München | DEVICE FOR STORING FUEL ELEMENTS IN A COATING BASIN OF A NUCLEAR REACTOR |
| DE2258741B2 (en) * | 1972-11-30 | 1975-09-04 | Siemens Ag, 1000 Berlin Und 8000 Muenchen | Nuclear reactor plant |
| DE2259669A1 (en) * | 1972-12-06 | 1974-06-12 | Licentia Gmbh | Irradiated fuel storage facility - with transversely mounted beams supporting fuel elements giving economic construction |
| US3910006A (en) * | 1973-06-07 | 1975-10-07 | Westinghouse Electric Corp | Fuel element handling arrangement and method |
| BE802637A (en) * | 1973-07-20 | 1973-11-16 | Centre Etd Energie Nucleaire | PROCESS FOR DEACTIVATION OF SODIUM AND / OR STORAGE OF IRRADIATED NUCLEAR FUEL ELEMENTS |
| IT1015376B (en) * | 1974-06-25 | 1977-05-10 | Agip Nucleare Sp | EQUIPMENT FOR THE TRANSFER OF FUEL ELEMENTS WITH HIGH RESIDUAL POWER |
-
1977
- 1977-11-28 DE DE2753034A patent/DE2753034C2/en not_active Expired
-
1978
- 1978-10-02 AT AT0708478A patent/AT365841B/en not_active IP Right Cessation
- 1978-10-23 CH CH1092678A patent/CH636722A5/en not_active IP Right Cessation
- 1978-11-17 SE SE7811884A patent/SE433144B/en not_active IP Right Cessation
- 1978-11-22 AR AR274528A patent/AR218945A1/en active
- 1978-11-22 IT IT30050/78A patent/IT1100293B/en active
- 1978-11-23 GB GB7845707A patent/GB2009484B/en not_active Expired
- 1978-11-27 BR BR7807768A patent/BR7807768A/en unknown
- 1978-11-27 FR FR7833481A patent/FR2410339A1/en active Granted
- 1978-11-28 JP JP14706878A patent/JPS54116599A/en active Pending
- 1978-11-28 CA CA000317031A patent/CA1175163A/en not_active Expired
- 1978-11-28 ES ES475479A patent/ES475479A1/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| GB2009484B (en) | 1982-05-12 |
| IT7830050A0 (en) | 1978-11-22 |
| DE2753034A1 (en) | 1979-05-31 |
| AT365841B (en) | 1982-02-25 |
| BR7807768A (en) | 1979-06-26 |
| JPS54116599A (en) | 1979-09-10 |
| AR218945A1 (en) | 1980-07-15 |
| SE433144B (en) | 1984-05-07 |
| ES475479A1 (en) | 1979-11-01 |
| CH636722A5 (en) | 1983-06-15 |
| FR2410339A1 (en) | 1979-06-22 |
| FR2410339B1 (en) | 1982-05-07 |
| GB2009484A (en) | 1979-06-13 |
| ATA708478A (en) | 1981-06-15 |
| SE7811884L (en) | 1979-05-29 |
| IT1100293B (en) | 1985-09-28 |
| DE2753034C2 (en) | 1986-10-09 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| MKEX | Expiry |