SK279074B6 - Container's internal device for transport and storage of nuclear fuel - Google Patents
Container's internal device for transport and storage of nuclear fuel Download PDFInfo
- Publication number
- SK279074B6 SK279074B6 SK1520-94A SK152094A SK279074B6 SK 279074 B6 SK279074 B6 SK 279074B6 SK 152094 A SK152094 A SK 152094A SK 279074 B6 SK279074 B6 SK 279074B6
- Authority
- SK
- Slovakia
- Prior art keywords
- longitudinal
- container
- dovetail groove
- nuclear fuel
- transport
- Prior art date
Links
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
- G21F5/008—Containers for fuel elements
- G21F5/012—Fuel element racks in the containers
-
- 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)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Stackable Containers (AREA)
- Filling Or Discharging Of Gas Storage Vessels (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Packaging Of Annular Or Rod-Shaped Articles, Wearing Apparel, Cassettes, Or The Like (AREA)
Abstract
Description
Oblasť technikyTechnical field
Vynález sa týka vnútorného zariadenia kontajnera určeného na transport a suché skladovanie čerstvých alebo vyhorených palivových článkov z jadrových reaktorov.The invention relates to an internal container device for the transport and dry storage of fresh or spent fuel elements from nuclear reactors.
Doterajší stav technikyBACKGROUND OF THE INVENTION
Sú známe uskutočnenia vnútorného zariadenia kontajnerov zostavené zo Stvor- alebo šesťhranných puzdier, kopírujúcich s nutnou montážnou vôľou skladované palivové články, vytvorených zvarením pásov z nerezových plechov legovaných bórom, ktorý pohlcovaním neutrónov zaisťuje podkritickosť palivových článkov. Medzi týmito puzdrami sú uložené s cieľom dištancovať ich polohy a odvod zvyškového tepla obvykle pozdĺžne plechové pásy z hliníkovej zliatiny, alebo priečne dosky s otvormi na jednotlivé puzdrá.There are known embodiments of an inner container device composed of four- or hexagonal bushings, coping with the necessary mounting clearance of the stored fuel elements, formed by welding the bores of stainless steel strips alloyed with boron, which by neutron absorption ensures the subcriticality of the fuel elements. Between these housings, usually longitudinal sheet metal strips of aluminum alloy or transverse plates with openings for individual housings are placed in order to distance their positions and dissipate residual heat.
Vzhľadom na technológiu výroby, t. j. lisovanie a zváranie, je ťažké dosiahnuť požadované presnosti pri zostavení vnútorného zariadenia z hľadiska jeho montáže do vlastného telesa kontajnera, pretože i tu je z dôvodov odvodu zvyškového tepla požadovaná minimálna vôľa medzi vonkajším povrchom vnútorného zariadenia a vnútorným povrchom telesa kontajnera. Sú známe i uskutočnenia, ktoré využívajú na výrobu puzdier hliníkovú zliatinu legovanú bórom. V tomto prípade nie je potrebné teplo odvádzajúce plechy alebo dosky ako v prechádzajúcom riešení, ale vzhľadom na to, že bór sa v hliníkovej zliatine nerozpúšťa, je z metalurgického hľadiska veľmi ťažké dosiahnuť rovnomerné legovanie hliníkovej zliatiny bórom, ktoré je nevyhnutné na zaistenie podkritickosti palivových článkov.With regard to production technology, i. j. pressing and welding, it is difficult to achieve the required accuracy when assembling the inner device in terms of its assembly into the container body itself, because here too, due to residual heat dissipation, a minimum clearance is required between the outer surface of the inner device and the inner surface of the container body. Embodiments are also known which use boron alloyed aluminum alloy to produce the sleeves. In this case there is no need for heat dissipating plates or plates as in the previous solution, but since boron does not dissolve in the aluminum alloy, it is very difficult from metallurgical point of view to achieve an even alloying of the aluminum alloy with boron necessary to ensure subcriticality of fuel cells. .
Podstata vynálezuSUMMARY OF THE INVENTION
Uvedené nevýhody podstatne obmedzuje vnútorné zariadenie kontajnera na transport a skladovanie jadrového paliva, zložené z profilových puzdier doliehajúcich vzájomne na seba časťou vonkajšej steny, pričom každé puzdro obklopuje aspoň jeden palivový článok a každá vonkajšia strana puzdra je od priliehajúcej vonkajšej strany ďalšieho puzdra zatienená absorpčným pásom. Podstata vynálezu vnútorného zariadenia kontajnera na transport a skladovanie jadrového paliva spočíva v tom, že v každej vonkajšej stene každého puzdra je vytvorená pozdĺžna rybinovitá drážka, ktorej dno je vybavené pozdĺžnymi výstupkami a do oboch koncov pozdĺžnej rybinovitej drážky je vložená plochá vložka vybavená klinovitým otvorom, do ktorého je uložený rozpínací klin. Každý absorpčný pás je uložený v priestore medzi plochými vložkami do pozdĺžnej tybinovitej drážky medzi ploché výstupky, zaisťujúce z každej strany medzeru medzi stenou puzdra a absorpčným pásom.The above-mentioned disadvantages are substantially reduced by the internal nuclear fuel transport and storage container device composed of profiled sleeves abutting a portion of the outer wall, each sleeve surrounding at least one fuel cell and each outer sleeve side being shielded from the adjacent outer sleeve side by an absorbent strip. According to the invention of the inner container for nuclear fuel transport and storage, a longitudinal dovetail groove is formed in each outer wall of each housing, the bottom of which is provided with longitudinal protrusions and a flat insert equipped with a wedge hole is inserted into both ends of the longitudinal dovetail groove. which has an expanding wedge. Each absorbent strip is disposed in the space between the flat inserts in a longitudinal, groove-like groove between the flat protrusions, providing on each side a gap between the wall of the housing and the absorbent strip.
Výhodou vnútorného zariadenia kontajnera podľa vynálezu je vďaka novému konštrukčnému usporiadaniu puzdier možnosť použiť na výrobu puzdier lacné, napr. hliníkové zliatiny bez obsahu bóru a lacnejšie bezodpadové technológie, napr. pretlačovanie bez toho, aby bola nutná dodatočná kalibrácia a aby bola znižovaná životnosť formy abrazívnymi účinkami bóru. To je umožnené tým, že prakticky každá stena každého puzdra je obložená absorpčným pásom, napr. z nehrdzavejúcej ocele legovanej bórom a to na optimálnom mieste z hľadiska využitia jeho absorpčných vlastností.The advantage of the inner container device according to the invention is, thanks to the new design of the sleeves, the possibility to use cheap ones for the manufacture of sleeves, e.g. boron-free aluminum alloys and cheaper waste-free technologies, eg extrusion without requiring additional calibration and reducing the life of the mold by the abrasive effects of boron. This is made possible by virtually every wall of each housing being lined with an absorbent band, e.g. of stainless steel alloyed with boron at the optimum location in terms of utilizing its absorption properties.
Spojenie jednotlivých puzdier je mechanické, nevyžaduje zváranie a vzhľadom na vzájomný kontakt medzi puzdrami nie je nutné používať ďalšie teplovodné materiály na odvod zvyškového tepla.The connection of the individual sleeves is mechanical, does not require welding, and due to the mutual contact between the sleeves, it is not necessary to use additional heat-conducting materials to remove residual heat.
Prehľad obrázkov na výkresochBRIEF DESCRIPTION OF THE DRAWINGS
Vynález je bližšie vysvetlený na výkresoch, na ktorých obr. 1 znázorňuje časť priečneho rezu vnútorným zariadením kontajnera podľa vynálezu, obr. 2 predstavuje pozdĺžny rez rybinovitou drážkou s plochou vložkou a rozpínacím klinom, obr. 3 zobrazuje priečny rez rybinovitou drážkou s rozpínacím klinom.BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a cross-sectional view of an internal device of a container according to the invention, FIG. 2 is a longitudinal section through a dovetail groove with a flat insert and an expanding wedge; FIG. 3 shows a cross-section of a dovetail groove with an expanding wedge.
Príklady uskutočnenia vynálezuDETAILED DESCRIPTION OF THE INVENTION
Vnútorné zariadenie kontajnera na transport a skladovanie jadrového paliva sa skladá podľa obr. 1 z niekoľkých puzdier 1. Puzdrá sú šesťhranné a ich vonkajšie steny 2 na seba v rohoch šesťhranu doliehajú. V každej vonkajšej stene 2 je vytvorená pozdĺžna rybinovitá drážka 3, ktorej dno je vybavené niekoľkými pozdĺžnymi výstupkami 30. Na týchto výstupkoch 30 spočíva absorpčný pás 4, ktorý je podľa obr. 2 a 3 v pozdĺžnom smere zaistený z oboch strán plochými vložkami 5, vloženými na každom z oboch koncov pozdĺžnej rybinovitej drážky 3. Každá plochá vložka 5 je vybavená klinovitým otvorom 50 na rozpínací klin 6, ktorý je v tomto prípade vybavený ešte vyťahovacím otvorom 60 so závitom na zaskrutkovanie nezakreslenej demontážnej skrutky a poistený v danej polohe zvarmi 70.The inner device of the nuclear fuel transport and storage container is folded according to FIG. 1 of a plurality of sleeves 1. The sleeves are hexagonal and their outer walls 2 abut against each other at the corners of the hexagon. In each outer wall 2 a longitudinal dovetail groove 3 is formed, the bottom of which is provided with a plurality of longitudinal protrusions 30. On these protrusions 30 the absorbent strip 4, which according to FIG. 2 and 3 in the longitudinal direction secured from both sides by flat inserts 5 inserted at each of the two ends of the longitudinal dovetail groove 3. Each flat inser 5 is provided with a wedge opening 50 for the expanding wedge 6, which in this case is also provided with a pull-out opening 60. threaded thread for unscrewed dismounting screw and locked in position by welding 70.
Vnútorné zariadenie kontajnera na transport a skladovanie jadrového paliva sa zostaví tak, že medzi jednotlivé puzdrá 1, la, lb, lc, ld, le, lf, lg, lh, li atď. sa postupne vložia absorpčné pásy 4 a z oboch koncov ploché vložky 5, ktoré po zasunutí rozpínacieho klina 6 navzájom spoja puzdrá 1. Počet a konfigurácia ustanovenia puzdier 1 je prakticky ľubovoľná podľa veľkosti kontajnera.The inner device of the nuclear fuel transport and storage container is assembled so that between the individual sleeves 1, 1a, 1b, 1c, 1d, 1e, 1f, 1g, 1h, 1i, etc. The absorbent strips 4 are inserted successively and from both ends the flat inserts 5, which after insertion of the expansion wedge 6 connect the sleeves 1 to each other. The number and configuration of the provision of the sleeves 1 is practically arbitrary according to the size of the container.
Claims (1)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CZ941071A CZ107194A3 (en) | 1994-05-03 | 1994-05-03 | Built-in structure of a container for transportation and storage of nuclear fuel |
Publications (2)
Publication Number | Publication Date |
---|---|
SK152094A3 SK152094A3 (en) | 1996-05-08 |
SK279074B6 true SK279074B6 (en) | 1998-06-03 |
Family
ID=5462709
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
SK1520-94A SK279074B6 (en) | 1994-05-03 | 1994-12-08 | Container's internal device for transport and storage of nuclear fuel |
Country Status (5)
Country | Link |
---|---|
CZ (1) | CZ107194A3 (en) |
DE (1) | DE4421486A1 (en) |
FR (1) | FR2719699B3 (en) |
GB (1) | GB2289007A (en) |
SK (1) | SK279074B6 (en) |
Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE19734166A1 (en) * | 1997-08-07 | 1999-02-11 | Siemens Ag | Transport container for spent nuclear reactor fuel elements |
FR2813701B1 (en) * | 2000-09-01 | 2002-11-29 | Transnucleaire | STORAGE BASKET FOR RADIOACTIVE MATERIAL |
FR2841034B1 (en) * | 2002-06-13 | 2004-09-03 | Cogema Logistics | STORAGE DEVICE FOR STORING AND / OR TRANSPORTING RADIOACTIVE MATERIAL |
FR2855311B1 (en) * | 2003-05-22 | 2006-02-03 | Cogema Logistics | STORAGE DEVICE FOR TRANSPORTING / STORING NUCLEAR FUEL ASSEMBLIES |
DE102013113785B4 (en) * | 2013-12-10 | 2016-01-14 | Nuclear Cargo + Service Gmbh | container |
CN108735315B (en) * | 2018-06-04 | 2024-05-14 | 江苏核电有限公司 | VVER spent fuel assembly storage cell and manufacturing method |
CN108735316B (en) * | 2018-06-04 | 2024-02-09 | 江苏核电有限公司 | Stainless steel boron aluminum composite board for storage cells of VVER fuel assembly and manufacturing method |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4331244A (en) * | 1980-05-02 | 1982-05-25 | The Babcock & Wilcox Company | Modular nuclear fuel assembly rack |
US4399366A (en) * | 1981-04-24 | 1983-08-16 | Bucholz James A | Separator assembly for use in spent nuclear fuel shipping cask |
US4746487A (en) * | 1981-06-10 | 1988-05-24 | U.S. Tool & Die, Inc. | Storage rack for nuclear fuel assemblies |
US4827139A (en) * | 1987-04-20 | 1989-05-02 | Nuclear Assurance Corporation | Spent nuclear fuel shipping basket and cask |
US4770844A (en) * | 1987-05-01 | 1988-09-13 | Westinghouse Electric Corp. | Basket structure for a nuclear fuel transportation cask |
US5232657A (en) * | 1991-06-28 | 1993-08-03 | Westinghouse Electric Corp. | Metal hydride flux trap neutron absorber arrangement for a nuclear fuel storage body |
-
1994
- 1994-05-03 CZ CZ941071A patent/CZ107194A3/en not_active IP Right Cessation
- 1994-06-20 DE DE4421486A patent/DE4421486A1/en not_active Withdrawn
- 1994-12-08 SK SK1520-94A patent/SK279074B6/en unknown
-
1995
- 1995-05-02 GB GB9508889A patent/GB2289007A/en not_active Withdrawn
- 1995-05-03 FR FR9505266A patent/FR2719699B3/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
FR2719699B3 (en) | 1996-04-26 |
SK152094A3 (en) | 1996-05-08 |
GB9508889D0 (en) | 1995-06-21 |
GB2289007A (en) | 1995-11-08 |
DE4421486A1 (en) | 1995-11-09 |
FR2719699A3 (en) | 1995-11-10 |
CZ280289B6 (en) | 1995-12-13 |
CZ107194A3 (en) | 1995-12-13 |
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