EP0036982A1 - Housing for radioactive materials in transport and/or storage containers - Google Patents
Housing for radioactive materials in transport and/or storage containers Download PDFInfo
- Publication number
- EP0036982A1 EP0036982A1 EP81101812A EP81101812A EP0036982A1 EP 0036982 A1 EP0036982 A1 EP 0036982A1 EP 81101812 A EP81101812 A EP 81101812A EP 81101812 A EP81101812 A EP 81101812A EP 0036982 A1 EP0036982 A1 EP 0036982A1
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- EP
- European Patent Office
- Prior art keywords
- insert basket
- basket according
- insert
- graphite
- matrix
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- 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.)
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- 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 present invention relates to a removable insert basket with shafts for radioactive material, in particular for receiving spent fuel elements from nuclear reactors, located in a transport and / or storage container.
- an insert basket is normally required in order to accommodate several spent fuel elements from nuclear reactors in the container at a predetermined distance from one another during transport or also during storage.
- the respective necessary fuel element positions are therefore designed as corresponding shafts into which the fuel elements are introduced.
- the shape and dimensions of the shaft cross-section depend on the fuel element types to be inserted.
- the fuel assemblies must be able to be brought in and out remotely with ease.
- the insert basket must be sufficiently stable so that it can withstand the mechanical and thermal loads during transport. It must also be designed so that the fuel assemblies to be transported are not damaged during transport and handling.
- Such insert baskets are usually designed as a pure steel frame or as a solid block made of non-ferrous metal.
- the shafts of the massive blocks are machine-made. If necessary, they are lined with steel.
- the massive non-ferrous. Constructions are suitable as insert baskets because they can dissipate the residual heat generated due to good heat conduction to the tank wall without auxiliary medium. They preferably consist of aluminum or copper or their alloys. Boron or cadmium can also be added to these alloys as a neutron absorber.
- the previously known insert baskets have a number of disadvantages. They have a high weight because they are predominantly made of metal due to the required thermal conductivity. In some cases, especially in the case of special steel frames, water cooling which is disadvantageous in the event of an accident is required. Only a small part of the neutron shielding is provided by the baskets, the main shielding effect is ensured by a special neutron protection on the shielding transport or storage container. At accidents, eg fire, this neutron protection can be destroyed on the shielding container.
- the object was achieved in that the matrix of the insert basket consists predominantly of graphite.
- FIG. 1 shows a side view of the insert basket according to the invention and illustration II the corresponding top view.
- Figure III shows the structure of the insert basket made of building blocks according to the invention, with and without metal disks,
- Figure IV the cup-shaped design of the metal disks and a tie rod arrangement, and
- a removable insert basket (4) which contains shafts (6) for receiving radioactive material, in particular for receiving spent fuel elements.
- the matrix (5) of the insert korbes (4) consists of graphite, a light and under normal conditions flame-retardant material with good heat conduction properties and excellent neutron moderation qualities.
- the graphite of the graphite matrix (5) is preferably compressed, for example by pressing or other known methods, and then, if necessary, processed by turning, milling and drilling. It has proved to be particularly advantageous that the shafts (6) and / or the outer surface of the E insatzkorbes (4) metallic neutron-absorbing linings (7, 10).
- These linings can be tubes with corresponding cross-sectional profiles (23, 24) or a basket container (10) which is provided with a cover (21).
- the cover (21) contains openings (25) through which the radioactive material can be introduced into the shafts (6).
- the insert basket (4) according to the invention is closed with a lid (11).
- the use of boron steel as the lining (7) of the shafts (6), the basket container (10) and the cover (21) is particularly favorable, as is the addition of boron carbide to the matrix graphite (5). This improves n-capture and increases criticality security.
- the graphite matrix (5) is advantageously constructed from appropriately shaped building blocks (8, 14, 15, 16, 22), a disk-shaped building block shape (8) having proven to be particularly favorable.
- metal disks (9) between the graphite disks (8).
- the metal discs (9) also be made of neutron absorbing material.
- a particularly advantageous modification is the design of the metal disks (9) as a pot shape (12), in which the graphitic building blocks (8, 14, 15, 16, 22) are protected on all sides.
- the basket container (10) can be omitted.
- the insert basket (4) consists of a strong base plate (26) on which the linings (7) for the shafts (6) are fastened, e.g. welded or screwed as pipes, made of graphite blocks (8, 14, 15, 16, 22) and metal disks (9), all connected to each other by tie rods (19) and fastening elements (20).
- the insert basket (4) according to the invention is excellently suited to be used alone as a storage basket in intermediate and final storage for storing radioactive substances. It is particularly advantageous to pass cooling channels (17) through the graphitic matrix material (5), preferably lined with neutron-absorbing metal tubes (18). If the insert basket (4) according to the invention is placed on a corresponding substructure in an air-cooled interim storage facility, the cooling air sweeps through the cooling channels (17) due to the thermals that arise and dissipates the waste heat generated by the radioactive decay.
- the E insatzkorb (4) has occasionally to the tie rods (19), the basket container (10) and the basket lid (11) means, such as hooks or eyelets, devices for the handling crane or similar lifting.
- the gap (13) between the basket (4) according to the invention and the shielding container (1) can be filled with graphite or metal powder, as can the remaining volume in the shafts (6) occupied by the radioactive fuel elements.
- the insert basket (4) according to the invention also has the advantage that it can be assembled quickly, e.g. by threading perforated graphite disks (8) and metal disks (9) onto the lining tubes (23, 24) of the shafts (6) or onto the tubes (18) of the cooling channels (17) and optionally onto the tie rod (20).
- the described configurations of the insert basket (4) either with the basket container (10) or with the metal disks (9) shaped as a pot shape (12) ensure that no graphite matrix material is easily lost even in the event of an accident.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Packages (AREA)
- Carbon And Carbon Compounds (AREA)
- Supplying Secondary Fuel Or The Like To Fuel, Air Or Fuel-Air Mixtures (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Bekannte Behälter zum Transport und/oder zur Lagerung bestrahlter Brennelemente besitzen Einsatzkörbe aus Stahlkonstruktionen oder massiven Körpern aus Nichteisenmetallen. Diese weisen ein hohes Gewicht auf und besitzen keine Neutronenabschirmwirkung. Diese Nachteile werden durch einen Einsatzkorb vermieden, der aus Graphit besteht.Known containers for transporting and / or storing irradiated fuel elements have insert baskets made of steel structures or solid bodies made of non-ferrous metals. These are heavy and have no neutron shielding effect. These disadvantages are avoided by using an insert basket made of graphite.
Description
Gegenstand der vorliegenden Erfindung ist ein in einem Transport- und/oder Lagerbehälter befindlicher herausnehmbarer Einsatzkorb mit Schächten für radioaktives Material, insbesondere zur Aufnahme von abgebrannten Brennelementen aus Kernreaktoren.The present invention relates to a removable insert basket with shafts for radioactive material, in particular for receiving spent fuel elements from nuclear reactors, located in a transport and / or storage container.
Bei Transport- und/oder Lagerbehältern ist normalerweise ein Einsatzkorb erforderlich, um gleichzeitig mehrere abgebrannte Brennelemente aus Kernreaktoren während des Transports oder auch während der Lagerung in einem vorgegebenen Abstand zueinander in dem Behälter unterzubringen. Deshalb sind die jeweiligen notwendigen Brennelementpositionen als entsprechende Schächte ausgebildet, in die die Brennelemente eingebracht werden. Der Schachtquerschnitt richtet sich in Form und Abmessung nach den einzubringenden Brennelementtypen. Außerdem müssen die Brennelemente mühelos fernbedient herein- und herausgebracht werden können. Der Einsatzkorb muß ausreichend stabil sein, damit er den mechanischen und thermischen Belastungen während des Transports standhält. Er muß außerdem so konstruiert sein, daß die zu befördernden Brennelemente während des Transports und der Handhabung nicht beschädigt werden.In the case of transport and / or storage containers, an insert basket is normally required in order to accommodate several spent fuel elements from nuclear reactors in the container at a predetermined distance from one another during transport or also during storage. The respective necessary fuel element positions are therefore designed as corresponding shafts into which the fuel elements are introduced. The shape and dimensions of the shaft cross-section depend on the fuel element types to be inserted. In addition, the fuel assemblies must be able to be brought in and out remotely with ease. The insert basket must be sufficiently stable so that it can withstand the mechanical and thermal loads during transport. It must also be designed so that the fuel assemblies to be transported are not damaged during transport and handling.
Solche Einsatzkörbe sind normalerweise als reines Stahlgestell oder als massiver Block aus Nichteisenmetall ausgeführt. Die Schächte der massiven Blöcke sind maschinell hergestellt. Sie sind gegebenenfalls mit Stahl ausgekleidet.Such insert baskets are usually designed as a pure steel frame or as a solid block made of non-ferrous metal. The shafts of the massive blocks are machine-made. If necessary, they are lined with steel.
Stahlgestelle sind als Einsatzkörbe geeignet, wenn sich in dem Transport- und/oder Lagerbehälter eine entsprechende Flüssigkeit befindet, die die von den Brennelementen erzeugte Restwärme an die Behälterwand ab leitet. Die Stahlgestelle können aus Borstahl bestehen, wobei Bor als Neutronenabsorber dient.Steel racks are suitable as insert baskets if there is a corresponding liquid in the transport and / or storage container, which conducts the residual heat generated by the fuel elements to the container wall. The steel frames can consist of boron steel, with boron serving as a neutron absorber.
Die mit Schächten versehenen massiven Nichteisen-. konstruktionen eignen sich als Einsatzkörbe, da sie die erzeugte Restwärme infolge guter Wärmeleitung ohne Hilfsmedium an die Behälterwand abzuleiten vermögen. Sie bestehen vorzugsweise aus Aluminium oder Kupfer bzw. deren Legierungen. Diesen Legierungen kann ebenfalls Bor oder Kadmium als Neutronenabsorber zugegeben werden.The massive non-ferrous. Constructions are suitable as insert baskets because they can dissipate the residual heat generated due to good heat conduction to the tank wall without auxiliary medium. They preferably consist of aluminum or copper or their alloys. Boron or cadmium can also be added to these alloys as a neutron absorber.
Die bisherigen bekannten Einsatzkörbe haben eine Reihe von Nachteilen. Sie weisen ein hohes Gewicht auf, da sie wegen der erforderlichen Wärmeleitfähigkeit überwiegend metallisch aufgebaut sind. Teilweise ist, insbesondere bei speziellen Stahlgestellen, eine beim Unfall nachteilige Wasserkühlung erforderlich. Die Neutronenabschirmung erfolgt nur zu einem geringen Teil durch die Körbe, die Hauptabschirmwirkung wird durch einen besonderen Neutronenschutz am Abschirmtransport- bzw. Lagerbehälter sichergestellt. Bei Unfällen, z.B. auch Feuer, kann dieser Neutronenschutz am Abschirmbehälter jedoch zerstört werden.The previously known insert baskets have a number of disadvantages. They have a high weight because they are predominantly made of metal due to the required thermal conductivity. In some cases, especially in the case of special steel frames, water cooling which is disadvantageous in the event of an accident is required. Only a small part of the neutron shielding is provided by the baskets, the main shielding effect is ensured by a special neutron protection on the shielding transport or storage container. At accidents, eg fire, this neutron protection can be destroyed on the shielding container.
Es war daher Aufgabe der vorliegenden Erfindung, einen in einem Transport- und/oder Lagerbehälter befindlichen herausnehmbaren Einsatzkorb mit Schächten für radioaktives Material, insbesondere zur Aufnahme von abgebrannten Brennelementen aus Kernreaktoren zu schaffen, der ein geringes Gewicht, eine wirksame Neutronenabschirmung und eine ausreichende Wärmeleitfähigkeit aufweist sowie als eigenständiger Zwischen- bzw. Endlagerbehälter verwendbar ist.It was therefore an object of the present invention to provide a removable insert basket in a transport and / or storage container with shafts for radioactive material, in particular for receiving spent fuel elements from nuclear reactors, which has a low weight, effective neutron shielding and adequate thermal conductivity and can be used as an independent intermediate or final storage container.
Die Aufgabe wurde erfindungsgemäß dadurch gelöst, daß die Matrix des Einsatzkorbes überwiegend aus Graphit besteht.The object was achieved in that the matrix of the insert basket consists predominantly of graphite.
Die Erfindung ist in den schematischen Abbildungen I bis V beispielhaft erläutert, wobei Abbildung I eine Seitenansicht des erfindungsgemäßen Einsatzkorbes und Abbildung II die entsprechende Draufsicht darstellen. Abbildung III zeigt den Aufbau des Einsatzkorbes aus erfindungsgemäßen Bausteinen, mit und ohne Metallscheiben, Abbildung IV die topfförmige Ausgestaltung der Metallscheiben sowie eine Zugankeranordnung, und Abbildung V Kühlkanäle im Einsatzkorb.The invention is illustrated by way of example in the schematic illustrations I to V, where illustration I represents a side view of the insert basket according to the invention and illustration II the corresponding top view. Figure III shows the structure of the insert basket made of building blocks according to the invention, with and without metal disks, Figure IV the cup-shaped design of the metal disks and a tie rod arrangement, and Figure V cooling channels in the insert basket.
In einem Abschirmbehälter (1) mit einem Abschirmdeckel (2) und einem Außendeckel (3) befindet sich ein herausnehmbarer Einsatzkorb (4), der Schächte (6) zur Aufnahme von radioaktivem Material, insbesondere zur Aufnahme von abgebrannten Brennelementen enthält. Die Matrix (5) des Einsatzkorbes (4) besteht aus Graphit, einem leichten und unter normalen Bedingungen schwer-brennbarem Material mit guten Wärmeleitungseigenschaften und hervorragenden Neutronenmoderierungsqualitäten. Der Graphit der Graphitmatrix (5) ist vorzugsweise verdichtet, beispielsweise durch Pressen oder andere bekannte Verfahren, und anschließend gegebenenfalls durch Drehen, Fräsen und Bohren bearbeitet. Es hat sich dabei als besonders vorteilhaft erwiesen, daß die Schächte (6) und/oder die äußere Oberfläche des Einsatzkorbes (4) metallische neutronenabsorbierende Auskleidungen (7, 10) aufweisen. Diese Auskleidungen können Rohre mit entsprechenden Querschnittsprofilen (23, 24) sein bzw. ein Korbbehälter (10), der mit einer Abdeckung (21) versehen ist. Die Abdeckung (21) enthält öffnungen (25), durch die das radioaktive Material in die Schächte (6) eingeführt werden kann. Der erfindungsgemäße Einsatzkorb (4) ist mit einem Deckel (11) verschlossen. Die Verwendung von Borstahl als Auskleidung (7) der Schächte (6), des Korbbehälters (10) und der Abdeckung (21) ist besonders günstig, ebenso das Hinzumischen von Borkarbid zum Matrixgraphit (5). Dadurch werden der n-Einfang verbessert und die Kritikalitätssicherheit vergrößert. Vorteilhafterweise ist die Graphitmatrix (5) aus entsprechend geformten Bausteinen (8, 14, 15, 16, 22) aufgebaut, wobei sich eine scheibenförmige Bausteinform (8) als besonders günstig herausgestellt hat.In a shielding container (1) with a shielding cover (2) and an outer cover (3) there is a removable insert basket (4) which contains shafts (6) for receiving radioactive material, in particular for receiving spent fuel elements. The matrix (5) of the insert korbes (4) consists of graphite, a light and under normal conditions flame-retardant material with good heat conduction properties and excellent neutron moderation qualities. The graphite of the graphite matrix (5) is preferably compressed, for example by pressing or other known methods, and then, if necessary, processed by turning, milling and drilling. It has proved to be particularly advantageous that the shafts (6) and / or the outer surface of the E insatzkorbes (4) metallic neutron-absorbing linings (7, 10). These linings can be tubes with corresponding cross-sectional profiles (23, 24) or a basket container (10) which is provided with a cover (21). The cover (21) contains openings (25) through which the radioactive material can be introduced into the shafts (6). The insert basket (4) according to the invention is closed with a lid (11). The use of boron steel as the lining (7) of the shafts (6), the basket container (10) and the cover (21) is particularly favorable, as is the addition of boron carbide to the matrix graphite (5). This improves n-capture and increases criticality security. The graphite matrix (5) is advantageously constructed from appropriately shaped building blocks (8, 14, 15, 16, 22), a disk-shaped building block shape (8) having proven to be particularly favorable.
Zur Stabilisierung und zur weiteren Verbesserung-der Wärmeleitfähigkeit ist es besonders vorteilhaft, zwischen die Graphitscheiben (8) Metallscheiben (9) anzuordnen. Dabei können die Metallscheiben (9) ebenfalls aus neutronenabsorbierendem Material gefertigt werden. Eine besonders vorteilhafte Abwandlung ist die Ausgestaltung der Metallscheiben (9) als Topfform (12), in der die graphitischen Bausteine (8, 14, 15, 16, 22) allseitig geschützt sind.To stabilize and further improve the thermal conductivity, it is particularly advantageous to arrange metal disks (9) between the graphite disks (8). The metal discs (9) also be made of neutron absorbing material. A particularly advantageous modification is the design of the metal disks (9) as a pot shape (12), in which the graphitic building blocks (8, 14, 15, 16, 22) are protected on all sides.
In besonderen Fällen kann auf den Korbbehälter (10) verzichtet werden. Dann besteht der Einsatzkorb (4) aus einer kräftigen Bodenplatte (26), auf der die Auskleidungen (7) für die Schächte (6) befestigt sind, z.B. als Rohre angeschweißt oder geschraubt, aus den graphitischen Bausteinen (8, 14, 15, 16, 22) und aus den Metallscheiben (9), alles durch Zuganker (19) und Befestigungselemente (20) miteinander verbunden.In special cases, the basket container (10) can be omitted. Then the insert basket (4) consists of a strong base plate (26) on which the linings (7) for the shafts (6) are fastened, e.g. welded or screwed as pipes, made of graphite blocks (8, 14, 15, 16, 22) and metal disks (9), all connected to each other by tie rods (19) and fastening elements (20).
Der erfindungsgemäße Einsatzkorb (4) ist hervorragend geeignet, für sich allein als Lagerkorb in Zwischen- und Endlagern zur Aufbewahrung radioaktiver Stoffe verwendet zu werden. Dabei ist es besonders vorteilhaft, durch das graphitische Matrixmaterial (5) Kühlkanäle (17), vorzugsweise mit neutronenabsorbierenden Metallrohren (18) ausgekleidet, zu führen. Wird der erfindungsgemäße Einsatzkorb (4) auf eine entsprechende Unterkonstruktion in einem luftgekühlten Zwischenlager gestellt, so streicht die Kühlluft auf Grund der sich einstellenden Thermik durch die Kühlkanäle (17) und führt die durch den radioaktiven Zerfall entstehende Abwärme ab.The insert basket (4) according to the invention is excellently suited to be used alone as a storage basket in intermediate and final storage for storing radioactive substances. It is particularly advantageous to pass cooling channels (17) through the graphitic matrix material (5), preferably lined with neutron-absorbing metal tubes (18). If the insert basket (4) according to the invention is placed on a corresponding substructure in an air-cooled interim storage facility, the cooling air sweeps through the cooling channels (17) due to the thermals that arise and dissipates the waste heat generated by the radioactive decay.
Der Einsatzkorb (4) besitzt fallweise an den Zugankern (19), am Korbbehälter (10) und am Korbdeckel (11) Einrichtungen, wie Haken oder ösen, zum Hantieren mittels Kran oder ähnlichen Hebe- vorrichtungen.The E insatzkorb (4) has occasionally to the tie rods (19), the basket container (10) and the basket lid (11) means, such as hooks or eyelets, devices for the handling crane or similar lifting.
Gegebenenfalls kann der Spalt (13) zwischen dem erfindungsgemäßen Korb (4) und dem Abschirmbehälter (1) mit Graphit- oder Metallpulver ausgefüllt werden, ebenso das verbleibende.Restvolumen in den durch die radioaktiven Brennelemente besetzten Schächten (6).If necessary, the gap (13) between the basket (4) according to the invention and the shielding container (1) can be filled with graphite or metal powder, as can the remaining volume in the shafts (6) occupied by the radioactive fuel elements.
Der erfindungsgemäße Einsatzkorb (4) hat ferner den Vorteil, daß er schnell aufbaubar ist, z.B. durch Auffädeln gelochter Graphit-Scheiben (8) und Metallscheiben (9) auf die Auskleidungsrohre (23, 24) der Schächte (6) bzw. auch auf die Rohre (18) der Kühlkanäle (17) und gegebenenfalls auf den Zuganker (20).The insert basket (4) according to the invention also has the advantage that it can be assembled quickly, e.g. by threading perforated graphite disks (8) and metal disks (9) onto the lining tubes (23, 24) of the shafts (6) or onto the tubes (18) of the cooling channels (17) and optionally onto the tie rod (20).
Weiterhin bewirken die beschriebenen Ausgestaltungen des Einsatzkorbes (4) entweder mit dem Korbbehälter (10) oder mit den als Topfform (12) geformten Metallscheiben (9), daß auch bei einem Unfall kein Graphit-Matrixmaterial ohne weiteres verlorengeht.Furthermore, the described configurations of the insert basket (4) either with the basket container (10) or with the metal disks (9) shaped as a pot shape (12) ensure that no graphite matrix material is easily lost even in the event of an accident.
Für die Graphit-Matrix (5) kann billiger Graphit mit Verunreinigungen verwendet werden. Der Verunreinigungsgehalt verbessert sogar noch die neutronenabsorbierenden Eigenschaften des Einsatzkorbes.Cheap graphite with impurities can be used for the graphite matrix (5). The contamination content even improves the neutron-absorbing properties of the insert basket.
Claims (12)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE3012310 | 1980-03-29 | ||
DE19803012310 DE3012310A1 (en) | 1980-03-29 | 1980-03-29 | INSERT BASKET FOR RADIOACTIVE MATERIAL IN TRANSPORT AND / OR STORAGE CONTAINERS |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0036982A1 true EP0036982A1 (en) | 1981-10-07 |
EP0036982B1 EP0036982B1 (en) | 1984-06-06 |
Family
ID=6098776
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP81101812A Expired EP0036982B1 (en) | 1980-03-29 | 1981-03-12 | Housing for radioactive materials in transport and/or storage containers |
Country Status (4)
Country | Link |
---|---|
US (1) | US4476394A (en) |
EP (1) | EP0036982B1 (en) |
DE (1) | DE3012310A1 (en) |
ES (1) | ES8303793A1 (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2548820A1 (en) * | 1983-07-06 | 1985-01-11 | Wiederaufarbeitung Von Kernbre | PROCESS FOR FILLING METALLIC CONTAINERS WITH A RADIOACTIVE FONDUE MASS MASS AND DEVICE FOR RECEIVING A RADIOACTIVE FONDUE MASS MASS |
US4680159A (en) * | 1984-08-17 | 1987-07-14 | Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh | Storage container assembly for accommodating individual fuel rods of irradiated nuclear reactor fuel elements |
EP1434239A1 (en) * | 2002-12-24 | 2004-06-30 | GNB Gesellschaft für Nuklear-Behälter mbH | Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells |
Families Citing this family (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4623510A (en) * | 1983-10-28 | 1986-11-18 | Westinghouse Electric Corp. | Permanent disposal of radioactive particulate waste in cartridge containing ferromagnetic material |
US4738799A (en) * | 1983-10-28 | 1988-04-19 | Westinghouse Electric Corp. | Permanent disposal of radioactive particulate waste |
DE4135066C1 (en) * | 1991-10-24 | 1993-04-01 | Gns Gesellschaft Fuer Nuklear-Service Mbh, 4300 Essen, De | |
JP3205179B2 (en) * | 1994-06-29 | 2001-09-04 | 株式会社日立製作所 | Radioactive material dry storage facility |
JPH09211192A (en) * | 1996-01-30 | 1997-08-15 | Sumitomo Metal Mining Co Ltd | Transportation method for nuclear fuel material |
US20010011711A1 (en) * | 1996-05-03 | 2001-08-09 | Graham Nicholson | Container for nuclear fuel transportation |
GB9609304D0 (en) * | 1996-05-03 | 1996-07-10 | British Nuclear Fuels Plc | Improvements in and relating to fuel transportation |
TW444209B (en) * | 1998-12-24 | 2001-07-01 | Hitachi Ltd | Radioactive material dry storage facility |
DE102004049236B4 (en) * | 2004-10-09 | 2006-07-13 | GNS Gesellschaft für Nuklear-Service mbH | Transport and/or storage container for nuclear fuel elements, comprises a carrier inside the container, and a number of receiving sections for the fuel elements |
US8300760B2 (en) * | 2005-12-29 | 2012-10-30 | Neucon Technology, Llc | Compressed powder composite neutron absorber material |
DE102006017427A1 (en) * | 2006-04-13 | 2007-10-18 | GNS Gesellschaft für Nuklear-Service mbH | Transport and/or storage container for fuel elements comprises a receiving basket having separated shafts in the form of tubes for fuel elements |
CN108962414B (en) * | 2018-06-15 | 2021-09-17 | 中国核电工程有限公司 | Plutonium solution storage tank |
Citations (8)
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DE2300620A1 (en) * | 1973-01-08 | 1974-07-11 | Transnuklear Gmbh | Shielded transport flask - for plutonium nitrate or uranyl nitrate solutions |
US3828197A (en) * | 1973-04-17 | 1974-08-06 | Atomic Energy Commission | Radioactive waste storage |
FR2254860A1 (en) * | 1973-12-17 | 1975-07-11 | Etude En Centre | Radioactive object transport container - using copper plated stainless steel esp for irradiated fuel rod assemblies |
FR2258692A1 (en) * | 1974-01-23 | 1975-08-18 | Transnucleaire | Package for nuclear fuel elements - particularly for transport prior to reprocessing |
DE2740933B1 (en) * | 1977-09-10 | 1979-01-18 | Rheinisch Westfaelisches Elek | Transport or storage container for radioactive materials, in particular irradiated nuclear reactor fuel elements |
DE2828138A1 (en) * | 1978-06-27 | 1980-01-10 | Amtrust Ag | Transport container for irradiated fuel elements - has removable basket to support elements in container or cooling pool |
GB2024694A (en) * | 1978-06-28 | 1980-01-16 | Transnuklear Gmbh | Radioactive material enclosures |
EP0020948A2 (en) * | 1979-06-21 | 1981-01-07 | The Carborundum Company | Cask for radioactive material, method of manufacturing such a cask, module used thereby and method of shielding neutrons |
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US3016463A (en) * | 1958-04-28 | 1962-01-09 | Smith Corp A O | Multi-layer vessel having a neutron absorbing layer |
US3882313A (en) * | 1972-11-07 | 1975-05-06 | Westinghouse Electric Corp | Concentric annular tanks |
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1980
- 1980-03-29 DE DE19803012310 patent/DE3012310A1/en not_active Ceased
-
1981
- 1981-03-05 ES ES500106A patent/ES8303793A1/en not_active Expired
- 1981-03-12 EP EP81101812A patent/EP0036982B1/en not_active Expired
- 1981-03-27 US US06/248,441 patent/US4476394A/en not_active Expired - Fee Related
Patent Citations (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2300620A1 (en) * | 1973-01-08 | 1974-07-11 | Transnuklear Gmbh | Shielded transport flask - for plutonium nitrate or uranyl nitrate solutions |
US3828197A (en) * | 1973-04-17 | 1974-08-06 | Atomic Energy Commission | Radioactive waste storage |
FR2254860A1 (en) * | 1973-12-17 | 1975-07-11 | Etude En Centre | Radioactive object transport container - using copper plated stainless steel esp for irradiated fuel rod assemblies |
FR2258692A1 (en) * | 1974-01-23 | 1975-08-18 | Transnucleaire | Package for nuclear fuel elements - particularly for transport prior to reprocessing |
DE2740933B1 (en) * | 1977-09-10 | 1979-01-18 | Rheinisch Westfaelisches Elek | Transport or storage container for radioactive materials, in particular irradiated nuclear reactor fuel elements |
DE2828138A1 (en) * | 1978-06-27 | 1980-01-10 | Amtrust Ag | Transport container for irradiated fuel elements - has removable basket to support elements in container or cooling pool |
GB2024694A (en) * | 1978-06-28 | 1980-01-16 | Transnuklear Gmbh | Radioactive material enclosures |
EP0020948A2 (en) * | 1979-06-21 | 1981-01-07 | The Carborundum Company | Cask for radioactive material, method of manufacturing such a cask, module used thereby and method of shielding neutrons |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2548820A1 (en) * | 1983-07-06 | 1985-01-11 | Wiederaufarbeitung Von Kernbre | PROCESS FOR FILLING METALLIC CONTAINERS WITH A RADIOACTIVE FONDUE MASS MASS AND DEVICE FOR RECEIVING A RADIOACTIVE FONDUE MASS MASS |
US4680159A (en) * | 1984-08-17 | 1987-07-14 | Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh | Storage container assembly for accommodating individual fuel rods of irradiated nuclear reactor fuel elements |
EP1434239A1 (en) * | 2002-12-24 | 2004-06-30 | GNB Gesellschaft für Nuklear-Behälter mbH | Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells |
Also Published As
Publication number | Publication date |
---|---|
ES500106A0 (en) | 1983-02-01 |
US4476394A (en) | 1984-10-09 |
EP0036982B1 (en) | 1984-06-06 |
DE3012310A1 (en) | 1981-10-08 |
ES8303793A1 (en) | 1983-02-01 |
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