DE3144113A1 - Concrete shielding housing for dry interim storage of fuel element containers - Google Patents
Concrete shielding housing for dry interim storage of fuel element containersInfo
- Publication number
- DE3144113A1 DE3144113A1 DE19813144113 DE3144113A DE3144113A1 DE 3144113 A1 DE3144113 A1 DE 3144113A1 DE 19813144113 DE19813144113 DE 19813144113 DE 3144113 A DE3144113 A DE 3144113A DE 3144113 A1 DE3144113 A1 DE 3144113A1
- Authority
- DE
- Germany
- Prior art keywords
- container
- fuel element
- fuel
- concrete
- interim storage
- 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
- 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
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)
Abstract
Description
VORRICHTUNG ZUR TROCKENEN ZWISCHENLAGERUNG VON ABGEBRANNTENDEVICE FOR DRY INTERMEDIATE STORAGE OF COMBUSTED
KERNREAKTORBRENNELEMENTEN Die Erfindung betrifft eine Vorrichtung zur trockenen Zwischenlagerung von abgebrannten Kernreaktdrbrennelementen mit einem die Brennelemente aufnehmenden Brennelementbehälter und einem den Brennelementbehälter umschließenden Betonschutzbehälter, wobei die lichten Maße des Betonschutzbehälters etwas größer als die Außenabmessungen des Brennelementbehälters sind.NUCLEAR REACTOR FUEL ELEMENTS The invention relates to an apparatus for the dry interim storage of spent nuclear reactor fuel elements with a the fuel element receiving the fuel element container and a fuel element container enclosing concrete protective container, with the clear dimensions of the concrete protective container are slightly larger than the outer dimensions of the fuel assembly.
Bei den Bemühungen, Brennelementbehälter im Freien zwischenzulagern,wurde bereits vorgeschlagen, die Brennelementbehälter in Silobehälter aus Beton oder Stahlbeton einzubringen. Bei einem nicht vorveröffentlichten Vorschlag zur Ausbildung eines derartigen Betonschutzbehälters weist der Schutzbehälter seitliche Zuluftkanäle am unteren Mantelrand und seitliche Abluftkanäle im Bereich des oberen Mantelrandes unterhalb des Deckels auf. Der Fuß des Schutzbehälters ist als separat unterfahrbare Palette ausgebildet, auf die der Brennelementbehälter und darüber der Betonschutzmantel des Betonschutzbehälters aufsetzbar sind (Patentanmeldung P 30 17 767.4). Durch die Anordnung der Zuluft- und Abluftkanäle wird innerhalb der Vorrichtung zur trockenen Zwischenlagerung eine Naturzugbelüftung erreicht, die zur Abfuhr der Nachzerfallswärme dient.In the course of efforts to store fuel assembly containers outdoors, already proposed, the fuel assembly containers in silo made of concrete or reinforced concrete bring in. In the case of a proposal for training a Such a concrete protective container, the protective container has lateral air supply channels at the lower edge of the jacket and lateral exhaust air ducts in the area of the upper jacket edge underneath the lid. The foot of the protective container can be accessed separately Pallet formed on which the fuel assembly container and above the protective concrete jacket of the concrete protection container can be attached (patent application P 30 17 767.4). By the arrangement of the supply air and exhaust air ducts is dry within the device Intermediate storage achieves natural draft ventilation, which is used to dissipate the decay heat serves.
Der Erfindung liegt die Aufgabe zugrunde, eine Vorrichtung zur trockenen Zwischenlagerung von abgebrannten Kernreaktorbrennelementen zu schaffen, bei der die Abfuhr der Nachzerfallswärme durch natürliche Konvektion verbessert ist.The invention is based on the object of a device for dry To create interim storage of spent nuclear reactor fuel elements in the the dissipation of decay heat is improved by natural convection.
Die Aufgabe wird erfindungsgemäß dadurch gelöst, daß der Brennelementbehälter auf seiner Oberfläche achsial verlaufende, radial abstehende Längsrippen aufweist, deren Enden mit geringem Abstand zur Innenfläche des Betonschutzbehälters liegen.The object is achieved according to the invention in that the fuel assembly container has axially extending, radially protruding longitudinal ribs on its surface, the ends of which are at a small distance from the inner surface of the concrete protection container.
Die Vorrichtung weist einen Brennelementbehälter mit achsialen Längsrippen auf, die einer guten Wärmeabgabe dienen.The device has a fuel element container with axial longitudinal ribs that serve a good heat dissipation.
Diese Längsrippen bilden nun mit dem im geringen Abstand angeordneten Betonschutzmantel eine Vielzahl von senkrechten Luftzügen. Dadurch wird ein äußerst günstiges Bestreichen der Längsrippen durch die aufsteigende Luft erreicht.These longitudinal ribs now form with the arranged at a small distance Concrete protective jacket a variety of vertical drafts. This becomes an extremely favorable coating of the longitudinal ribs achieved by the rising air.
Eine sehr gute Wärmeabgabe an den aufsteigenden Luftstrom ist die Folge.A very good heat transfer to the rising air stream is that Episode.
Anhand der Zeichnung wird nachstehend ein Ausführungsbeispiel der Erfindung näher erläutert. Es zeigt Fig. 1 einen Betonschutzbehälter im Schnitt gemäß Linie I - I in Fig. 2 und Fig. 2 eine geschnittene Draufsicht der Vorrichtung gemäß Linie II - II in Fig. 1.Based on the drawing, an embodiment of the Invention explained in more detail. It shows Fig. 1 a concrete protection container in section according to line I - I in Fig. 2 and Fig. 2 is a sectional plan view of the device according to line II - II in FIG. 1.
Der Betonschutzbehälter 3 besteht aus einem palettenartig ausgebildeten Fußteil 4, einem darauf aufgesetzten zylindrischen Betonschutzmantel 5 und einem auf dem Betonschutzmantel 5 liegenden zylindrischen Deckel 6.The concrete protective container 3 consists of a pallet-like Foot part 4, a cylindrical concrete protective jacket 5 and one placed thereon A cylindrical cover 6 lying on the protective concrete casing 5.
Das Fußteil 4 besteht aus einer quadratischen Bodenplatte 7, an deren Ecken jeweils ein Fuß 8 angeordnet ist, so daß das Fußteil 4 als unterfahrbare Palette ausgebildet ist.The foot part 4 consists of a square base plate 7, at which Corners each have a foot 8 is arranged, so that the foot part 4 as a pallet that can be driven under is trained.
Die Bodenplatte 7 weist eine zentrisch. angeordnete, kreisförmige,erhobene Stellfläche 9 auf. Der. Durchmesser der Stell fläche 9 ist kleiner als der lichte Durchmesser des zylinderförmigen Betonschutzmantels 5, der auf das Fußteil 4 aufgesetzt ist.The bottom plate 7 has a centrally. arranged, circular, raised Footprint 9 on. Of the. The diameter of the footprint 9 is smaller than the clear Diameter of the cylindrical concrete protective jacket 5, which is placed on the foot part 4 is.
Der Betonschutzmantel 5 weist an seinem unteren Ende Ausnehmungen 11 auf, die als Zuluftkanäle dienen. Der auf dem Betonschutzmantel 5 liegende Deckel 6 weist im Randbereich auf seiner dem Betonschutzmantel 5 zugewandten Fläche ebenfalls Ausnehmungen 12 auf, die als Abluftkanäle dienen.The concrete protective jacket 5 has recesses at its lower end 11, which serve as supply air ducts. The cover lying on the protective concrete jacket 5 6 also points in the edge area on its surface facing the concrete protective casing 5 Recesses 12, which serve as exhaust ducts.
Auf der Stellfläche 9 des Fußteiles 4 ist ein hier unbeladen dargestellter Brennelementbehälter 13 aufrechtstehend angeordnet. Dieser Brennelementbehälter 13 weist einen dickwandigen Behältergrundkörper 14 auf, in dessen Wandung sich achsiale Bohrungen 15 befinden, die mit Kunststoffstäbe zur Neutronenabschirmung gefüllt sind. Der Behältergrundkörper 14 ist an einem Ede offen und stufenfförmig erweitert.On the footprint 9 of the foot part 4 one is unloaded here depicted Fuel element container 13 arranged upright. This fuel assembly container 13 has a thick-walled container base body 14, in the wall of which axially Bores 15 are located, which are filled with plastic rods for neutron shielding are. The container base body 14 is open at one end and widened in a stepped manner.
In diesen inneren Stufen ist ein Mehrfachdeckelsystem 16 zum gasdichten Verschluß des Brennelementbehälters 13 angeordnet.In these inner steps is a multiple cover system 16 for gas-tight Closure of the fuel assembly container 13 is arranged.
In an sich bekannter Weise weist der Brennelementbehälter 13 auf seiner zylinderförmigen Außenoberfläche achsial verlaufende Kühlrippen 17 auf, die eine vergrößerte:Oberfläche der Behälterwandung zur Abfuhr der Nachzerfallswärme an die Umgebungsluft darstellen. Wie aus der Fig. 2 ersichtlich wird, reichen die Enden der Kühlrippen 17 bis dicht an die Innenfläche des zylindrischen Betonschutzmantels 5. Es entstehen so zwischen den einzelnen Kühlrippen 17 und der abdeckenden Betonschutzwand 5 einzelne Luftkanäle 18, durch die die aufsteigende Luft zwangsweise geführt wird.In a manner known per se, the fuel assembly container 13 has on its cylindrical outer surface axially extending cooling fins 17, the one enlarged: surface of the container wall to dissipate the decay heat to the Represent ambient air. As can be seen from FIG. 2, the ends are sufficient of the cooling fins 17 to close to the inner surface of the cylindrical concrete protective jacket 5. This creates between the individual cooling fins 17 and the concrete protective wall that covers it 5 individual air channels 18 through which the rising air is forcibly guided.
Durch die beschriebene-Ausbildung wird verhindert, daß sich in der aufsteigenden Kühlluft Trennschichten bilden, die nicht direkt mit der Behälterwand bzw. den Kühlrippen 17 in Kontakt kommen. Die gesamte aufgrund der natürlichen Konvektion vorbeistreichende Kühlluftmenge wird zur Abführung der Nachzerfallswärme optimal ausgenutzt.The training described prevents it from being in the ascending cooling air forms separating layers that are not directly connected to the container wall or the cooling fins 17 come into contact. The whole due to natural convection The amount of cooling air that passes by is optimal for dissipating the decay heat exploited.
LeerseiteBlank page
Claims (1)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19813144113 DE3144113A1 (en) | 1981-11-06 | 1981-11-06 | Concrete shielding housing for dry interim storage of fuel element containers |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19813144113 DE3144113A1 (en) | 1981-11-06 | 1981-11-06 | Concrete shielding housing for dry interim storage of fuel element containers |
Publications (1)
Publication Number | Publication Date |
---|---|
DE3144113A1 true DE3144113A1 (en) | 1983-05-19 |
Family
ID=6145780
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DE19813144113 Ceased DE3144113A1 (en) | 1981-11-06 | 1981-11-06 | Concrete shielding housing for dry interim storage of fuel element containers |
Country Status (1)
Country | Link |
---|---|
DE (1) | DE3144113A1 (en) |
Cited By (22)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6718000B2 (en) * | 2002-02-06 | 2004-04-06 | Holtec International, Inc. | Ventilated vertical overpack |
US7068748B2 (en) | 2004-03-18 | 2006-06-27 | Holtec International, Inx. | Underground system and apparatus for storing spent nuclear fuel |
US7330526B2 (en) | 2005-03-25 | 2008-02-12 | Holtec International, Inc. | System and method of storing high level waste |
US7590213B1 (en) | 2004-03-18 | 2009-09-15 | Holtec International, Inc. | Systems and methods for storing spent nuclear fuel having protection design |
US7676016B2 (en) | 2005-02-11 | 2010-03-09 | Holtec International, Inc. | Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment |
US7994380B2 (en) | 2006-10-11 | 2011-08-09 | Holtec International, Inc. | Apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow |
US8098790B2 (en) | 2004-03-18 | 2012-01-17 | Holtec International, Inc. | Systems and methods for storing spent nuclear fuel |
DE102012106921A1 (en) * | 2012-07-30 | 2014-01-30 | Steag Energy Services Gmbh | Container system for the disposal of radioactive non-heat-generating waste |
US8660230B2 (en) | 2007-12-22 | 2014-02-25 | Holtec International, Inc. | System and method for the ventilated storage of high level radioactive waste in a clustered arrangement |
US8718220B2 (en) | 2005-02-11 | 2014-05-06 | Holtec International, Inc. | Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment |
US8798224B2 (en) | 2009-05-06 | 2014-08-05 | Holtec International, Inc. | Apparatus for storing and/or transporting high level radioactive waste, and method for manufacturing the same |
US8905259B2 (en) | 2010-08-12 | 2014-12-09 | Holtec International, Inc. | Ventilated system for storing high level radioactive waste |
US9001958B2 (en) | 2010-04-21 | 2015-04-07 | Holtec International, Inc. | System and method for reclaiming energy from heat emanating from spent nuclear fuel |
US9105365B2 (en) | 2011-10-28 | 2015-08-11 | Holtec International, Inc. | Method for controlling temperature of a portion of a radioactive waste storage system and for implementing the same |
US9208914B2 (en) | 2009-11-05 | 2015-12-08 | Holtec International | System, method and apparatus for providing additional radiation shielding to high level radioactive materials |
US9443625B2 (en) | 2005-03-25 | 2016-09-13 | Holtec International, Inc. | Method of storing high level radioactive waste |
US9514853B2 (en) | 2010-08-12 | 2016-12-06 | Holtec International | System for storing high level radioactive waste |
US10811154B2 (en) | 2010-08-12 | 2020-10-20 | Holtec International | Container for radioactive waste |
US10892063B2 (en) | 2012-04-18 | 2021-01-12 | Holtec International | System and method of storing and/or transferring high level radioactive waste |
US11373774B2 (en) | 2010-08-12 | 2022-06-28 | Holtec International | Ventilated transfer cask |
US11569001B2 (en) | 2008-04-29 | 2023-01-31 | Holtec International | Autonomous self-powered system for removing thermal energy from pools of liquid heated by radioactive materials |
US11887744B2 (en) | 2011-08-12 | 2024-01-30 | Holtec International | Container for radioactive waste |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2915376A1 (en) * | 1979-04-14 | 1980-10-23 | Transnuklear Gmbh | CONTAINER OF CONTAINERS FOR TRANSPORTATION AND STORAGE OF RADIOACTIVE WASTE MATERIALS, IN PARTICULAR IRRADIATED NUCLEAR REACTOR FUEL ELEMENTS |
DE8012618U1 (en) * | 1980-05-09 | 1981-11-05 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | DEVICE FOR RECEIVING, TRANSPORTING AND RADIATING SHIELDING OF CONTAINERS LOADED WITH BURNED REACTOR FUEL ELEMENTS |
-
1981
- 1981-11-06 DE DE19813144113 patent/DE3144113A1/en not_active Ceased
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2915376A1 (en) * | 1979-04-14 | 1980-10-23 | Transnuklear Gmbh | CONTAINER OF CONTAINERS FOR TRANSPORTATION AND STORAGE OF RADIOACTIVE WASTE MATERIALS, IN PARTICULAR IRRADIATED NUCLEAR REACTOR FUEL ELEMENTS |
DE8012618U1 (en) * | 1980-05-09 | 1981-11-05 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | DEVICE FOR RECEIVING, TRANSPORTING AND RADIATING SHIELDING OF CONTAINERS LOADED WITH BURNED REACTOR FUEL ELEMENTS |
Cited By (40)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6718000B2 (en) * | 2002-02-06 | 2004-04-06 | Holtec International, Inc. | Ventilated vertical overpack |
US8098790B2 (en) | 2004-03-18 | 2012-01-17 | Holtec International, Inc. | Systems and methods for storing spent nuclear fuel |
US7068748B2 (en) | 2004-03-18 | 2006-06-27 | Holtec International, Inx. | Underground system and apparatus for storing spent nuclear fuel |
US9916911B2 (en) | 2004-03-18 | 2018-03-13 | Holtec International, Inc. | Systems and methods for storing spent nuclear fuel |
US7590213B1 (en) | 2004-03-18 | 2009-09-15 | Holtec International, Inc. | Systems and methods for storing spent nuclear fuel having protection design |
US8625732B2 (en) | 2004-03-18 | 2014-01-07 | Holtec International, Inc. | Systems and methods for storing spent nuclear fuel |
US11342091B2 (en) | 2004-03-18 | 2022-05-24 | Holtec International | Systems and methods for storing spent nuclear fuel |
US7676016B2 (en) | 2005-02-11 | 2010-03-09 | Holtec International, Inc. | Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment |
US11264142B2 (en) | 2005-02-11 | 2022-03-01 | Holtec International | Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment |
US10614924B2 (en) | 2005-02-11 | 2020-04-07 | Holtec International | Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment |
US8718220B2 (en) | 2005-02-11 | 2014-05-06 | Holtec International, Inc. | Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment |
US9761339B2 (en) | 2005-02-11 | 2017-09-12 | Holtec International, Inc. | Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment |
US8351562B2 (en) | 2005-03-25 | 2013-01-08 | Holtec International, Inc. | Method of storing high level waste |
US7933374B2 (en) | 2005-03-25 | 2011-04-26 | Holtec International, Inc. | System and method of storing and/or transferring high level radioactive waste |
US9443625B2 (en) | 2005-03-25 | 2016-09-13 | Holtec International, Inc. | Method of storing high level radioactive waste |
US11250963B2 (en) | 2005-03-25 | 2022-02-15 | Holtec International | Nuclear fuel storage facility |
US10373722B2 (en) | 2005-03-25 | 2019-08-06 | Holtec International | Nuclear fuel storage facility with vented container lids |
US7330526B2 (en) | 2005-03-25 | 2008-02-12 | Holtec International, Inc. | System and method of storing high level waste |
US8415521B2 (en) | 2006-10-11 | 2013-04-09 | Holtec International, Inc. | Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials |
US7994380B2 (en) | 2006-10-11 | 2011-08-09 | Holtec International, Inc. | Apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow |
US8067659B2 (en) | 2006-10-11 | 2011-11-29 | Holtec International, Inc. | Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage |
US9460821B2 (en) | 2007-12-22 | 2016-10-04 | Holtec International, Inc. | System and method for the ventilated storage of high level radioactive waste in a clustered arrangement |
US8660230B2 (en) | 2007-12-22 | 2014-02-25 | Holtec International, Inc. | System and method for the ventilated storage of high level radioactive waste in a clustered arrangement |
US11569001B2 (en) | 2008-04-29 | 2023-01-31 | Holtec International | Autonomous self-powered system for removing thermal energy from pools of liquid heated by radioactive materials |
US10332642B2 (en) | 2009-05-06 | 2019-06-25 | Holtec International | Apparatus for storing and/or transporting high level radioactive waste, and method for manufacturing the same |
US8798224B2 (en) | 2009-05-06 | 2014-08-05 | Holtec International, Inc. | Apparatus for storing and/or transporting high level radioactive waste, and method for manufacturing the same |
US9208914B2 (en) | 2009-11-05 | 2015-12-08 | Holtec International | System, method and apparatus for providing additional radiation shielding to high level radioactive materials |
US9001958B2 (en) | 2010-04-21 | 2015-04-07 | Holtec International, Inc. | System and method for reclaiming energy from heat emanating from spent nuclear fuel |
US10418136B2 (en) | 2010-04-21 | 2019-09-17 | Holtec International | System and method for reclaiming energy from heat emanating from spent nuclear fuel |
US10217537B2 (en) | 2010-08-12 | 2019-02-26 | Holtec International | Container for radioactive waste |
US8905259B2 (en) | 2010-08-12 | 2014-12-09 | Holtec International, Inc. | Ventilated system for storing high level radioactive waste |
US10811154B2 (en) | 2010-08-12 | 2020-10-20 | Holtec International | Container for radioactive waste |
US9514853B2 (en) | 2010-08-12 | 2016-12-06 | Holtec International | System for storing high level radioactive waste |
US11373774B2 (en) | 2010-08-12 | 2022-06-28 | Holtec International | Ventilated transfer cask |
US9293229B2 (en) | 2010-08-12 | 2016-03-22 | Holtec International, Inc. | Ventilated system for storing high level radioactive waste |
US11887744B2 (en) | 2011-08-12 | 2024-01-30 | Holtec International | Container for radioactive waste |
US9105365B2 (en) | 2011-10-28 | 2015-08-11 | Holtec International, Inc. | Method for controlling temperature of a portion of a radioactive waste storage system and for implementing the same |
US10892063B2 (en) | 2012-04-18 | 2021-01-12 | Holtec International | System and method of storing and/or transferring high level radioactive waste |
US11694817B2 (en) | 2012-04-18 | 2023-07-04 | Holtec International | System and method of storing and/or transferring high level radioactive waste |
DE102012106921A1 (en) * | 2012-07-30 | 2014-01-30 | Steag Energy Services Gmbh | Container system for the disposal of radioactive non-heat-generating waste |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
DE3144113A1 (en) | Concrete shielding housing for dry interim storage of fuel element containers | |
EP0078988B1 (en) | Concrete protection container for the storage of fuel-element receptacles | |
EP0079469B1 (en) | Concrete protection container for the storage of fuel-element receptacles | |
DE3645230C2 (en) | ||
DE3212707A1 (en) | TRANSPORT AND STORAGE CONTAINER FOR FUEL FUEL | |
DE1173997B (en) | Fuel use | |
DE3139823C2 (en) | Fuel bundle | |
CH664037A5 (en) | SYSTEM WITH A NUCLEAR HEATING REACTOR. | |
DE1539821B2 (en) | HILL-SHAPED FUEL ELEMENT FOR A NUCLEAR REACTOR | |
CH658535A5 (en) | FUEL CARTRIDGE WITH A REFRIGERANT TUBE. | |
DE69010842T2 (en) | Nuclear fuel bundle for a boiling water reactor. | |
EP0079475B1 (en) | Concrete protection container for the storage of fuel-element receptacles | |
DE2632466A1 (en) | THERMAL INSULATION DEVICE FOR A CONTAINER | |
DE69018195T2 (en) | Nuclear fuel bundle for a boiling water reactor. | |
DE1589662B2 (en) | NUCLEAR FUEL ELEMENT | |
DE1464284A1 (en) | Nuclear reactor | |
CH649224A5 (en) | FILTERS FOR SEPARATING SOLID POLLUTANTS FROM A LIQUID, IN PARTICULAR SOLID POLLUTANTS FROM THE REACTOR COOLING WATER OF NUCLEAR POWER PLANTS. | |
DE2919797C2 (en) | Storage facility for the storage of spent fuel | |
DE69206757T2 (en) | Spacers for nuclear reactor fuel bundles | |
EP0102562B1 (en) | Storage container for solutions of fission products | |
DE3345099A1 (en) | LIQUID-COOLED CORE REACTOR, ESPECIALLY BOILING WATER REACTOR | |
DE2319025C2 (en) | Nuclear fuel element | |
DE3306940A1 (en) | FUEL TRANSPORT CONTAINER | |
DE3144117A1 (en) | Concrete shielding housing for dry interim storage of fuel element containers | |
DE2338413A1 (en) | REACTOR CORE |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
8110 | Request for examination paragraph 44 | ||
8131 | Rejection |