WO2005013286A2 - Brennelement für einen druckwasserkernreaktor - Google Patents
Brennelement für einen druckwasserkernreaktor Download PDFInfo
- Publication number
- WO2005013286A2 WO2005013286A2 PCT/EP2004/008041 EP2004008041W WO2005013286A2 WO 2005013286 A2 WO2005013286 A2 WO 2005013286A2 EP 2004008041 W EP2004008041 W EP 2004008041W WO 2005013286 A2 WO2005013286 A2 WO 2005013286A2
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- webs
- spacer
- fuel element
- lattice
- outside
- 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.)
- Ceased
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/34—Spacer grids
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
- G21C3/332—Supports for spacer grids
-
- 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
Definitions
- the invention relates to a fuel assembly for a pressurized water nuclear reactor, as is known for example from DE 196 35 927 Cl.
- Such a fuel assembly is exemplarily illustrated in FIG. 5.
- a plurality of fuel rods 2 are guided parallel to one another in the rod direction (axially) through a plurality of spacers 4 which are axially spaced apart from one another, each of which forms a two-dimensional grid with a plurality of meshes 6 which are arranged in columns 8 and rows 10.
- support tubes which do not contain any fuel and are provided for receiving and guiding control rods (so-called control rod guide tubes 12) are passed through the meshes 6 of this grid in addition to the fuel rods.
- support tubes may also be present, which likewise do not contain any fuel and only serve to increase the stability (instrumentation tubes or structural tubes, neither instrument tubes nor structural tubes are provided in the fuel element 2 shown as an example). Unlike the fuel rods in the meshes 6, these support tubes are welded to the spacers 4, so that their stabilizing effect is ensured over the entire service life of the fuel assembly 2.
- the spacers are therefore designed so that the expected shock loads do not lead to a major bulge or buckling of the spacer.
- the invention is based on the object of specifying a fuel assembly for a pressurized water nuclear reactor in which, even after the action of transverse forces which exceed the buckling resistance of the spacers, i. H. after irreversible plastic deformation, the insertability of the control rods is improved compared to the known fuel elements.
- a fuel assembly for a pressurized water nuclear reactor which contains a plurality of fuel rods, which are guided in a plurality of axially spaced spacers, each one
- a support tube control rod guide tube or structural tube
- the spacer is designed in such a way that when one is passed laterally onto the spacer effective limit force a deformation exclusively, ie due to the system due to the mechanical Structure (systematic) always begins in an area of the spacer, which is located outside of an inner area containing the control rod guide tubes.
- the invention is based on the knowledge that the targeted introduction of the deformation (bulging or buckling) at the edge of the spacer ensures the integrity of the inner area, which is sensitive to the mobility of the control rods, even as the deformation progresses, since the plastic deformation is initially only in the Progresses in areas where it starts.
- FIG. 6 and 7 each show a schematic representation of a customary spacer 4a, in the example a spacer with 17 x 17 stitches 6, on the opposite side edges of which a pressing force F perpendicular to the rows 10 (parallel to the columns 8) has been exerted , which lies above the buckling or buckling limit Fki t .
- support tube sections were welded into the spacer 4 at the positions P a , at which control rod guide tubes 12 are located in the fuel assembly, and protrude about 10 mm on both sides from the spacer 4.
- the spacer 4 was either thermally relaxed and each support tube-free mesh 6 with sections of fuel rod cladding that belong to the respective spacer type, or instead of the cladding tube sections normally provided for this spacer type, tube sections with a slightly smaller outer diameter were used in order to simulate the relaxation of the spacer 4 in this way.
- the cladding tube sections also protrude above the spacer 4 and simulate the fuel rods that are spring-loaded in the meshes that are not penetrated by control rod guide tubes when the fuel element is completely configured.
- Fig. 6 it can now be seen by way of example that when the buckling limit F kr ⁇ t is reached, a bump-like bulging or buckling of two middle rows 10 10 , 10n takes place.
- An increase in the transverse force F can lead to the buckling of further rows 10 ⁇ , 10 2 , 10 7 , 10 8 , 10i 6 and 10 ⁇ 7 , as is illustrated in FIG. 7.
- FIG. 8 A similar situation is shown in FIG. 8 with a conventional 16 x 16 spacer 4b, in which bulging also begins in the middle rows 10 8 , 10 9 , which are free of support or control rod guide tubes.
- the invention is now based on the observation that a central bulge is far more problematic than a bulge on the edge, since the former leads to a mutual offset of the control rod guide tubes leads, as can be seen easily with reference to FIGS. 6-8.
- the invention is based on the consideration that - by means of targeted constructive measures, in particular through a specifically weaker design of the edge zones of the spacer located outside the inner region, the start of the deformation can be systematically shifted to this. In this way, the integrity of the interior is maintained even when deformation begins.
- the meshes of the spacer are formed preferably by arranged at the edge 'grid edge webs and internal grid webs, which in the following, the term grid bar both
- Lattice webs can also designate lattice inner webs.
- the edge zone in which such mechanical weakening is carried out is then formed from the inner grid bars located outside the inner area, the ends of the inner grid bars penetrating the inner area, and the grid edge bars.
- At least one grating inner web penetrating the inner region has a higher strength than at least one grating inner web arranged outside this inner region.
- Lattice webs are preferably connected to one another by welded connections, with at least some of the welded connections of the inner lattice webs outside the inner region having a lower strength than the welded connections the inner grid bars are made within the interior.
- At least some of the inner grid webs have a material weakening in a web area lying outside the inner area compared to the web areas arranged inside the inner area, this material weakening in particular due to a smaller wall thickness (web width) of these inner web webs or specifically for weakening into the webs recesses is made.
- FIG. 1 each show a spacer according to the invention in a schematic plan view after a deformation test has been carried out
- FIG. 3 shows a perspective view of a section of a spacer in an edge area, in which different measures according to the invention for targeted weakening in this edge area are illustrated schematically
- FIG. 4 shows a further embodiment of a spacer according to the invention in a schematic plan view, likewise after carrying out a deformation test
- FIG. 5 shows a fuel assembly for a pressurized water nuclear reactor, as is known in the prior art
- FIGS. 6-8 each have a known spacer in a schematic plan view after carrying out a deformation test.
- FIG. 1 shows a 16 x 16 spacer 4, with an arrangement of the support tubes in positions P a , as they are also in the known spacer shown in Fig. 8.
- all support tubes are control rod guide tubes 12. No further structural tubes are present in this exemplary embodiment.
- the spacer 4 is made up of bars 14 ⁇ , - 14 ⁇ 7 , and 16 ⁇ - 16 17 , which are welded together at the crossing points.
- the grid webs 14 ⁇ , 14 17 , 16 ⁇ and 16 ⁇ 7 form the edge of the grid and are referred to below as grid edge webs.
- the lattice webs 14 2 - 14 16 and 16 2 - 16 ⁇ 6 run inside the lattice and are referred to below as lattice inner webs.
- the control rod guide tubes 12 define an inner region 18 highlighted by hatching, which in the exemplary embodiment is formed by the square zone delimited by the inner grid webs 14 3 14 ⁇ 5 , 16 3 and 16 15 , which these inner grid webs 14 3 , 14 15 , 16 3 and 16 15 includes.
- the points marked by a black dot that the welded connections 20 of the inner grid webs 14 2 , 14 16 , 16 2 , 16 ⁇ 6 located outside this inner region 18 with the grid inner webs 16 2 -i6 or 14 2 -i6 is weakened compared to the other welding points. This can be done by reducing the welding length, the diameter of the welding nodes or the number of welding points.
- the welded connections of the lattice edge webs to one another and to the lattice inner webs can also undergo targeted weakening.
- the weakenings made in the exemplary embodiment only on the inner web bars are particularly advantageous.
- Fig. 2 the spacer 4 is gem.
- Fig. 1 shown after carrying out a deformation test, in which, in contrast to the situation shown in Fig. 1, sliding on one of the side surfaces between which the force F> F kr ⁇ t is exerted has been prevented. It can be seen from the figure that in this case a deformation occurs which, unlike the point-symmetrical deformation according to FIG. 1, is mirror-symmetrical. In this case too, the integrity of the inner region 18 is retained.
- FIG. 3 there is a grating inner web arranged outside the inner region, for example the grating inner web 14 2 with inner grating webs l ⁇ ⁇ i + , i +3 crossing with it in one shown perspective section.
- a spacer is shown in the example, in which the inner lattice webs 14 2 , 16i, i + ⁇ ( ⁇ +3 are connected to one another with welding nodes 22a, b.
- An alternative embodiment consists in reducing the number of welding nodes 22b per crossing point, but carrying them out identically to the welding nodes in the interior area (crossing point B).
- a targeted weakening can also be achieved by making recesses 24 in the inner grid webs 14 2 , 16i, i +1 , ⁇ +3 in their web areas lying outside the inner region 18 (crossing point C).
- the inner grid webs 1, 2.16 / 162.16 arranged outside the inner region 18 with a reduced wall thickness compared to the other grid webs (inner grid webs and outer grid webs).
- the measures mentioned - reducing the diameter of the welding nodes, reducing the number of welding nodes, weakening the web plates - can also be combined with one another.
- the lattice bridges can also be included in the measures mentioned.
- the middle inner lattice webs 14 9 , 16 9 is designed to be stronger than the inner grid webs 14 ⁇ , 14 X6 , 16 ⁇ , 16 ⁇ 6 outside the inner region 18.
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)
- Fuel-Injection Apparatus (AREA)
Abstract
Description
Claims
Priority Applications (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2006521465A JP2007500339A (ja) | 2003-07-28 | 2004-07-19 | 加圧水形原子炉の燃料集合体 |
| EP04741134A EP1611584A2 (de) | 2003-07-28 | 2004-07-19 | Brennelement für einen druckwasserkernreaktor |
| US11/343,041 US20060285629A1 (en) | 2003-07-28 | 2006-01-30 | Fuel assembly for a pressurized water nuclear reactor |
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE10334580A DE10334580B3 (de) | 2003-07-28 | 2003-07-28 | Brennelement für einen Druckwasserkernreaktor |
| DE10334580.9 | 2003-07-28 |
Related Child Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US11/343,041 Continuation US20060285629A1 (en) | 2003-07-28 | 2006-01-30 | Fuel assembly for a pressurized water nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| WO2005013286A2 true WO2005013286A2 (de) | 2005-02-10 |
| WO2005013286A3 WO2005013286A3 (de) | 2005-06-23 |
Family
ID=34111725
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/EP2004/008041 Ceased WO2005013286A2 (de) | 2003-07-28 | 2004-07-19 | Brennelement für einen druckwasserkernreaktor |
Country Status (9)
| Country | Link |
|---|---|
| US (1) | US20060285629A1 (de) |
| EP (1) | EP1611584A2 (de) |
| JP (1) | JP2007500339A (de) |
| KR (1) | KR100778613B1 (de) |
| CN (1) | CN1320553C (de) |
| DE (1) | DE10334580B3 (de) |
| TW (1) | TWI263232B (de) |
| WO (1) | WO2005013286A2 (de) |
| ZA (1) | ZA200507003B (de) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009526977A (ja) * | 2006-02-18 | 2009-07-23 | アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング | 加圧水形原子炉の燃料集合体 |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2065898A1 (de) * | 2007-12-01 | 2009-06-03 | AREVA NP GmbH | Brennelement für einen Siedewasserreaktor |
| CA2818881C (en) * | 2010-11-23 | 2019-06-11 | Westinghouse Electric Company Llc | Full spectrum loca evaluation model and analysis methodology |
| JP6244172B2 (ja) * | 2013-04-18 | 2017-12-06 | 原子燃料工業株式会社 | 原子炉の燃料集合体用グリッド |
| US20170032853A1 (en) * | 2015-07-29 | 2017-02-02 | Westinghouse Electric Company Llc | Nuclear fuel assembly with seismic/loca tolerance grid |
| CN114999688B (zh) * | 2022-06-14 | 2024-04-26 | 中国核动力研究设计院 | 一种缩比模拟燃料组件 |
| JP2024171673A (ja) * | 2023-05-30 | 2024-12-12 | 株式会社日立製作所 | 燃料集合体及び原子炉の炉心 |
Family Cites Families (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4325786A (en) * | 1979-11-29 | 1982-04-20 | Combustion Engineering, Inc. | Spacer grid for reducing bowing in a nuclear fuel assembly |
| LU82970A1 (fr) * | 1980-11-28 | 1982-06-30 | Metallurgie Hoboken | Procede pour collecter de metaux non-ferreux contenus dans des dechets ferres |
| US4659542A (en) * | 1984-10-03 | 1987-04-21 | Westinghouse Electric Corp. | Grid structure for nuclear fuel assembly |
| US5271054A (en) * | 1991-09-25 | 1993-12-14 | Combustion Engineering, Inc. | Perimeter grid strip |
| US5307392A (en) * | 1992-06-29 | 1994-04-26 | Combustion Engineering, Inc. | Energy dissipating outer strip for grid |
| SE510816C2 (sv) * | 1993-11-02 | 1999-06-28 | Asea Atom Ab | Spridare och bränslepatron för en kärnreaktor |
| WO1995024718A1 (de) * | 1994-03-08 | 1995-09-14 | Siemens Aktiengesellschaft | Abstandhaltergitter für kernbrennstoff enthaltende brennstäbe eines kernreaktorbrennelements |
| US5703392A (en) * | 1995-06-02 | 1997-12-30 | Utron Technology Inc | Minimum size integrated circuit static memory cell |
| FR2736190B1 (fr) * | 1995-06-29 | 1997-10-10 | Framatome Sa | Grille-entretoise d'un assemblage de combustible pour un reacteur nucleaire et assemblage de combustible |
| US5675621A (en) * | 1995-08-17 | 1997-10-07 | General Electric Company | Reduced height flat spring spacer for nuclear fuel rods |
| US6167104A (en) * | 1996-09-04 | 2000-12-26 | Siemens Aktiengesellschaft | Pressurized water reactor fuel assembly with a guide tube and method for producing the guide tube |
| DE19635927C1 (de) * | 1996-09-04 | 1998-02-12 | Siemens Ag | Führungsrohre für Druckwasserreaktor-Brennelement mit minimiertem strahlungsinduziertem Wachstum und zugehöriges Herstellungsverfahren |
| JP2000230994A (ja) * | 1999-02-09 | 2000-08-22 | Nippon Nuclear Fuel Dev Co Ltd | 燃料集合体用スペーサ |
| RU2177650C2 (ru) * | 2000-01-26 | 2001-12-27 | Открытое акционерное общество "Машиностроительный завод" | Тепловыделяющая сборка водо-водяного энергетического ядерного реактора |
| US6522710B2 (en) * | 2001-07-03 | 2003-02-18 | Westinghouse Electric Company Llc | Fastened spacer for grid of a nuclear reactor with associated method |
| DE10146128B4 (de) * | 2001-09-19 | 2005-03-03 | Framatome Anp Gmbh | Brennelement für einen Druckwasserreaktor |
| US6606369B1 (en) * | 2002-03-06 | 2003-08-12 | Westinghouse Electric Company Llc | Nuclear reactor with improved grid |
| DE10236400B4 (de) * | 2002-06-29 | 2005-08-18 | Framatome Anp Gmbh | Brennelement für einen Druckwasserkernreaktor |
-
2003
- 2003-07-28 DE DE10334580A patent/DE10334580B3/de not_active Expired - Fee Related
-
2004
- 2004-07-19 EP EP04741134A patent/EP1611584A2/de not_active Withdrawn
- 2004-07-19 WO PCT/EP2004/008041 patent/WO2005013286A2/de not_active Ceased
- 2004-07-19 JP JP2006521465A patent/JP2007500339A/ja active Pending
- 2004-07-19 KR KR1020067001124A patent/KR100778613B1/ko not_active Expired - Fee Related
- 2004-07-19 CN CNB2004800104414A patent/CN1320553C/zh not_active Expired - Fee Related
- 2004-07-26 TW TW093122238A patent/TWI263232B/zh active
-
2005
- 2005-09-01 ZA ZA200507003A patent/ZA200507003B/en unknown
-
2006
- 2006-01-30 US US11/343,041 patent/US20060285629A1/en not_active Abandoned
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009526977A (ja) * | 2006-02-18 | 2009-07-23 | アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング | 加圧水形原子炉の燃料集合体 |
Also Published As
| Publication number | Publication date |
|---|---|
| WO2005013286A3 (de) | 2005-06-23 |
| CN1777961A (zh) | 2006-05-24 |
| TW200509143A (en) | 2005-03-01 |
| ZA200507003B (en) | 2006-04-26 |
| US20060285629A1 (en) | 2006-12-21 |
| DE10334580B3 (de) | 2005-03-17 |
| JP2007500339A (ja) | 2007-01-11 |
| EP1611584A2 (de) | 2006-01-04 |
| KR100778613B1 (ko) | 2007-11-22 |
| TWI263232B (en) | 2006-10-01 |
| CN1320553C (zh) | 2007-06-06 |
| KR20060030516A (ko) | 2006-04-10 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| DE3887230T2 (de) | Abstandhaltergitter für ein Kernbrennstabbündel. | |
| DE2905661C2 (de) | Abstandshalter für die zu einem Kernreaktorbrennelement zusammengefaßten Brennstäbe | |
| DE2514300A1 (de) | Vorgefertigte mehrschichtenstahlbetonplatte | |
| DE69104285T2 (de) | Fussstück für Kernreaktorbrennstabbündel mit einer Adapterplatte und einer daran befestigten Filterplatte. | |
| DE2827927C2 (de) | ||
| DE1294574B (de) | Auswechselbares Kernreaktor-Brennelement, bestehend aus mehreren Brennstaeben | |
| DE10334580B3 (de) | Brennelement für einen Druckwasserkernreaktor | |
| DE69404263T2 (de) | Einrichtung zur Messung der von einem Bündelabstandhalter ausgeübten Kraft | |
| DE2550932B2 (de) | Zellenförmige Brennelement-Rostkonstruktion | |
| CH629619A5 (de) | Halterung fuer stabartige elemente in einem kernreaktor. | |
| DE68903892T2 (de) | Mischgitter mit ablenkfahnen fuer kernstabbuendel. | |
| DE102019201682A1 (de) | Bauwerksdämpfer mit wenigstens einem zumindest bereichsweise leiterartig ausgebildeten Schubdämpfungsteil | |
| DE69512516T2 (de) | Abstandshalter mit reduzierter höhe für kernbrennstäbe | |
| EP1984924B1 (de) | Brennelement für einen druckwasserkernreaktor | |
| DE2749583B2 (de) | Kernbrennelement mit einer Abstandshalteeinrichtung | |
| DE102009046668A1 (de) | Brennelement für einen Druckwasserkernreaktor | |
| EP1795667A2 (de) | Bewehrungselement für Tragwerke aus Stahlbeton, Spannbeton oder dergleichen | |
| DE10236399B4 (de) | Brennelement für einen Druckwasserkernreaktor | |
| DE805649C (de) | Unterteilter Betonbalken o. dgl., insbesondere Eisenbahnschwelle | |
| DE2122008B2 (de) | Kernbrennstoffanordnung | |
| DE2543626A1 (de) | Stabfoermige bauteile zwischen brennelementen von siedewasserreaktoren | |
| WO1993024933A1 (de) | Kernreaktorbrenstabbündel mit sechseckigem aus zusammengesetzten basiselementen bestehendem abstandhalter | |
| DE3723883A1 (de) | Spannbetontraeger | |
| DE2539645A1 (de) | Vorrichtung zur irreversiblen stossabsorption | |
| DE1960579A1 (de) | Als Feder wirkende Vorrichtung |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| AK | Designated states |
Kind code of ref document: A2 Designated state(s): AE AG AL AM AT AU AZ BA BB BG BR BW BY BZ CA CH CN CO CR CU CZ DE DK DM DZ EC EE EG ES FI GB GD GE GH GM HR HU ID IL IN IS JP KE KG KP KR KZ LC LK LR LS LT LU LV MA MD MG MK MN MW MX MZ NA NI NO NZ OM PG PH PL PT RO RU SC SD SE SG SK SL SY TJ TM TN TR TT TZ UA UG US UZ VC VN YU ZA ZM ZW |
|
| AL | Designated countries for regional patents |
Kind code of ref document: A2 Designated state(s): BW GH GM KE LS MW MZ NA SD SL SZ TZ UG ZM ZW AM AZ BY KG KZ MD RU TJ TM AT BE BG CH CY CZ DE DK EE ES FI FR GB GR HU IE IT LU MC NL PL PT RO SE SI SK TR BF BJ CF CG CI CM GA GN GQ GW ML MR NE SN TD TG |
|
| 121 | Ep: the epo has been informed by wipo that ep was designated in this application | ||
| WWE | Wipo information: entry into national phase |
Ref document number: 2005/07003 Country of ref document: ZA Ref document number: 200507003 Country of ref document: ZA |
|
| WWE | Wipo information: entry into national phase |
Ref document number: 20048104414 Country of ref document: CN |
|
| WWE | Wipo information: entry into national phase |
Ref document number: 2004741134 Country of ref document: EP |
|
| WWE | Wipo information: entry into national phase |
Ref document number: 2006521465 Country of ref document: JP |
|
| WWP | Wipo information: published in national office |
Ref document number: 2004741134 Country of ref document: EP |
|
| WWE | Wipo information: entry into national phase |
Ref document number: 1020067001124 Country of ref document: KR |
|
| WWE | Wipo information: entry into national phase |
Ref document number: 11343041 Country of ref document: US |
|
| WWP | Wipo information: published in national office |
Ref document number: 1020067001124 Country of ref document: KR |
|
| WWP | Wipo information: published in national office |
Ref document number: 11343041 Country of ref document: US |