EP1512155B1 - Method and device for disposing of a fuel element case of a boiling water reactor - Google Patents
Method and device for disposing of a fuel element case of a boiling water reactor Download PDFInfo
- Publication number
- EP1512155B1 EP1512155B1 EP03759894A EP03759894A EP1512155B1 EP 1512155 B1 EP1512155 B1 EP 1512155B1 EP 03759894 A EP03759894 A EP 03759894A EP 03759894 A EP03759894 A EP 03759894A EP 1512155 B1 EP1512155 B1 EP 1512155B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- fuel assembly
- assembly box
- carrier structure
- stabilized
- fuel
- 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 - Lifetime
Links
- 239000000446 fuel Substances 0.000 title claims description 48
- 238000000034 method Methods 0.000 title claims description 19
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 8
- 238000009835 boiling Methods 0.000 title description 5
- 238000005192 partition Methods 0.000 claims description 7
- 239000008358 core component Substances 0.000 claims description 3
- 230000001143 conditioned effect Effects 0.000 description 3
- 125000006850 spacer group Chemical group 0.000 description 3
- 239000000306 component Substances 0.000 description 2
- 230000003750 conditioning effect Effects 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 230000003319 supportive effect Effects 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
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
Definitions
- the invention relates to a method for disposing of a fuel box.
- the invention relates to a method and apparatus for disposing of radioactively contaminated parts of a boiling water reactor plant.
- the wall 2 of such a fuel element box 4 encloses a substantially rectangular cavity 6.
- the fuel box 4 is open at its ends and is only provided on a front side at opposite corners with support struts 8a, which for fixing the fuel channel 4 on serve a fuel element head, not shown in the figure.
- the fuel channel 4 is provided in its lower region with further elements, in the example nubs 8b and outer plates 8c, which are specific to the type of box shown by way of example. In the conditioning of such a fuel element box this is usually pressed and then cut into small pieces. However, such a procedure is expensive.
- the invention is based on the object to provide a method for disposing of a fuel assembly of a boiling water reactor system, which is simplified compared to the procedure mentioned in the prior art.
- the invention is based on the object to provide a method for disposing of radioactively contaminated parts of a boiling water reactor system and an apparatus for performing this method.
- the first object is achieved according to the invention with a method having the features of claim 1.
- the fuel assembly is stabilized with a preassembled support structure by inserting the support structure into the fuel assembly.
- the fuel channel box is closed on one of its end faces by means of a base plate arranged on the support structure and serving as a base.
- the fuel assembly is not destroyed but provided with one or more supportive components that give it a higher strength or stability.
- a prepared in this way for the disposal or conditioned fuel assembly can also also as a transport container for other parts to be disposed of and correspondingly conditioned parts, in particular for core components or for small-volume so-called core scrap to be used.
- the fuel assembly is provided with a carrying handle. Thereby, it can be handled in the same way with the same facilities as they are provided for the handling of the fuel assembly.
- the object is achieved according to the invention with the features of claim 3. Since the stabilized fuel assembly is used as a transport container for more radioactively contaminated parts, its particularly cost-effective disposal is possible together with the core scrap.
- the leaves are separated from a control element to be disposed and introduced into the stabilized fuel assembly. Since the longitudinal and transverse expansions of the leaves of a control largely correspond to those of a fuel box these can be accommodated in a fuel box extremely space-saving, which can accommodate the leaves of three controls in this way.
- the support structure divides the fuel assembly with an internal partition in at least two sub-areas, which is supported during insertion of the leaves in one of the sub-areas. As a result, the filling of the fuel channel is facilitated.
- the support structure 10 comprises a base plate 12 which carries a partition plate 14 extending perpendicularly to the flat side of the base plate and in particular is welded thereto.
- the partition plate 14 has a longitudinal extent which is greater than the longitudinal extent of the fuel channel 4 and is provided at its side facing away from the base plate 12 free end with a recess 16 so that a carrying handle 18 is formed.
- a spacer plate 20 is fixed on this, which passes through the provided in this area with a slot 22 partition plate 14.
- FIGS. 3a, b For this purpose, this is introduced from the bottom side into the empty fuel element box 4 until the base plate 12 closes the empty fuel element box 4 and forms a bottom. The carrying handle 18 then protrudes beyond the fuel channel 4. It can also be seen in the figure that the fuel element box 4 is subdivided by the separating plate 14 into two subregions 42, 44.
- FIGS. 4a, b are in the stabilized with the support structure 10 fuel assembly 40 control rod blades 24 inserted, which have been separated in a previous step from to be disposed of tax bars and of which in FIG. 4b a halved by the previous decomposition bracket 26 is shown a carrying handle.
- the spacer plate 20 serves to support the control rod blades 24 so that the space used to hold the control blade blades 24 is free from interfering internals located at the bottom of the fuel box 4. At the same time four sub-chambers 46 are formed below the control blades 24, which can be used to hold small-volume core scrap.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Processing Of Solid Wastes (AREA)
Description
Die Erfindung bezieht sich auf ein Verfahren zum Entsorgen eines Brennelementkastens. Außerdem bezieht sich die Erfindung auf ein Verfahren und eine Vorrichtung zum Entsorgen von radioaktiv kontaminierten Teilen einer Siedewasserreaktoranlage.The invention relates to a method for disposing of a fuel box. In addition, the invention relates to a method and apparatus for disposing of radioactively contaminated parts of a boiling water reactor plant.
Einbauteile einer nuklearen Reaktoranlage die mit dem Kühlwasser des Primärkreislaufes in Berührung kommen, sind erheblich radioaktiv kontaminiert und, falls sie im Reaktorkern eingebaut waren, zusätzlich aktiviert. Durch betriebsbedingten Verschleiß, dem insbesondere Kerneinbauteile im hohen Maße unterliegen, ist es erforderlich, diese Teile auszubauen und durch neue zu ersetzen. Die ausgebauten Teile müssen unter Einhaltung strenger Vorsichtsmaßnamen konditioniert werden, um sie für die Entsorgung handhabbar zu machen. Ein solches Verschleißteil ist in einem Siedewasserreaktor beispielsweise ein vollständiges Brennelement, zu dessen Vorbereitung für die Endlagerung ein Verfahren in der
Der Erfindung liegt nun die Aufgabe zu Grunde, ein Verfahren zum Entsorgen eines Brennelementkastens einer Siedewasserreaktoranlage anzugeben, das gegenüber der im Stand der Technik genannten Vorgehensweise vereinfacht ist. Außerdem liegt der Erfindung die Aufgabe zu Grunde, ein Verfahren zum Entsorgen von radioaktiv kontaminierten Teilen einer Siedewasserreaktoranlage sowie eine Vorrichtung zum Durchführen dieses Verfahrens anzugeben.The invention is based on the object to provide a method for disposing of a fuel assembly of a boiling water reactor system, which is simplified compared to the procedure mentioned in the prior art. In addition, the invention is based on the object to provide a method for disposing of radioactively contaminated parts of a boiling water reactor system and an apparatus for performing this method.
Die erstgenannte Aufgabe wird gemäß der Erfindung gelöst mit einem Verfahren mit den Merkmalen des Patentanspruches 1. Gemäß diesen Merkmalen wird der Brennelementkasten mit einer vormontierten Tragstruktur stabilisiert, indem die Tragstruktur in den Brennelementkasten eingeführt wird. Ferner wird der Brennelementkasten auf einer seiner Stirnseiten mit Hilfe einer an der Tragstruktur angeordneten und als Boden dienenden Basisplatte verschlossen. Mit anderen Worten: Der Brennelementkasten wird nicht zerstört sondern mit einem oder mehreren ihn stützenden Bauteilen versehen, die ihm eine höhere Festigkeit oder Stabilität verleihen. Damit ist ein aufwendiges Verpressen und Zerlegen des Brennelementkastens nicht mehr erforderlich und seine Entsorgung vereinfacht. Ein auf diese Weise für die Entsorgung vorbereiteter oder konditionierter Brennelementkasten kann außerdem zugleich als Transportbehälter für weitere zu entsorgende und entsprechend konditionierte Teile, insbesondere für Kerneinbauteile oder für kleinvolumigen sogenannten Core-Schrott verwendet werden.The first object is achieved according to the invention with a method having the features of claim 1. According to these features, the fuel assembly is stabilized with a preassembled support structure by inserting the support structure into the fuel assembly. Furthermore, the fuel channel box is closed on one of its end faces by means of a base plate arranged on the support structure and serving as a base. In other words, the fuel assembly is not destroyed but provided with one or more supportive components that give it a higher strength or stability. For a costly pressing and disassembly of the fuel assembly is no longer required and its disposal simplified. A prepared in this way for the disposal or conditioned fuel assembly can also also as a transport container for other parts to be disposed of and correspondingly conditioned parts, in particular for core components or for small-volume so-called core scrap to be used.
In einer vorteilhaften Ausgestaltung des Verfahrens wird der Brennelementkasten mit einem Tragegriff versehen. Dadurch kann er in gleicher Weise mit denselben Einrichtungen gehandhabt werden, wie sie für die Handhabung des Brennelementes vorgesehen sind.In an advantageous embodiment of the method, the fuel assembly is provided with a carrying handle. Thereby, it can be handled in the same way with the same facilities as they are provided for the handling of the fuel assembly.
Bezüglich des zweitgenannten Verfahrens wird die Aufgabe gemäß der Erfindung gelöst mit den Merkmalen des Patentanspruches 3. Da der stabilisierte Brennelementkasten als Transportbehälter für weitere radioaktiv kontaminierte Teile verwendet wird, ist dessen besonders kostengünstige Entsorgung gemeinsam mit dem Core-Schrott möglich.With respect to the second-mentioned method, the object is achieved according to the invention with the features of claim 3. Since the stabilized fuel assembly is used as a transport container for more radioactively contaminated parts, its particularly cost-effective disposal is possible together with the core scrap.
In einer vorteilhaften Ausgestaltung des Verfahrens werden von einem zu entsorgenden Steuerelement die Blätter abgetrennt und in den stabilisierten Brennelementkasten eingeführt. Da die Längs- und Querausdehnungen der Blätter eines Steuerelementes denen eines Brennelementkastens weitgehend entsprechen können diese äußerst platzsparend in einem Brennelementkasten untergebracht werden, der auf diese Weise die Blätter von drei Steuerelementen aufnehmen kann.In an advantageous embodiment of the method, the leaves are separated from a control element to be disposed and introduced into the stabilized fuel assembly. Since the longitudinal and transverse expansions of the leaves of a control largely correspond to those of a fuel box these can be accommodated in a fuel box extremely space-saving, which can accommodate the leaves of three controls in this way.
Insbesondere unterteilt die Tragstruktur den Brennelementkasten mit einer innenliegenden Trennwand in zumindest zwei Teilbereiche, die beim Einführen der Blätter in einen der Teilbereiche gestützt wird. Dadurch wird das Befüllen des Brennelementkastens erleichtert.In particular, the support structure divides the fuel assembly with an internal partition in at least two sub-areas, which is supported during insertion of the leaves in one of the sub-areas. As a result, the filling of the fuel channel is facilitated.
Hinsichtlich der Vorrichtung wird die genannte Aufgabe gemäß der Erfindung gelöst mit den Merkmalen des Patentanspruches 6. Vorteile der erfindungsgemäßen Vorrichtung sowie Vorteile der dem Patentanspruch 6 jeweils untergeordneten Patentansprüche ergeben sich sinngemäß aus den diesen Patentansprüchen jeweils entsprechenden Verfahrensansprüchen.With regard to the device, said object is achieved according to the invention with the features of claim 6. Advantages of the device according to the invention and advantages of the claim 6 respectively subordinate claims will become apparent mutatis mutandis from the claims corresponding to each corresponding method claims.
Zur weiteren Erläuterung der Erfindung wird auf das Ausführungsbeispiel der Zeichnung verwiesen. Es zeigen:
-
Fig. 1a und b eine Draufsicht auf die Bodenseite bzw. auf eine Längsseite eines Brennelementkastens, -
Fig. 2a und b eine Draufsicht auf die Bodenseite bzw. auf die Längsseite einer erfindungsgemäßen Tragstruktur, -
Fig. 3a und b eine Draufsicht auf die Stirnseite bzw. auf eine Längsseite des mit der Tragstruktur stabilisierten Brennelementkastens, -
Fig. 4a und b eine Draufsicht auf die Stirnseite bzw. auf eine Längsseite des mit den Blättern von Steuerstäben gefüllten Brennelementkasten.
-
Fig. 1a and b a plan view of the bottom side or on a longitudinal side of a fuel assembly, -
Fig. 2a and b a plan view of the bottom side or on the longitudinal side of a support structure according to the invention, -
Fig. 3a and b a plan view of the front side or on a longitudinal side of the stabilized with the support structure fuel box, -
Fig. 4a and b a plan view of the front side or on a longitudinal side of the filled with the leaves of control rods fuel bundle box.
Gemäß
Gemäß
Die Distanzplatte 20 dient zum Stützen der Steuerstabblätter 24, so dass der für die Aufnahme der Steuerstabblätter 24 genutzte Raum frei von störenden, im unteren Bereich des Brennelementkastens 4 befindlichen Einbauten ist. Zugleich werden unterhalb der Steuerstabblätter 24 vier Teilkammern 46 gebildet, die zur Aufnahme von kleinvolumigen Core-Schrott verwendet werden können.The
- 22
- Wandwall
- 44
- BrennelementkastenFuel channel
- 66
- Hohlraumcavity
- 8a8a
- Stützstrebensupport struts
- 8b8b
- Noppeburl
- 8c8c
- Platteplate
- 1010
- Tragstruktursupporting structure
- 1212
- Basisplattebaseplate
- 1414
- Trennplatteseparating plate
- 1616
- Ausnehmungrecess
- 1818
- Tragegriffhandle
- 2020
- Distanzplattespacer plate
- 2222
- Schlitzslot
- 2424
- SteuerstabblätterControl rod blades
- 2626
- Bügelhanger
- 4040
- BrennelementkastenFuel channel
- 42,4442.44
- Teilbereichesubregions
- 4646
- Teilkammernsubchambers
Claims (8)
- Method for the disposal of a fuel assembly box (4) of a boiling-water reactor system, in which the fuel assembly box (4) is stabilized with a prefabricated carrier structure (10), by the carrier structure (10) being introduced into the fuel assembly box (4) and in which a face side of the fuel assembly box (4) is closed with the aid of a base plate (12) arranged at the carrier structure (10) and serving as a base.
- Method according to Claim 1, in which the carrier structure (10) is provided with a carrier handle (18).
- Method for the disposal of radioactively contaminated parts of a boiling-water reactor system, in particular of integrated core parts, in which a fuel assembly box (40) stabilized according to any one of the preceding claims is used as a transport container.
- Method according to Claim 3, in which the control rod blades (24) of a control rod which is to be disposed of are separated and conveyed into the stabilized fuel assembly box (40).
- Method according to Claim 4, in which the carrier structure subdivides the stabilized fuel assembly box (40) with an interior partition wall (14) into at least two part areas (42, 44), which are supported on the introduction of the blades into one of the part areas (42, 44).
- Device for the disposal of radioactively contaminated parts of a boiling-water reactor system, in particular of integrated core components, with a fuel assembly box (40), which is stabilized with a prefabricated carrier structure (10) introduced into the fuel assembly box (40) and serves as a transport container, wherein the carrier structure (10) comprises a base plate (12) which closes the fuel assembly box (4) on one side.
- Device according to Claim 6, in which the carrier structure (10) is provided with a carrier handle (18).
- Device according to Claim 6 or 7, in which at least one partition plate (14) is arranged on the base plate (12) of the carrier structure (10) such as to be perpendicular to it, which subdivides the interior of the stabilized fuel assembly box (40) into at least two part areas (42, 44).
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE10226245 | 2002-06-13 | ||
DE10226245A DE10226245A1 (en) | 2002-06-13 | 2002-06-13 | Method and device for disposing of a fuel assembly. Disposing of a boiling water reactor system |
PCT/EP2003/005339 WO2003107356A1 (en) | 2002-06-13 | 2003-05-22 | Method and device for disposing of a fuel element case of a boiling water reactor |
Publications (2)
Publication Number | Publication Date |
---|---|
EP1512155A1 EP1512155A1 (en) | 2005-03-09 |
EP1512155B1 true EP1512155B1 (en) | 2009-04-01 |
Family
ID=29719014
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP03759894A Expired - Lifetime EP1512155B1 (en) | 2002-06-13 | 2003-05-22 | Method and device for disposing of a fuel element case of a boiling water reactor |
Country Status (6)
Country | Link |
---|---|
EP (1) | EP1512155B1 (en) |
JP (1) | JP2005534003A (en) |
DE (2) | DE10226245A1 (en) |
ES (1) | ES2322648T3 (en) |
TW (1) | TWI220992B (en) |
WO (1) | WO2003107356A1 (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP5781265B2 (en) * | 2009-07-31 | 2015-09-16 | 三菱重工業株式会社 | Transport container for fuel assembly |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5629964A (en) * | 1994-03-11 | 1997-05-13 | Roberts; Paul | Neutron absorbing apparatus |
DE19728978A1 (en) * | 1997-07-07 | 1999-01-14 | Siemens Ag | Gas-tight container for several used fuel elements of nuclear reactor |
DE29912810U1 (en) * | 1999-07-22 | 2000-11-23 | Siemens AG, 80333 München | Fuel assembly box with stop for lifting tools |
DE19947120C2 (en) * | 1999-09-30 | 2002-02-28 | Framatome Anp Gmbh | Process for preparing a fuel assembly for final storage and prepared fuel assembly |
-
2002
- 2002-06-13 DE DE10226245A patent/DE10226245A1/en not_active Withdrawn
-
2003
- 2003-05-22 ES ES03759894T patent/ES2322648T3/en not_active Expired - Lifetime
- 2003-05-22 DE DE50311371T patent/DE50311371D1/en not_active Expired - Lifetime
- 2003-05-22 WO PCT/EP2003/005339 patent/WO2003107356A1/en active Application Filing
- 2003-05-22 JP JP2004514086A patent/JP2005534003A/en active Pending
- 2003-05-22 EP EP03759894A patent/EP1512155B1/en not_active Expired - Lifetime
- 2003-06-06 TW TW092115357A patent/TWI220992B/en not_active IP Right Cessation
Also Published As
Publication number | Publication date |
---|---|
DE10226245A1 (en) | 2004-01-08 |
DE50311371D1 (en) | 2009-05-14 |
ES2322648T3 (en) | 2009-06-24 |
TWI220992B (en) | 2004-09-11 |
TW200402740A (en) | 2004-02-16 |
WO2003107356A1 (en) | 2003-12-24 |
EP1512155A1 (en) | 2005-03-09 |
JP2005534003A (en) | 2005-11-10 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
DE4438493A1 (en) | Boiling water reactor fuel element with improved spacer design | |
DE69601690T2 (en) | Device and method for jointly storing nuclear fuel bundles and control rods | |
DE69007338T2 (en) | Nuclear reactor fuel bundle with a device for collecting particles that are in the reactor cooling water. | |
CH686819A5 (en) | Tool for a punch press with a laser welding system. | |
EP1512155B1 (en) | Method and device for disposing of a fuel element case of a boiling water reactor | |
CH618040A5 (en) | Device for the ultimate disposal of radioactive waste substances | |
DE202017005797U1 (en) | Carrying structure for a multicopter | |
EP2017853B1 (en) | Method for dismantling a nuclear power plant | |
EP1439547B1 (en) | Transport and/or storage container for spent fuel elements, damaged fuel elements and/or fuel rods of damaged fuel elements | |
DD222720A5 (en) | LIQUID-HEATED CORE REACTOR, ESPECIALLY WATER REACTOR | |
EP1989715B1 (en) | Combustion element for a light-water reactor | |
DE10313792B4 (en) | Processing station for processing a workpiece | |
DE4017987C2 (en) | ||
DE69123126T2 (en) | FUEL ELEMENT RACK FOR CONSUMED FUEL FUEL | |
DE102019103202A1 (en) | Method and device including assembly tools and computer program for producing a partition grid | |
DE3529312A1 (en) | METHOD FOR THE ULTIMATE OR Dismantling Irradiated Nuclear Fuel Elements | |
EP4272227A1 (en) | Strengthening of fuel assemblies of nuclear power plants | |
DE2445984A1 (en) | PROCEDURE FOR FUEL SUPPLY FOR NUCLEAR REACTORS AND FUEL ELEMENT FOR THEM | |
DE10137284B4 (en) | Process for dismantling a process engineering apparatus | |
DE102014116224A1 (en) | Grating for industrial heat treatment | |
DE2935043A1 (en) | Holder for storing electronic components prior to processing - has tubular magazines held in holes in stack of horizontal support grids | |
DE1589632A1 (en) | Control rod for nuclear reactors | |
DE7622329U1 (en) | DEVICE FOR THE FINAL DISPOSAL OF RADIOACTIVE WASTE CLASSIFIED BY ACTIVITY | |
DE19937670A1 (en) | Storage of nuclear fuel elements and absorbers comprises assembling unused absorber elements into frame, and dismantling used elements | |
DE10348439B4 (en) | Punching device for packaging films |
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: 20041009 |
|
AK | Designated contracting states |
Kind code of ref document: A1 Designated state(s): AT BE BG CH CY CZ DE DK EE ES FI FR GB GR HU IE IT LI LU MC NL PT RO SE SI SK TR |
|
RBV | Designated contracting states (corrected) |
Designated state(s): DE ES FI SE |
|
RAP1 | Party data changed (applicant data changed or rights of an application transferred) |
Owner name: AREVA NP GMBH |
|
RAP1 | Party data changed (applicant data changed or rights of an application transferred) |
Owner name: AREVA NP GMBH |
|
GRAP | Despatch of communication of intention to grant a patent |
Free format text: ORIGINAL CODE: EPIDOSNIGR1 |
|
GRAS | Grant fee paid |
Free format text: ORIGINAL CODE: EPIDOSNIGR3 |
|
GRAA | (expected) grant |
Free format text: ORIGINAL CODE: 0009210 |
|
AK | Designated contracting states |
Kind code of ref document: B1 Designated state(s): DE ES FI SE |
|
REF | Corresponds to: |
Ref document number: 50311371 Country of ref document: DE Date of ref document: 20090514 Kind code of ref document: P |
|
REG | Reference to a national code |
Ref country code: ES Ref legal event code: FG2A Ref document number: 2322648 Country of ref document: ES Kind code of ref document: T3 |
|
REG | Reference to a national code |
Ref country code: SE Ref legal event code: TRGR |
|
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 |
Effective date: 20100105 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: ES Payment date: 20110524 Year of fee payment: 9 Ref country code: SE Payment date: 20110523 Year of fee payment: 9 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: FI Payment date: 20110520 Year of fee payment: 9 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: DE Payment date: 20110720 Year of fee payment: 9 |
|
REG | Reference to a national code |
Ref country code: SE Ref legal event code: EUG |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: FI Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20120522 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: SE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20120523 |
|
REG | Reference to a national code |
Ref country code: DE Ref legal event code: R119 Ref document number: 50311371 Country of ref document: DE Effective date: 20121201 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: DE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20121201 |
|
REG | Reference to a national code |
Ref country code: ES Ref legal event code: FD2A Effective date: 20131022 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: ES Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20120523 |