EP0115028B1 - Lagerbehälter für radioaktives Material - Google Patents
Lagerbehälter für radioaktives Material Download PDFInfo
- Publication number
- EP0115028B1 EP0115028B1 EP83112825A EP83112825A EP0115028B1 EP 0115028 B1 EP0115028 B1 EP 0115028B1 EP 83112825 A EP83112825 A EP 83112825A EP 83112825 A EP83112825 A EP 83112825A EP 0115028 B1 EP0115028 B1 EP 0115028B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- bush
- storage container
- lid
- container
- holding shaft
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
- 239000012857 radioactive material Substances 0.000 title claims description 6
- 230000007797 corrosion Effects 0.000 claims description 13
- 238000005260 corrosion Methods 0.000 claims description 13
- 239000000463 material Substances 0.000 claims description 10
- 238000003860 storage Methods 0.000 claims description 9
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 5
- 238000007789 sealing Methods 0.000 claims description 3
- 229910000831 Steel Inorganic materials 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 240000000731 Fagus sylvatica Species 0.000 description 1
- 235000010099 Fagus sylvatica Nutrition 0.000 description 1
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 229910000856 hastalloy Inorganic materials 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 238000012432 intermediate storage Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 239000011435 rock Substances 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 229910052719 titanium Inorganic materials 0.000 description 1
- 239000010936 titanium Substances 0.000 description 1
- 239000002699 waste material Substances 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 object of the invention is a storage container for radioactive material, in particular for spent fuel elements, consisting of a base body provided with a cover, a jacket made of a corrosion-resistant material surrounding the cover and the base body and a carrying device in the form of a trunnion.
- radioactive materials such as B. spent fuel from nuclear power plants or waste from facilities for the reprocessing of spent fuel
- containers are used in which the radioactive materials are safely enclosed, from which the heat generated can be safely dissipated at any time and which are critically safe.
- Thick-walled containers are usually used, some of which are lined with stainless steel on the inside. Should the containers be underground, e.g. B. stored in disused mines, the container walls must be able to absorb the mechanical forces and be corrosion-resistant. For reasons of economy, multilayered containers made of base body and jacket are used in such cases. A heat-resistant, inexpensive material is normally used for the base body, which does not have to be corrosion-resistant, since it does not come into contact with corrosive media. The tank is dimensioned so that it can withstand the rock pressure. It does not have to be tight so that the bottom and the lid can be inserted or screwed in. Corrosion-resistant materials are used for the jacket. High-alloy steels or zirconium- or titanium-based steels can be considered in salt mines in which the presence of quinary alkalis must be expected.
- Containers of this type predominantly contain storage boxes in which the radioactive inventory is located and are in turn placed in shielding containers, at least during transport and a possible intermediate storage.
- the lid of the multi-layer container is provided with a fixed mounting pin, with the aid of which the multi-layer container can be inserted into the shielding container and removed from it if necessary.
- the minimum trunnion height is about 15 to 20 cm.
- a disadvantage of this fixed mounting pin is that the shielding container must be made longer by this height. This increases the overall weight and increases the cost of the shielding container considerably.
- the weighted trunnion must be made of the same very expensive, corrosion-resistant material as the corrosion-proof outer jacket in order to avoid local element formation and the like. This also has a weight and cost disadvantageous effect.
- the invention was therefore based on the object of creating a storage container for radioactive material, in particular for spent fuel elements from nuclear reactors, consisting of a base body provided with a lid, a jacket surrounding the lid and the base body made of a corrosion-resistant material and a carrying device in the form a trunnion, in which the disadvantages described are eliminated and space and material-saving use is ensured while maintaining the favorable corrosion properties.
- the object was achieved in that a cylindrical recess is made in the cover, a bushing is inserted into this recess and the support pin is interchangeably fastened in this bushing, the bushing and jacket being made of the same material and welded to one another via a collar.
- the bushing is provided with an external thread for fastening in the recess and with an internal thread for fastening the support pin.
- the bushing has at least partially a flat bottom as a sealing surface and the bushing and trunnion are further provided with a central, matching bore for checking for leaks.
- a bushing (5) is located in a recess in the cover (3), which closes off the base body (4) of a storage container and which is provided with an all-round corrosion protection jacket (2) (e.g. made of Hastelloy).
- the bushing (5) and the corrosion protection jacket (2) are made of the same material.
- the socket (5) is firmly connected to the cover (3), preferably screwed into the cover (3) by means of an external thread (8).
- a support pin (1) is detachably connected to the socket (5), advantageously by means of a thread. Accordingly, the socket (5) can be equipped with an internal thread (9). However, other detachable connections, such as. B. bayonet connections possible.
- the bushing (5) is provided with a collar (11) which is welded to the corrosion protection jacket (2).
- the bushing (5) and the support pin (1) are provided with a central, matching bore (12, 13) for checking the corrosion protection jacket (2).
- helium or another suitable test gas can be used to detect any leaks in weld seams via a channel (7) into the gap (6) between the base body (4) or the cover (3) and the corrosion protection jacket (2) arrive.
- the bushing (5) at least partially has a flat bottom (10) on which additional sealing elements can be arranged if necessary. After leak tests have been carried out, the bore (12) in the bushing (5) can be closed, for example by means of a taper pin (14), which is then welded off.
- the trunnion (1) is removed from the beech (5). This eliminates all of the disadvantages described above - high material costs, wasted space and weight as well as damage to the cover (3) and scheduling.
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)
- Stackable Containers (AREA)
- Packages (AREA)
- Containers Having Bodies Formed In One Piece (AREA)
- Details Of Rigid Or Semi-Rigid Containers (AREA)
- Closures For Containers (AREA)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19828236359U DE8236359U1 (de) | 1982-12-24 | 1982-12-24 | Lagerbehaelter fuer radioaktives material |
| DE8236359U | 1982-12-24 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| EP0115028A1 EP0115028A1 (de) | 1984-08-08 |
| EP0115028B1 true EP0115028B1 (de) | 1987-05-27 |
Family
ID=6746855
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP83112825A Expired EP0115028B1 (de) | 1982-12-24 | 1983-12-20 | Lagerbehälter für radioaktives Material |
Country Status (7)
| Country | Link |
|---|---|
| US (1) | US4610839A (es) |
| EP (1) | EP0115028B1 (es) |
| JP (1) | JPS59166900A (es) |
| BR (1) | BR8306990A (es) |
| CA (1) | CA1219089A (es) |
| DE (2) | DE8236359U1 (es) |
| ES (1) | ES286831Y (es) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4926046A (en) * | 1988-12-12 | 1990-05-15 | Westinghouse Electric Corp. | Volumetrically efficient container apparatus |
| US5416334A (en) * | 1994-05-12 | 1995-05-16 | The United States Of America As Represented By The United States Department Of Energy | Hot cell shield plug extraction apparatus |
| DE19918334C1 (de) * | 1999-04-22 | 2001-01-18 | Siemens Ag | Vorrichtung zur Aufnahme von mit Feststoffen versetzten Flüssigkeiten sowie Vorrichtung zum Entfernen von Flüssigkeit aus einer derartigen Aufnahmevorrichtung |
| JP4064646B2 (ja) * | 2001-06-29 | 2008-03-19 | 三菱重工業株式会社 | 放射性物質の密閉容器、密閉容器の密閉溶接方法、および密閉溶接方法に用いる排気装置 |
| US6674828B1 (en) | 2002-06-14 | 2004-01-06 | David P. Weber | Safe lift and process for transporting canisters of spent nuclear fuel |
| US6788755B2 (en) | 2002-06-14 | 2004-09-07 | American Crane & Equipment Corporation | Safe lift and process for transporting canisters of spent nuclear fuel |
| JP2015518567A (ja) * | 2012-04-18 | 2015-07-02 | ホルテック・インターナショナル・インコーポレーテッド | 高レベル放射性廃棄物の貯蔵および／または移送 |
| FR3001958B1 (fr) * | 2013-02-13 | 2016-02-05 | Andra | Procede et casier d'entreposage de colis de substances radioactives dans un puits |
| WO2020251383A1 (ru) * | 2019-06-11 | 2020-12-17 | Акционерное Общество "Федеральный Центр Ядерной И Радиационной Безопасности" | Контейнер для транспортировки и/или хранения отработавших тепловыделяющиих сборок |
Family Cites Families (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US1616050A (en) * | 1925-08-11 | 1927-02-01 | Kania Rudolph | Domestic boiler |
| FR1484669A (fr) * | 1966-02-23 | 1967-06-16 | Commissariat Energie Atomique | Réceptacle pour le transport et le transfert de liquide radioactif |
| FR2050952A5 (es) * | 1969-06-30 | 1971-04-02 | Commissariat Energie Atomique | |
| US3749917A (en) * | 1971-05-12 | 1973-07-31 | H Kucherer | Device for encapsulating a radioactive resin-water slurry |
| US3789871A (en) * | 1972-04-19 | 1974-02-05 | Dexter Automatic Prod Co Inc | Vent apparatus |
| US4016749A (en) * | 1973-07-05 | 1977-04-12 | Wachter William J | Method and apparatus for inspection of nuclear fuel rods |
| FR2352377A1 (fr) * | 1976-05-21 | 1977-12-16 | Commissariat Energie Atomique | Installation pour le transfert dans un conteneur d'un produit toxique, notamment d'un produit radioactif a haut pouvoir de contamination, et conteneur adapte a la mise en oeuvre de cette installation |
| US4197467A (en) * | 1977-12-16 | 1980-04-08 | N L Industries, Inc. | Dry containment of radioactive materials |
| DE2830111C2 (de) * | 1978-07-08 | 1984-01-19 | Transnuklear Gmbh, 6450 Hanau | Deckelkonstruktion für Abschirmbehälter zum Transport und zur Lagerung bestrahtler Brennelemente |
| FR2456995A1 (fr) * | 1979-05-18 | 1980-12-12 | Commissariat Energie Atomique | Dispositif de fermeture de l'etui de transport d'un assemblage irradie dans un reacteur nucleaire |
| DE3010518A1 (de) * | 1980-03-19 | 1981-10-01 | GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen | Bauelementensatz fuer den abgeschirmten transport und fuer die abgeschirmte lagerung von radioaktiven substanzen |
| US4377509A (en) * | 1980-07-14 | 1983-03-22 | The United States Of America As Represented By The Secretary Of The Navy | Packaging for ocean disposal of low-level radioactive waste material |
| DE3148528A1 (de) * | 1980-12-22 | 1982-07-15 | Steag Kernenergie Gmbh, 4300 Essen | Vorrichtung zur aufbewahrung von radkoaktivem material |
| SE425707B (sv) * | 1981-03-20 | 1982-10-25 | Asea Ab | Sett att innesluta utbrenda kernbrenslestavar i en behallare av koppar |
| DE3138485C2 (de) * | 1981-09-28 | 1985-12-12 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Behälter zur Aufnahme und Aufbewahrung von radioaktiven Stoffen |
-
1982
- 1982-12-24 DE DE19828236359U patent/DE8236359U1/de not_active Expired
-
1983
- 1983-12-12 ES ES1983286831U patent/ES286831Y/es not_active Expired
- 1983-12-20 DE DE8383112825T patent/DE3371834D1/de not_active Expired
- 1983-12-20 EP EP83112825A patent/EP0115028B1/de not_active Expired
- 1983-12-20 BR BR8306990A patent/BR8306990A/pt not_active IP Right Cessation
- 1983-12-23 US US06/565,003 patent/US4610839A/en not_active Expired - Fee Related
- 1983-12-23 CA CA000444206A patent/CA1219089A/en not_active Expired
- 1983-12-23 JP JP58242250A patent/JPS59166900A/ja active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| DE3371834D1 (en) | 1987-07-02 |
| US4610839A (en) | 1986-09-09 |
| BR8306990A (pt) | 1984-07-31 |
| EP0115028A1 (de) | 1984-08-08 |
| JPS59166900A (ja) | 1984-09-20 |
| DE8236359U1 (de) | 1983-06-30 |
| ES286831Y (es) | 1986-06-01 |
| CA1219089A (en) | 1987-03-10 |
| ES286831U (es) | 1985-11-16 |
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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 |
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| 17P | Request for examination filed |
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| AK | Designated contracting states |
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| 17Q | First examination report despatched |
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| GRAA | (expected) grant |
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| STAA | Information on the status of an ep patent application or granted ep patent |
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| BERE | Be: lapsed |
Owner name: DEUTSCHE G- FUR WIEDERAUFARBEITUNG VON KERNBRENNS Effective date: 19921231 Owner name: NUKEM G.M.B.H. Effective date: 19921231 |
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| GBPC | Gb: european patent ceased through non-payment of renewal fee |
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