EP0057429B1 - Conteneur multi-couches pour le transport et le stockage de déchets radioactifs - Google Patents
Conteneur multi-couches pour le transport et le stockage de déchets radioactifs Download PDFInfo
- Publication number
- EP0057429B1 EP0057429B1 EP82100591A EP82100591A EP0057429B1 EP 0057429 B1 EP0057429 B1 EP 0057429B1 EP 82100591 A EP82100591 A EP 82100591A EP 82100591 A EP82100591 A EP 82100591A EP 0057429 B1 EP0057429 B1 EP 0057429B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- container
- layers
- storage
- transporting
- layer
- 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
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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
Definitions
- the invention relates to a multilayered transport and storage container for the long-term storage of radioactive waste, in particular spent fuel elements, in suitable geological formations, the container consisting of three or more layers of different metals or metal alloys, which from the outside inward in the electrochemical voltage series become more and more noble (positive).
- Irradiated, spent fuel elements are processed either immediately after temporary storage in the water basin or after a limited further interim storage.
- the nuclear fuels and broods are separated from the fission products and returned to the fuel cycle.
- the cleavage products are by known methods, usually using large amounts of valuable materials, such as. B. lead and copper, conditioned and in suitable geological formations practically no longer removable.
- Containers made of alloyed and unalloyed steel, copper and corundum are proposed as packaging for radioactive materials and irradiated fuel elements.
- the steel containers are either not sufficiently corrosion-resistant or, like copper, are very expensive.
- Corundum containers are generally suitable, but the experience required for their manufacture is lacking.
- the fuel elements for packaging would have to be disassembled into small corundum containers for manufacturing reasons, which is associated with considerable effort.
- Such containers only partially meet the conditions of long-term storage, such as tight containment at the pressures and temperatures that occur, and corrosion against brine, or they must be made very thick-walled. In addition, they are usually not suitable as a transport container at the same time, so that the waste has to be reloaded from the transport container into the final storage container at considerable expense.
- Steel containers for receiving spent fuel elements are known from DE-A-2804828, on the inner and / or outer surface of which aluminum layers of 0.5 to 2 mm thickness are located. These containers are also not sufficiently corrosion-resistant for long-term storage.
- the container has at least three layers, of which the outer layer is made of cast iron, the next inner layer of nickel or a nickel alloy and the inner layer of copper or a copper alloy. This ensures that, even if there is a partial corrosive breakthrough through the outer layer, the subsequent layer can only be attacked when the outer layer has completely dissolved. This means that the resistance time value can be calculated and the service life against corrosion is retained even in the event of unforeseeable malfunctions.
- the time for the dissolution of the second jacket can also be calculated. Based on the removal rates per time and area, the service life of the outer jacket in a certain corrosive medium, as well as the service life of the second jacket etc. can be calculated. With this arrangement, it is possible to manufacture the outer jacket from relatively inexpensive material, such as cast iron, to make the container for its suitability as a transport container to give the necessary rigidity for the 9 m drop test.
- the repository container consists of the outer jacket (1) with a welded or joined lid (5). Alloyed cast iron, preferably cast iron, is used as the material.
- the first inner jacket (2) located in this outer container consists of nickel or a nickel alloy, which is more noble in the electrochemical series than the outer jacket (1). An excessively large potential spacing is not desirable so as not to accelerate too much in the event of local element formation as the outer sheath goes into solution.
- the second inner container (3) must again be nobler in material than the first inner jacket (2). Here nickel-copper alloys come into consideration.
- the interior (4) is filled with spent fuel or highly active waste. All three container layers are self-contained, which can be done, for example, by welding.
- the electrochemical potentials of the adjacent layers are not too far apart.
- the layer thicknesses of the outer layers are in the range of 5 to 20 cm, those of the other noble layers in the range of 5 to 50 mm. Above all, bronzes, especially tin-rich ones, have proven themselves as corrosion-resistant materials.
Landscapes
- Engineering & Computer Science (AREA)
- Environmental & Geological Engineering (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Laminated Bodies (AREA)
- Filling Or Discharging Of Gas Storage Vessels (AREA)
- Details Of Rigid Or Semi-Rigid Containers (AREA)
- Electroplating Methods And Accessories (AREA)
Claims (2)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE3103526 | 1981-02-03 | ||
DE3103526A DE3103526C2 (de) | 1981-02-03 | 1981-02-03 | Mehrschichtiger Transport- und Lagerbehälter für radioaktive Abfälle |
Publications (3)
Publication Number | Publication Date |
---|---|
EP0057429A2 EP0057429A2 (fr) | 1982-08-11 |
EP0057429A3 EP0057429A3 (en) | 1985-12-11 |
EP0057429B1 true EP0057429B1 (fr) | 1989-03-15 |
Family
ID=6123895
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP82100591A Expired EP0057429B1 (fr) | 1981-02-03 | 1982-01-28 | Conteneur multi-couches pour le transport et le stockage de déchets radioactifs |
Country Status (5)
Country | Link |
---|---|
US (1) | US4562001A (fr) |
EP (1) | EP0057429B1 (fr) |
JP (1) | JPS57178189A (fr) |
CA (1) | CA1166027A (fr) |
DE (2) | DE3103526C2 (fr) |
Families Citing this family (13)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4935943A (en) * | 1984-08-30 | 1990-06-19 | The United States Of America As Represented By The United States Department Of Energy | Corrosion resistant storage container for radioactive material |
DE3445124C1 (de) * | 1984-12-11 | 1986-01-23 | Nukem Gmbh, 6450 Hanau | Auskleidung fuer Bohrloecher in Salzstoecken |
DE3610862A1 (de) * | 1986-04-01 | 1987-10-08 | Kernforschungsz Karlsruhe | Laengszylindrischer behaelter fuer die endlagerung von einer oder mehreren mit hochradioaktiven abfaellen gefuellten kokillen |
US4891165A (en) * | 1988-07-28 | 1990-01-02 | Best Industries, Inc. | Device and method for encapsulating radioactive materials |
WO1990001208A1 (fr) * | 1988-07-28 | 1990-02-08 | Best Industries, Inc. | Procede et dispositif d'encapsulation de materiaux radioactifs |
US4861520A (en) * | 1988-10-28 | 1989-08-29 | Eric van't Hooft | Capsule for radioactive source |
US5899882A (en) * | 1994-10-27 | 1999-05-04 | Novoste Corporation | Catheter apparatus for radiation treatment of a desired area in the vascular system of a patient |
US5683345A (en) | 1994-10-27 | 1997-11-04 | Novoste Corporation | Method and apparatus for treating a desired area in the vascular system of a patient |
US5611429A (en) * | 1995-04-05 | 1997-03-18 | Phillips; Paul B. | Medical syringe disposal |
US6544606B1 (en) * | 2000-01-11 | 2003-04-08 | Nac International | Systems and methods for storing fissile materials |
NO20044434D0 (no) * | 2004-10-19 | 2004-10-19 | Nuclear Prot Products As | Lang-tids lagringscontainer og fremgangsmate for fremstilling av denne |
SE531261C2 (sv) * | 2007-05-25 | 2009-02-03 | Olle Grinder | Kapsel avsedd för slutförvaring av utbränt kärnbränsle |
CN111739672B (zh) * | 2020-05-13 | 2023-12-22 | 中国核电工程有限公司 | 一种降低氚渗透速率的结构 |
Family Cites Families (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3610290A (en) * | 1968-10-22 | 1971-10-05 | Texas Instruments Inc | Metal laminates and tubing embodying such laminates |
US4208453A (en) * | 1969-06-30 | 1980-06-17 | Alloy Surfaces Company, Inc. | Modified diffusion coating of the interior of a steam boiler tube |
US4031921A (en) * | 1975-09-09 | 1977-06-28 | The United States Of America As Represented By The United States Energy Research And Development Administration | Hydrogen-isotope permeation barrier |
US4290847A (en) * | 1975-11-10 | 1981-09-22 | Minnesota Mining And Manufacturing Company | Multishell microcapsules |
FR2375695A1 (fr) * | 1976-12-21 | 1978-07-21 | Asea Ab | Procede pour le traitement de dechets radioactifs |
JPS6051070B2 (ja) * | 1977-07-21 | 1985-11-12 | 株式会社東芝 | 核燃料要素およびその製造方法 |
JPS5428738A (en) * | 1977-08-08 | 1979-03-03 | Usui Kokusai Sangyo Kk | Double plated band steel for use in making corrosion resistant overlapped steel pipes |
DE2804828A1 (de) * | 1978-02-04 | 1979-08-09 | Nukem Gmbh | Stahlbehaelter zur aufnahme abgebrannter brennelemente |
US4192765A (en) * | 1978-02-15 | 1980-03-11 | John N. Bird | Container for radioactive nuclear waste materials |
US4337167A (en) * | 1978-02-15 | 1982-06-29 | Bird John M | Container for radioactive nuclear waste materials |
JPS5589792A (en) * | 1978-12-28 | 1980-07-07 | Tokyo Shibaura Electric Co | Nuclear fuel rod |
US4362696A (en) * | 1979-05-21 | 1982-12-07 | The United States Of America As Represented By The United States Department Of Energy | Corrosion-resistant fuel cladding allow for liquid metal fast breeder reactors |
US4292528A (en) * | 1979-06-21 | 1981-09-29 | The Carborundum Company | Cask for radioactive material and method for preventing release of neutrons from radioactive material |
US4338215A (en) * | 1979-09-24 | 1982-07-06 | Kennecott Corporation | Conversion of radioactive wastes to stable form for disposal |
JPS5662955A (en) * | 1979-10-26 | 1981-05-29 | Hitachi Ltd | Manufacture of nuclear fuel cladding pipe |
-
1981
- 1981-02-03 DE DE3103526A patent/DE3103526C2/de not_active Expired
-
1982
- 1982-01-28 EP EP82100591A patent/EP0057429B1/fr not_active Expired
- 1982-01-28 DE DE8282100591T patent/DE3279552D1/de not_active Expired
- 1982-02-02 CA CA000395350A patent/CA1166027A/fr not_active Expired
- 1982-02-02 US US06/344,962 patent/US4562001A/en not_active Expired - Fee Related
- 1982-02-03 JP JP57015003A patent/JPS57178189A/ja active Pending
Also Published As
Publication number | Publication date |
---|---|
EP0057429A2 (fr) | 1982-08-11 |
US4562001A (en) | 1985-12-31 |
EP0057429A3 (en) | 1985-12-11 |
JPS57178189A (en) | 1982-11-02 |
CA1166027A (fr) | 1984-04-24 |
DE3103526C2 (de) | 1985-11-14 |
DE3103526A1 (de) | 1982-08-12 |
DE3279552D1 (en) | 1989-04-20 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
EP0057429B1 (fr) | Conteneur multi-couches pour le transport et le stockage de déchets radioactifs | |
EP0072429B1 (fr) | Conteneur pour le stockage à long terme de déchets radioactifs | |
EP0092679B1 (fr) | Conteneur pour matières radioactives | |
DE1521694A1 (de) | Zersetzbare Zinkanode | |
DE3027999A1 (de) | Verfahren zum herstellen eines gefaesses fuer kernbrennstoff und kernbrennstoffgefaess | |
DE3519438A1 (de) | Korrosionsschutzverfahren fuer ein rohr eines dampferzeugers und vorrichtung zur durchfuehrung dieses verfahrens | |
DE2527686C2 (de) | Kernbrennelement mit einem zylindrischen Behälter | |
EP0057867A1 (fr) | Conteneur multicouche pour le stockage efficace de longue durée de matériau radioactif | |
DE3346355C2 (de) | Behälter zur Endlagerung von radioaktiven Abfällen | |
EP0556455B1 (fr) | Conteneur de transport blindé pour éléments combustibles de réacteur nucléaire irradies et procédé de dépÔt d'une couche superficielle sur le conteneur de transport blindé | |
EP0057866B1 (fr) | Dispositif de protection contre la corrosion de récipients contenant des matières radioactives | |
EP0057430A1 (fr) | Récipient de transport et de stockage pour déchets radioactifs | |
DE3518799C2 (de) | Mehrschichten-Gleitlager | |
EP0062831B1 (fr) | Conteneur pour le stockage de longue durée de matières radioactives | |
DE19581642C2 (de) | Kalt- und Heißwasserzuführungs-Kupferlegierungsrohr mit einem Schutzfilm auf der inneren Oberfläche, Verfahren zu seiner Herstellung sowie ein Heißwasserzuführungs-Wärmeaustauscher | |
DE3610862C2 (fr) | ||
DE897742C (de) | Verfahren zur Herstellung radioaktiver Metallfolien und Draehte | |
DE3239813C2 (de) | Wärmetauscher | |
DE3716913C2 (fr) | ||
DE3103494C2 (de) | Behälter zur Lagerung radioaktiver Stoffe | |
DE3403599A1 (de) | Verfahren zum transportieren, zwischenlagern und endlagern von abgebrannten brennelementen, behaeltersystem zur durchfuehrung dieses verfahrens sowie herstellung eines behaelters fuer den transport und/oder lagerung von abgebrannten brennelementen | |
DE3006507A1 (de) | Stoerfallschutz fuer die lagerung selbsterhitzender radioaktiver stoffe | |
DE8111040U1 (de) | Behälter zur Langzeitlagerung von radioaktiven Stoffen (II) | |
DE8102695U1 (de) | Transport- und lagerbehaelter fuer radioaktive abfaelle | |
DE8032599U1 (de) | Behaelter zur lagerung radioaktiver stoffe |
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 |
|
AK | Designated contracting states |
Designated state(s): BE DE FR GB SE |
|
17P | Request for examination filed |
Effective date: 19820925 |
|
PUAL | Search report despatched |
Free format text: ORIGINAL CODE: 0009013 |
|
AK | Designated contracting states |
Designated state(s): BE DE FR GB SE |
|
17Q | First examination report despatched |
Effective date: 19870428 |
|
GRAA | (expected) grant |
Free format text: ORIGINAL CODE: 0009210 |
|
AK | Designated contracting states |
Kind code of ref document: B1 Designated state(s): BE DE FR GB SE |
|
GBT | Gb: translation of ep patent filed (gb section 77(6)(a)/1977) | ||
REF | Corresponds to: |
Ref document number: 3279552 Country of ref document: DE Date of ref document: 19890420 |
|
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: 19891213 Year of fee payment: 9 |
|
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 | ||
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: DE Effective date: 19911001 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: SE Payment date: 19911216 Year of fee payment: 11 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: BE Payment date: 19911224 Year of fee payment: 11 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: FR Payment date: 19911230 Year of fee payment: 11 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: GB Payment date: 19920117 Year of fee payment: 11 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: GB Effective date: 19930128 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: SE Effective date: 19930129 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: BE Effective date: 19930131 |
|
BERE | Be: lapsed |
Owner name: DEUTSCHE -G. FUR WIEDERAUFARBEITUNG VON KERNBRENN Effective date: 19930131 Owner name: NUKEM G.M.B.H.- Effective date: 19930131 |
|
GBPC | Gb: european patent ceased through non-payment of renewal fee |
Effective date: 19930128 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: FR Effective date: 19930930 |
|
REG | Reference to a national code |
Ref country code: FR Ref legal event code: ST |
|
EUG | Se: european patent has lapsed |
Ref document number: 82100591.5 Effective date: 19930810 |