EP0930620A1 - Lagerbehälter für die Zwischen- und/oder Endlagerung abgebrannter Brennelemente - Google Patents
Lagerbehälter für die Zwischen- und/oder Endlagerung abgebrannter Brennelemente Download PDFInfo
- Publication number
- EP0930620A1 EP0930620A1 EP98115126A EP98115126A EP0930620A1 EP 0930620 A1 EP0930620 A1 EP 0930620A1 EP 98115126 A EP98115126 A EP 98115126A EP 98115126 A EP98115126 A EP 98115126A EP 0930620 A1 EP0930620 A1 EP 0930620A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- storage container
- absorber
- backfill material
- neutron
- container according
- 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.)
- Granted
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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
-
- 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
- G21F1/00—Shielding characterised by the composition of the materials
Definitions
- the invention relates to a storage container for the intermediate and / or final storage of spent fuel elements, in particular uncompacted spent fuel elements, whereby at least one fuel assembly arranged in the storage container is, the cavities surrounding the fuel assemblies are filled with a backfill material.
- Fuel elements arranged in a bed of backfill material essentially from zeolite and / or activated carbon consists.
- Zeolite and activated carbon should not - or volatile radionuclides, especially radioactive Absorb iodine, cesium and strontium.
- the activated carbon will also act as a neutron moderator.
- the fill should also act as a mechanical buffer against the outside acting forces serve.
- the bed also added, for example, metal semolina to the To increase the thermal conductivity of the fill, so that effective dissipation of the decay heat of the fuel elements is achieved.
- the well-known storage container stands out by the disadvantage that both neutron absorption as well as neutron moderation and actinide absorption the bulk leaves something to be desired. This leads to, that in the known storage container more complex Shielding measures must be taken and for example realized a correspondingly thick container wall must have an adequate shielding effect to achieve.
- the manufacture of this storage container is material and costly. Otherwise take the known storage container due to the relatively thick outer walls a relatively high and therefore disadvantageous Storage volume.
- the invention is the technical problem based on a storage container of the type mentioned to indicate the in terms of neutron absorption, the Neutron moderation and actinide absorption all Requirements are sufficient and nonetheless not very complex can be trained.
- the invention teaches to solve this technical problem a storage container of the type mentioned, which thereby is characterized in that the backfill material 2 to 6 parts by weight a neutron absorber, 5 to 10 parts by weight a neutron moderator and 74 to 88 parts by weight of an actinide absorber.
- the individual components of the backfill material are expedient completely mixed together. So far is preferably the backfill material as essentially Homogeneous mixture contained in the storage container.
- the backfill material is expediently as dense as possible Bulk introduced into the storage container.
- the Cavities in which the backfill material is filled in essentially completely filled by the backfill material are expedient completely mixed together.
- a preferred embodiment within the scope of the invention is of particular importance is characterized by that the voids between fuel assemblies and container wall as well as the voids between the fuel assemblies are filled with the backfill material. So in the essentially all free spaces between the fuel elements and between the fuel elements and the storage container wall filled out.
- the invention is also of particular importance characterized in that the fuel assemblies in at least a primary container are arranged that the primary container is set in a secondary container and that the Cavities between the primary container outer wall and the secondary container inner wall filled with the backfill material are.
- at least a primary container the cavities between the fuel assemblies and the primary container wall and the cavities filled with the backfill between the fuel elements. It is within the scope of the invention that several such filled primary container in a secondary container be set and all gaps between the primary containers and between the primary containers and the secondary container wall filled with the backfill material are.
- the backfill material preferably additionally has Metal powder and / or metal granules for heat dissipation on. These metal components are also expedient essentially complete with the remaining ingredients of the backfill material mixed. It will preferably be a Metal with high thermal conductivity is used. It's in the frame the invention that the metal powder and / or metal granules is made of copper. Because preferably all Clearances between the fuel elements with the backfill material are filled out, the heat exchange is through Radiation within the fuel assemblies and within the Storage container prevented. The added good thermal conductivity Metal powder and / or metal granulate can compensate for this and effectively dissipate the heat.
- the backfill material has 5 to 10 parts by weight of the Metal powder and / or metal granules.
- boron carbide used as a neutron absorber Preferably Titanium hydride used as a neutron moderator.
- phosphate and / or sulfate-carrying actinide absorbers Minerals of the weathering cycle used.
- the backfill material has the following composition:
- Neutron absorber preferably boron carbide: 2 to 6% by weight, Neutron moderator, preferably titanium hydride: 5 to 10 % By weight and actinide absorber, preferably mineral Crandallitt group: 74 to 88% by weight.
- the filling material expediently also has 5 to 10% by weight of the metal powder and / or metal granules, preferably made of copper, on. - It goes without saying that the Weight percentages in each selected mix Add 100% by weight.
- the invention is based on the finding that a backfill material of the composition according to the invention a particularly effective neutron shielding, the is called neutron moderation and neutron absorption. On the other hand, there is also a very effective actinide absorption reached. Even if the storage container is damaged occur during transport or storage, the actinides are largely completely captured and immobilized. Surprisingly, with the invention Backfill material for all types of decay products or radionuclides completely in the storage container held back.
- the remarkable advantage is that additional complex Shields on the storage container are not required and in particular the shielding thickness of the storage container wall can be carried out relatively small.
- the backfill material according to the invention that from the outside of the storage container and the fuel assemblies acting forces are effectively intercepted and the Fuel elements from destruction by these external Powers are protected.
- the composition of the backfill material according to the invention also due to its excellent chemical compatibility out. Undesired chemical reactions do not take place.
- the figures show a storage container 1 for the intermediate and / or Final storage of spent uncompressed fuel elements 2.
- the fuel elements 2 arranged in a basket grid 3, the is set in the storage container 1.
- the fuel elements 2 surrounding cavities are with a backfill material 4 filled out.
- a storage container according to FIGS. 1 and 2 is preferably like filled with the filling material 4 according to the invention:
- the storage container 1 is in the reactor with the fuel elements 2 load, after which a primary cover 6 on the storage container 1 is applied. Through an opening 7 in the primary cover 6, the interior of the storage container is initially dried. Then preferably through the same opening 7 the backfill material 4 in the interior of the storage container 1 introduced.
- a suitable one is expedient for this Filling device and a metering device are provided.
- the opening 7 is expedient closed and then the storage container 1 with a secondary cover 8 tightly and permanently welded.
- the backfill material consists of boron carbide, titanium hydride, a mineral mixture of crandallite, woodhouse and and / or Alunite group and copper powder.
- 3 and 4 show a further embodiment of the storage container according to the invention 1.
- the fuel elements 2 are arranged in a primary container 9. 3 and 4 in the exemplary embodiment the primary container the storage container 1, which in the 1 and 2 is shown and is this primary container 9 has been filled in the same way described. It however, it is also within the scope of the invention that Embodiment of the primary container 9 only the fuel elements 2 records without using the invention Filling material 4 to be filled.
- the primary container 9 is in one Secondary container 10 set.
- the voids between Primary container outer wall 11 and secondary container inner wall 12 are with the backfill material 4 according to the invention filled out.
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)
- Solid Fuels And Fuel-Associated Substances (AREA)
Abstract
Description
- Fig. 1
- einen erfindungsgemäßen Lagerbehälter in einer ersten Ausführungsform,
- Fig. 2
- ein Querschnitt A-A durch den Gegenstand nach Fig. 1,
- Fig. 3
- den Gegenstand nach Fig. 1 in einer anderen Ausführungsform,
- Fig. 4
- einen Querschnitt B-B durch den Gegenstand nach Fig. 3.
Claims (10)
- Lagerbehälter (1) für die Zwischen- und/oder Endlagerung abgebrannter Brennelemente (2), insbesondere unverdichteter abgebrannter Brennelemente (2), wobei zumindest ein Brennelement (2) in dem Lagerbehälter (1) angeordnet ist,
wobei die die Brennelemente (2) umgebenden Hohlräume mit einem Verfüllmaterial (4) ausgefüllt sind, dadurch gekennzeichnet,
daß das Verfüllmaterial (4) 2 bis 6 Gewichtsanteile eines Neutronenabsorbers, 5 bis 10 Gewichtsanteile eines Neutronenmoderators und 74 bis 88 Gewichtsanteile eines Aktinidenabsorbers aufweist. - Lagerbehälter nach Anspruch 1, dadurch gekennzeichnet, daß die Hohlräume zwischen den Brennelementen (2) und der Behälterwandung (5) sowie die Hohlräume zwischen den Brennelementen (2) mit dem Verfüllmaterial (4) ausgefüllt sind.
- Lagerbehälter nach Anspruch 1, dadurch gekennzeichnet, daß die Brennelemente (2) in zumindest einem Primärbehälter (9) angeordnet sind, daß der Primärbehälter (9) in einen Sekundärbehälter (10) eingestellt ist und daß die Hohlräume zwischen Primärbehälteraußenwandung (11) und Sekundärbehälterinnenwandung (12) mit dem Verfüllmaterial (4) ausgefüllt sind.
- Lagerbehälter nach einem der Ansprüche 1 bis 3, dadurch gekennzeichnet, daß das Verfüllmaterial (4) zusätzlich ein Metallpulver und/oder Metallgranulat zur Wärmeableitung aufweist.
- Lagerbehälter nach Anspruch 4, dadurch gekennzeichnet, daß das Metallpulver und/oder Metallgranulat aus Kupfer besteht.
- Lagerbehälter nach einem der Ansprüche 4 oder 5, dadurch gekennzeichnet, daµ das Verfüllmaterial (4) 5 bis 10 Gewichtsanteile des Metallpulvers und/oder Metallgranulates aufweist.
- Lagerbehälter nach einem der Ansprüche 1 bis 6, dadurch gekennzeichnet, daß Borcarbid als Neutronenabsorber eingesetzt ist.
- Lagerbehälter nach einem der Ansprüche 1 bis 7, dadurch gekennzeichnet, daß Titanhydrid als Neutronenmoderator eingesetzt ist.
- Lagerbehälter nach einem der Ansprüche 1 bis 8, dadurch gekennzeichnet, daß als Aktinidenabsorber phosphat- und/oder sulfatführende Minerale des Verwitterungskreislaufes eingesetzt sind.
- Lagerbehälter nach einem der Ansprüche 1 bis 9, dadurch gekennzeichnet, daß als Aktinidenabsorber ein Mineralgemenge der Crandallit-, Woodhouseit- und/oder Alunit-Gruppe eingesetzt ist.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CZ19984236A CZ289908B6 (cs) | 1997-12-24 | 1998-12-18 | Skladovací nádoba pro meziskladování a/nebo konečné skladování vyhořelých palivových článků |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE1997157843 DE19757843C1 (de) | 1997-12-24 | 1997-12-24 | Lagerbehälter für die Zwischen- und/oder Endlagerung abgebrannter Brennelemente |
DE19757843 | 1997-12-24 |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0930620A1 true EP0930620A1 (de) | 1999-07-21 |
EP0930620B1 EP0930620B1 (de) | 2002-02-27 |
Family
ID=7853362
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP19980115126 Expired - Lifetime EP0930620B1 (de) | 1997-12-24 | 1998-08-12 | Lagerbehälter für die Zwischen- und/oder Endlagerung abgebrannter Brennelemente |
Country Status (3)
Country | Link |
---|---|
EP (1) | EP0930620B1 (de) |
DE (1) | DE19757843C1 (de) |
ES (1) | ES2172068T3 (de) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE102004049236B4 (de) * | 2004-10-09 | 2006-07-13 | GNS Gesellschaft für Nuklear-Service mbH | Transport- und/oder Lagerbehälter für Brennelemente |
DE102004059216B3 (de) * | 2004-12-09 | 2006-06-01 | Forschungszentrum Karlsruhe Gmbh | Verfahren zur Einlagerung radioaktiver Reststoffe, Behälter dafür und seine Verwendung |
Citations (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3832563A (en) * | 1972-08-07 | 1974-08-27 | B Dubovsky | Apparatus for storing and processing fissionable substances |
GB2038227A (en) * | 1978-12-29 | 1980-07-23 | Nuklear Service Gmbh Gns | Transport and/or storage container for radioactive wastes from nuclear power stations |
DE2943934A1 (de) * | 1979-10-31 | 1981-05-14 | Nukem Gmbh, 6450 Hanau | Verfahren zur lagerung von kugelfoermigen brennelementen |
DE3005466A1 (de) * | 1980-02-14 | 1981-08-20 | Steag Kernenergie Gmbh, 4300 Essen | Vorrichtung fuer die lagerung radioaktiver substanzen |
US4399366A (en) * | 1981-04-24 | 1983-08-16 | Bucholz James A | Separator assembly for use in spent nuclear fuel shipping cask |
JPS63140997A (ja) * | 1986-12-03 | 1988-06-13 | 株式会社日立製作所 | 燃料輸送容器 |
EP0520438A1 (de) * | 1991-06-28 | 1992-12-30 | Westinghouse Electric Corporation | Metallhydrid-Neutronenabsorberanordnung für Kernbrennstofflagerbehälter |
DE19545761A1 (de) * | 1995-12-07 | 1997-06-12 | Siemens Ag | Behälter mit einem radioaktiven Körper |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB1105957A (en) * | 1964-11-27 | 1968-03-13 | English Electric Co Ltd | Radiation shielding materials |
DE3107505A1 (de) * | 1981-02-27 | 1982-09-16 | Steag Kernenergie Gmbh, 4300 Essen | Vorrichtung zum lagern radioaktiver substanzen mit einer mehrzahl einen korrosionsschutzmantel aufweisenden gleichen innenbehaeltern und einem die behaelter in einem paket zusammenhaltenden mantel |
DE3542640C1 (de) * | 1985-12-03 | 1987-01-15 | Nukem Gmbh | Verfahren zur Abtrennung von Kationen aus waessrigen Loesungen |
-
1997
- 1997-12-24 DE DE1997157843 patent/DE19757843C1/de not_active Expired - Lifetime
-
1998
- 1998-08-12 ES ES98115126T patent/ES2172068T3/es not_active Expired - Lifetime
- 1998-08-12 EP EP19980115126 patent/EP0930620B1/de not_active Expired - Lifetime
Patent Citations (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3832563A (en) * | 1972-08-07 | 1974-08-27 | B Dubovsky | Apparatus for storing and processing fissionable substances |
GB2038227A (en) * | 1978-12-29 | 1980-07-23 | Nuklear Service Gmbh Gns | Transport and/or storage container for radioactive wastes from nuclear power stations |
DE2943934A1 (de) * | 1979-10-31 | 1981-05-14 | Nukem Gmbh, 6450 Hanau | Verfahren zur lagerung von kugelfoermigen brennelementen |
DE3005466A1 (de) * | 1980-02-14 | 1981-08-20 | Steag Kernenergie Gmbh, 4300 Essen | Vorrichtung fuer die lagerung radioaktiver substanzen |
US4399366A (en) * | 1981-04-24 | 1983-08-16 | Bucholz James A | Separator assembly for use in spent nuclear fuel shipping cask |
JPS63140997A (ja) * | 1986-12-03 | 1988-06-13 | 株式会社日立製作所 | 燃料輸送容器 |
EP0520438A1 (de) * | 1991-06-28 | 1992-12-30 | Westinghouse Electric Corporation | Metallhydrid-Neutronenabsorberanordnung für Kernbrennstofflagerbehälter |
DE19545761A1 (de) * | 1995-12-07 | 1997-06-12 | Siemens Ag | Behälter mit einem radioaktiven Körper |
Non-Patent Citations (1)
Title |
---|
DATABASE WPI Section Ch Week 8829, Derwent World Patents Index; Class K07, AN 88-202498, XP002097482 * |
Also Published As
Publication number | Publication date |
---|---|
DE19757843C1 (de) | 1999-08-12 |
ES2172068T3 (es) | 2002-09-16 |
EP0930620B1 (de) | 2002-02-27 |
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