EP0028222B1 - Procede pour le transport et le stockage de matieres radioactives - Google Patents

Procede pour le transport et le stockage de matieres radioactives Download PDF

Info

Publication number
EP0028222B1
EP0028222B1 EP80900762A EP80900762A EP0028222B1 EP 0028222 B1 EP0028222 B1 EP 0028222B1 EP 80900762 A EP80900762 A EP 80900762A EP 80900762 A EP80900762 A EP 80900762A EP 0028222 B1 EP0028222 B1 EP 0028222B1
Authority
EP
European Patent Office
Prior art keywords
container
storage container
storage
concrete
arrangement
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
EP80900762A
Other languages
German (de)
English (en)
Other versions
EP0028222A1 (fr
Inventor
Pal Doroszlai
Ferruccio Ferroni
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.)
Elektrowatt Ingenieurunternehmung AG
Original Assignee
Elektrowatt Ingenieurunternehmung AG
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
Priority to AT80900762T priority Critical patent/ATE4755T1/de
Application filed by Elektrowatt Ingenieurunternehmung AG filed Critical Elektrowatt Ingenieurunternehmung AG
Publication of EP0028222A1 publication Critical patent/EP0028222A1/fr
Application granted granted Critical
Publication of EP0028222B1 publication Critical patent/EP0028222B1/fr
Expired legal-status Critical Current

Links

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
    • G21F5/14—Devices for handling containers or shipping-casks, e.g. transporting devices loading and unloading, filling of 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
    • G21F5/008—Containers for fuel elements
    • G21F5/012—Fuel element racks in 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
    • G21F7/00—Shielded cells or rooms
    • G21F7/005—Shielded passages through walls; Locks; Transferring devices between rooms

Definitions

  • the invention relates to a method for the transport and storage of radioactive materials, in which the radioactive materials are enclosed in a hermetically sealable storage container made of chemically resistant material, in which the storage container is in turn inserted into a transport container which ensures mechanical, thermal and radiation protection. in which the latter is transported to a storage location, and in which at the storage location the storage container is removed from the transport container and inserted for storage in a silo which ensures radiation protection.
  • This process is used for the final storage of radioactive materials.
  • a number of steel tubes are buried in the ground at the disposal site.
  • a transport trolley with the transport container is moved over an empty steel tube, the transport container is opened at the bottom and the storage container is lowered hydraulically into the steel tube, which is then filled with gravel and then sealed.
  • the method is not suitable for the interim storage of radioactive materials that later have to be reprocessed.
  • no specific precautions are taken to remove the material from the steel tubes.
  • the tubes would have to be pulled out of the ground using a crane, although the problem of radiation protection has not been solved.
  • a method should therefore be found which permits the relatively compact interim storage of the spent fuel assemblies without incurring high costs for monitoring and handling facilities in the storage facility and without having to use a large number of expensive transport containers.
  • the process should be designed so that the storage containers can be removed from the silo for the reprocessing of the radioactive material safely and easily.
  • the method according to the invention fulfills these requirements. It is characterized by the fact that, in order to remove the storage container from the transport container, the latter is sunk into a concrete shaft, that after lifting the transport container lid, a protective container is placed on the concrete shaft, that the protective container is opened at the bottom and the storage container is lifted into the protective container, that the latter is closed again, that the protective container is then lifted from the concrete shaft and placed on the opening of the concrete silo, and that the storage container is then lowered into the concrete silo, whereupon the protective container is removed and the concrete silo is closed by a lid.
  • the device for carrying out the method according to the invention with a transport container and a hermetically closable storage container for the radioactive materials which can be enclosed therein is characterized in that the device has a concrete shaft for receiving the transport container when the storage container is unloaded, a protective container for receiving and transferring the storage container from Concrete shaft to the storage area and a number of concrete silos to accommodate the storage containers for storage.
  • the transport container 17 shown in FIG. 1 consists of a solid steel cylinder 31 which ensures adequate shielding against gamma rays.
  • the transport container 17 is forged in one piece, so that only a single weld 33 is required between the steel cylinder 31 and the container base 32.
  • Cooling fins 34 are arranged outside the steel cylinder 31.
  • the transport container 17 is closed with a tamper-proof and tightly closing lid 19.
  • trunnions 35 are attached at various points and removable shock absorbers 16 are mounted on both ends of the container 17.
  • the transport container described is a version that can normally be loaded with 12 fuel elements. In the present case, however, the transport container is loaded with a storage container.
  • This storage container 7 has a stainless steel jacket 36 for seven pressurized water reactor fuel elements. The wall thickness of the jacket is approximately 15 mm.
  • the lid 1 of the storage container is fastened to the jacket by means of screws 2.
  • the protruding lips 3 between the cover flange 3 and the jacket flange 38 are welded together.
  • Ribs 4 are attached over the length of the storage container, which ensure the heat emission to the transport container or to the environment.
  • Steel ribs 5 are welded to the bottom 39 and to the lid 1, which have a stiffening effect and also serve to emit heat. All ribs 4, 5 also act as shock absorbers in the event of an accident.
  • the cover 1 is not yet screwed onto the jacket 36, so that the screw bolts 2 do not hinder the welding.
  • the container 7 is first evacuated through the valve 6. The external pressure presses the cover 1 onto the jacket flange 38. A seal 9 helps to maintain the vacuum.
  • the container is pressed out with helium at a pressure of approx. 7 atm and the tightness of the container is checked with helium detectors 40 (FIG. 10).
  • the overpressure in the container filled with helium is left and an end cover 8 is welded on via the filling valve 6.
  • the pressurized storage container 7 is thus hermetically sealed.
  • the operations described are carried out in the reverse order.
  • the closure cover 8 is removed after the weld seam has been ground off, the helium pressure is released from the container and the vacuum is established. The screws 2 are then removed and the lip weld 3 is ground off.
  • the fuel elements are surrounded by boron steel boxes 11 in the storage container.
  • the storage container is normally always dry, but the distance between the boxes 11 and their boron content ensure the sufficient subcriticality even when filling with water.
  • the space between the boxes 11 is filled with disc-shaped cast aluminum bodies 10. These cast aluminum bodies give the configuration great stability in the event of an accident, they slow down the fast neutrons somewhat, absorb some of the gamma rays and dissipate the decay heat of the fuel elements to the storage container wall.
  • the loading and closing of the storage container must be carried out in protected and controlled rooms, ideally in the immediate vicinity of the reactor.
  • the necessary remote-controlled devices must also be available here.
  • the dimensions of the storage container for seven pressurized water reactor fuel elements are selected so that they fit straight into the usual transport container, which normally has space for 12 fuel elements.
  • the storage container is thus loaded into the transport container and transported to the interim storage facility. During transport, all safety-related regulations and requirements such as mechanical strength, thermal properties and radiation protection conditions are met by the transport container.
  • the actual interim storage consists of a Concrete slab 41, in which cylindrical recesses or silos 12 for the storage containers 7 are embedded (FIGS. 6, 7).
  • the inner walls of the silos 12 are expediently covered with a steel lining.
  • the storage containers are cooled by free convection of the ambient air.
  • the supply of fresh air takes place by channels 13 below the laser gerpos i tion.
  • the heated air rises through baffles 14, which prevent the gamma rays from escaping, through the concrete cover 15 to the outside.
  • FIGS. 3-6 The various stages for unloading the storage container from the transport container to placing it in the interim storage facility are illustrated in FIGS. 3-6.
  • the transport container 17 is lowered into a concrete shaft 18 (FIG. 4). Now the lid 19 is lifted off and removed from the silo so that the protective container 20 can be placed on the transport container 17.
  • a lifting plate 22, which is arranged in the interior of the protective container, is lowered and is pivoted with the lifting tabs 23 of the storage container 7.
  • the storage container 7 is pulled up into the protective container 20 and the closing slide 21 is pushed in again.
  • the protective container 20 provides sufficient protection against the radiation from the storage container 7 so that it can be lifted out of the concrete shaft 18.
  • the protective container is then transported to the storage location. Once there, it is placed on an intermediate ring 24 via the opening of the silo 12.
  • the slide valve 21 is pulled out again and the storage container 7 is lowered into the silo 12 (FIG. 6).
  • the lifting plate 22 is decoupled by twisting and the protective container 20 is removed together with the intermediate ring 24. The latter serves to guide the storage container into the silo when it sinks.
  • the position of the storage container 7 in the silo 12 is secured by longitudinal ribs 25a of the lining 25, which give off the heat generated in the concrete to the air flow.
  • the remaining heat generated in the concrete is given off to the environment by additional freely circulating cooling air in the channels 28.
  • the cooling system prevents an inadmissible temperature rise and the associated dehydration of the concrete.
  • Environmental pollution from the interim storage facility is possible in three different ways: through direct radiation, through leaks in the fuel casing of the storage containers and through activation of the cooling air by the fast neutrons.
  • the thick concrete wall with added boron forms a sufficient barrier against direct radiation (primary gamma radiation, neutron radiation and secondary gamma radiation after neutron capture).
  • the tightness of the storage containers is checked by the monitoring system using helium detectors.
  • the activation of the air can be kept largely harmless if the cold supply air is free of dust. This means that no dust particles can be deposited on the storage container, activated there and then carried away by the cooling air.
  • the interim storage facility including the crane systems, can be covered with an ordinary hall, which should not hinder the free escape of warm air, but should ensure the usual protection against atmospheric conditions (cross wind with dust, rain, snow).
  • the massive concrete structure of the interim storage facility offers sufficient protection against all mechanical influences (earthquake, plane crash, etc.).
  • a grid 26 of plastic pipes is laid over the concrete cover 15 of the concrete silo 12. One branch each from the pipes in both directions penetrates into the air outlet openings of the concrete cover 15 without, however, impairing the free air outlet.
  • a central suction fan 27 ensures constant negative pressure in the tubes.
  • a scanning control fryer 43 periodically opens one of the valves 44 against the suction pump 27 of the helium detector 40 one after the other.
  • a defective storage container can thus be found within a scanning cycle. Such a container must be removed from the silo and transported back to the loading or unloading location. Leakage from a storage container does not mean that there is no activity, since undamaged fuel elements are stored in the interim storage facility. The helium filling of the storage containers prevents any chemical damage to the fuel elements during the storage period.
  • the fuel is thus protected by a double mechanical barrier.
  • the second purely mechanical barrier can easily be expanded to a further barrier against mass transfer.
  • the air channels in the cover 15 are omitted.
  • the cooling air flow of the storage container, together with the cooling air of the concrete from the channels 28, circulates in a closed circuit.
  • the recooling takes place in additional vertical shafts 29 with vertical heat pipes 30 with heat exchangers 45 arranged at the top.
  • the escape of the circulating air into the workshop located above the warehouse is avoided by the suction blowers 27 of the leakage monitoring system which generate a vacuum.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Packages (AREA)
  • Input Circuits Of Receivers And Coupling Of Receivers And Audio Equipment (AREA)

Claims (16)

1. Procédé pour le transport et le stockage de matières radio-actives, dans lequel les matières radio-actives sont enfermées dans un conteneur de stockage qui, obturable hermétiquement et fabriqué en une matière chimiquement inaltérable, est à son tour placé dans un conteneur de transport garantissant une protection mécanique, thermique et contre les rayonnements, procédé dans lequel ledit conteneur de transport est transporté jusqu'à une zone de stockage et, dans cette zone de stockage, le conteneur de stockage est enlevé du conteneur de transport et est déposé, en vue de son stockage, dans un silo garantissant une protection contre les rayonnements, procédé caractérisé par le fait que, pour retirer le conteneur de stockage du conteneur de transport, ce dernier est abaissé dans un puits en béton; par le fait, après que le couvercle du conteneur de transport a été soulevé, un conteneur de protection est placé sur le puits en béton; par le fait que le fond du conteneur de protection est ouvert et le conteneur de stockage est inséré de bas en haut dans ce conteneur de protection; par le fait que ce dernier est de nouveau fermé; par le fait que le conteneur de protection est ensuite soulevé à l'écart du puits en béton et est placé sur l'ouverture du silo en béton; et par le fait que le conteneur de stockage est ensuite descendu dans le silo en béton, après quoi le conteneur de protection est enlevé et le silo en béton est obturé par un couvercle.
2. Procédé selon la revendication 1, caractérisé par le fait que, après que les matières radio-actives ont été placées dans le conteneur de stockage, un couvercle est placé sur ce conteneur et ce dernier est mis sous vide par l'intermédiaire d'une valve; par le fait que deux lèvres périphériques situées entre le couvercle et l'ouverture du conteneur sont ensuite solidarisées par soudage; par le fait que le couvercle est ensuite vissé en plus sur le conteneur; et par le fait qu'un gaz protecteur soumis à une surpression est ensuite injecté dans ce dernier.
3. Procédé selon la revendication 1, caractérisé par le fait que le conteneur de stockage est refroidi dans le silo en béton par une circulation convective naturelle de l'air.
4. Procédé selon la revendication 1, caractérisé par le fait que, pour refroidir le conteneur de stockage, de l'air de refroidissement est mis en circuit et refroidi par un tube de chaleur qui évacue la chaleur vers l'extérieur.
5. Procédé selon les revendications 2, 3 et 4, caractérisé par le fait que l'étanchéité du conteneur de stockage est contrôlée par une surveillance de la présence du gaz protecteur dans l'air de refroidissement.
6. Dispositif pour la mise en oeuvre du procédé selon la revendication 1, comportant un conteneur de transport (17) et un conteneur de stockage (7) des matières radio-actives, qui peut être enfermé dans ledit conteneur de transport et peut être obturé hermétiquement, dispositif caractérisé par le fait qu'il comprend un puits en béton (18) pour recevoir le conteneur de transport ( 17) lors du déchargement du conteneur de stockage (7), un conteneur de protection (20) pour recevoir et transférer le conteneur de stockage (7) du puits en béton (18) à la zone de stockage (41), ainsi qu'un certain nombre de silos en béton (12) pour recevoir les conteneurs de stockage (7) en vue du stockage.
7. Dispositif selon la revendication 6, caractérisé par le fait que le conteneur de transport (17) consistant en un cylindre massif en acier (31) et forgé d'un seul tenant est doté latéralement d'ailettes de refroidissement (34) et présente à ses deux extrémités des amortisseurs de chocs (16) amovibles.
8. Dispositif selon la revendication 6, caractérisé par le fait que le conteneur de stockage (7) présentant une enveloppe (36) en acier inoxydable est obturé hermétiquement par un couvercle (1); par le fait qu'une lèvre périphérique (3) est respectivement placée sur le couvercle (1) et sur le rebord (38) de l'enveloppe; et par le fait que ces lèvres (3) sont solidarisées par soudage.
9. Dispositif selon la revendication 8, caractérisé par le fait que le conteneur de stockage est doté de nervures (4 et 5) à ses deux extrémités ainsi que sur son périmètre.
10. Dispositif selon la revendication 8, caractérisé par le fait que des caissons (11) en acier au bore sont disposés dans l'espace interne du conteneur de stockage en vue de recevoir les matières radio-actives.
11. Dispositif selon la revendication 10, caractérisé par le fait que l'espace entre les caissons (11) en acier au bore est comblé par des corps (10) en fonte de métal léger.
12. Dispositif selon la revendication 8, caractérisé par le fait que le couvercle ( 1 ) est en outre solidarisé par vissage avec l'enveloppe d'acier (36); et par le fait que le conteneur de stockage (7) est empli d'un gaz protecteur soumis à une surpression.
13. Dispositif selon les revendications 6 et 9, caractérisé par le fait que le silo en béton (12) est muni de nervures internes (25) qui s'engagent entre les nervures (4) du conteneur de stockage (7).
14. Dispositif selon la revendication 13, caractérisé par le fait que le conteneur de stockage (7) est refroidi dans le silo en béton (12) par de l'air de refroidissement.
15. Dispositif selon les revendications 6 et 14, caractérisé par le fait qu'un réseau (26) de tubes entrelacés est placé au-dessus du silo en béton (12) pour guider l'air de refroidissement; par le fait que le réseau de tubes est en communication avec un détecteur (40) de gaz protecteurs; et par le fait que, au moyen d'un appareil (43) de contrôle par détection et par l'intermédiaire de valves (44) pouvant être actionnées par ce dernier, l'air de refroidissement de n'importe lequel des silos en béton (12) peut être sélectivement distribué au détecteur (40) de gaz protecteurs.
EP80900762A 1979-05-07 1980-11-17 Procede pour le transport et le stockage de matieres radioactives Expired EP0028222B1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
AT80900762T ATE4755T1 (de) 1979-05-07 1980-05-06 Verfahren zum transport und zur lagerung von radioaktiven materialien.

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CH4281/79 1979-05-07
CH428179A CH637499A5 (de) 1979-05-07 1979-05-07 Verfahren zum transport und zur lagerung von radioaktiven materialien.

Publications (2)

Publication Number Publication Date
EP0028222A1 EP0028222A1 (fr) 1981-05-13
EP0028222B1 true EP0028222B1 (fr) 1983-09-21

Family

ID=4273185

Family Applications (1)

Application Number Title Priority Date Filing Date
EP80900762A Expired EP0028222B1 (fr) 1979-05-07 1980-11-17 Procede pour le transport et le stockage de matieres radioactives

Country Status (10)

Country Link
EP (1) EP0028222B1 (fr)
JP (1) JPS56500584A (fr)
AT (1) ATE4755T1 (fr)
BR (1) BR8008674A (fr)
CH (1) CH637499A5 (fr)
DD (1) DD151527A5 (fr)
DE (1) DE3064891D1 (fr)
FI (1) FI801374A (fr)
HU (1) HU182080B (fr)
WO (1) WO1980002469A1 (fr)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE8018595U1 (de) * 1980-07-11 1980-11-27 Transnuklear Gmbh, 6450 Hanau Verbindungselement zur befestigung der innenauskleidung in einem behaeltergrundkoerper zum transport und/oder zur lagerung von radioaktivem material
US4711758A (en) * 1984-12-24 1987-12-08 Westinghouse Electric Corp. Spent fuel storage cask having basket with grid assemblies
ES8705990A1 (es) * 1984-12-24 1987-05-16 Westinghouse Electric Corp Un barril para almacenamiento de larga duracion de combus- tible nuclear gastado
US20010011711A1 (en) 1996-05-03 2001-08-09 Graham Nicholson Container for nuclear fuel transportation
GB9609304D0 (en) 1996-05-03 1996-07-10 British Nuclear Fuels Plc Improvements in and relating to fuel transportation
DE10228387B4 (de) * 2002-06-25 2014-10-16 Polygro Trading Ag Behältersystem zum Transport und zur Lagerung hochradioaktiver Materialien

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3997078A (en) * 1974-12-13 1976-12-14 Programmed & Remote Systems Corporation Sealing cover for containers for hazardous materials
GB1496846A (en) * 1975-12-01 1978-01-05 Atomic Energy Authority Uk Transport containers for radioactive material
US4040480A (en) * 1976-04-15 1977-08-09 Atlantic Richfield Company Storage of radioactive material
US4209420A (en) * 1976-12-21 1980-06-24 Asea Aktiebolag Method of containing spent nuclear fuel or high-level nuclear fuel waste
US4115700A (en) * 1977-04-04 1978-09-19 Combustion Engineering, Inc. High density fuel storage racks
DE7737499U1 (de) * 1977-12-09 1978-05-24 Steag Kernenergie Gmbh, 4300 Essen Abschirmtransport- und/oder abschirmlagerbehaelter fuer radioaktive abfaelle
DE2821780A1 (de) * 1978-05-18 1979-11-22 Lovincic Miroslav Transport- und lagereinrichtung fuer radioaktive stoffe

Also Published As

Publication number Publication date
ATE4755T1 (de) 1983-10-15
JPS56500584A (fr) 1981-04-30
WO1980002469A1 (fr) 1980-11-13
DD151527A5 (de) 1981-10-21
EP0028222A1 (fr) 1981-05-13
BR8008674A (pt) 1981-04-14
CH637499A5 (de) 1983-07-29
FI801374A (fi) 1980-11-08
HU182080B (en) 1983-12-28
DE3064891D1 (en) 1983-10-27

Similar Documents

Publication Publication Date Title
US5920602A (en) Underground storage facility, and associated method of storing waste
US4055508A (en) Cask handling method and apparatus
DE3301735A1 (de) Uebergangslager fuer hochradioaktiven abfall
DE2915376C2 (de) Behälterkombination für den Transport und die Lagerung bestrahlter Brennelemente aus Kernreaktoren
DE2821780A1 (de) Transport- und lagereinrichtung fuer radioaktive stoffe
US10020084B2 (en) System and method for processing spent nuclear fuel
DE2220491A1 (de) Kernkraftwerk mit einer sicherheitshuelle
DD153265A5 (de) Verfahren und vorrichtung zum transport und zur lagerung radioaktiver substanzen
DE2730729A1 (de) Vorrichtung zum lagern bestrahlter bzw. abgebrannter brennelemente aus hochtemperatur-kernreaktoren
DE2740185A1 (de) Strahlenschutzschild fuer kernreaktoren
DE2929467C2 (de) Lagergebäude für abgebrannte Kernreaktorbrennelemente
DE2418518A1 (de) Speichervorrichtung fuer radioaktiven abfall
EP0028222B1 (fr) Procede pour le transport et le stockage de matieres radioactives
CH628176A5 (en) Method and device for storing irradiated or spent fuel elements from pressurised water and boiling water nuclear reactors
EP0741904B1 (fr) Panier de stockage et de transport d'elements combustibles
US4876593A (en) Temporary hot cell and related method for handling high radiation level sources
EP0377176A2 (fr) Enveloppe d'absorption pour une source radioactive, notamment un réacteur nucléaire
DE2753034A1 (de) Aufbewahrung bestrahlter brennelemente
DE3244727A1 (de) Verfahren und behaeltersystem zum ueberfuehren bzw. transportieren von brennelementen aus einem kernkraftwerk zu einer lagerstaette
DE1514702B2 (de) Kernreaktoranlage mit Leichtwasserkühlung und einem Brennelementbecken innerhalb eines druckfesten Reaktorgebäudes
DE2911185A1 (de) Verfahren sowie behaelter zum lagern und/oder zum transportieren von radioaktiven brennelementen sowie schuettgut zur verwendung bei dem verfahren
Moyer et al. Baseline descriptions for LWR spent fuel storage, handling, and transportation
CA2016923A1 (fr) Construction servant au stockage des matieres radioactives
DE3034821A1 (de) Zwischenlager fuer radioaktives material
Forrester et al. Interim Storage of RH-TRU 72B Canisters at the DOE Oak Ridge Reservation

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: 19801212

AK Designated contracting states

Designated state(s): AT CH DE FR GB SE

GRAA (expected) grant

Free format text: ORIGINAL CODE: 0009210

AK Designated contracting states

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

REF Corresponds to:

Ref document number: 4755

Country of ref document: AT

Date of ref document: 19831015

Kind code of ref document: T

REF Corresponds to:

Ref document number: 3064891

Country of ref document: DE

Date of ref document: 19831027

ET Fr: translation filed
PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: DE

Payment date: 19840421

Year of fee payment: 5

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: FR

Payment date: 19840425

Year of fee payment: 5

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: CH

Payment date: 19840428

Year of fee payment: 5

PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: SE

Payment date: 19840630

Year of fee payment: 5

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
PGFP Annual fee paid to national office [announced via postgrant information from national office to epo]

Ref country code: AT

Payment date: 19850405

Year of fee payment: 6

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

Ref country code: AT

Effective date: 19860506

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

Ref country code: SE

Effective date: 19860507

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

Ref country code: LI

Effective date: 19860531

Ref country code: CH

Effective date: 19860531

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]

Ref country code: FR

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

Effective date: 19870130

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: 19870203

REG Reference to a national code

Ref country code: FR

Ref legal event code: ST

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

Ref country code: GB

Effective date: 19881118

EUG Se: european patent has lapsed

Ref document number: 80900762.8

Effective date: 19870225