EP0036982B1 - Einsatzkorb für radioaktives Material in Transport- und/oder Lagerbehältern - Google Patents
Einsatzkorb für radioaktives Material in Transport- und/oder Lagerbehältern Download PDFInfo
- Publication number
- EP0036982B1 EP0036982B1 EP81101812A EP81101812A EP0036982B1 EP 0036982 B1 EP0036982 B1 EP 0036982B1 EP 81101812 A EP81101812 A EP 81101812A EP 81101812 A EP81101812 A EP 81101812A EP 0036982 B1 EP0036982 B1 EP 0036982B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- bin insert
- insert according
- graphite
- matrix
- bin
- 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
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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
Definitions
- the invention relates to 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.
- an insert basket is normally required in order to accommodate a plurality of 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.
- Steel racks are suitable as insert baskets if there is a corresponding liquid in the transport and / or storage container, which dissipates 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.
- the massive non-iron constructions with shafts 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. In the event of accidents, e.g. B. also 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.
- 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 basket (4) consists of graphite, a light and, under normal conditions, flammable 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 proven particularly advantageous that the shafts (6) and / or the outer surface of the insert basket (4) have 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 lining (7) of the manholes (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 disks (9) can 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 dispensed with.
- the insert basket (4) consists of a strong base plate (26) on which the linings (7) for the shafts (6) are fastened, for. B. welded or screwed as pipes, from the graphite blocks (8, 14, 15, 16, 22) and from the metal disks (9), all connected by tie rods (19) and fasteners (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 insert basket (4) has on the tie rods (19), on the basket container (10) and on the basket lid (11) devices, such as hooks or eyes, for handling by crane or similar lifting devices.
- 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, for. B. by threading perforated graphite discs (8) and metal discs (9) on the lining pipes (23, 24) of the shafts (6) and also on the pipes (18) of the cooling channels (17) and optionally on the tie rod (19 ).
- 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.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Packages (AREA)
- Supplying Secondary Fuel Or The Like To Fuel, Air Or Fuel-Air Mixtures (AREA)
- Carbon And Carbon Compounds (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE3012310 | 1980-03-29 | ||
DE19803012310 DE3012310A1 (de) | 1980-03-29 | 1980-03-29 | Einsatzkorb fuer radioaktives material in transport- und/oder lagerbehaelter |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0036982A1 EP0036982A1 (de) | 1981-10-07 |
EP0036982B1 true EP0036982B1 (de) | 1984-06-06 |
Family
ID=6098776
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP81101812A Expired EP0036982B1 (de) | 1980-03-29 | 1981-03-12 | Einsatzkorb für radioaktives Material in Transport- und/oder Lagerbehältern |
Country Status (4)
Country | Link |
---|---|
US (1) | US4476394A (es) |
EP (1) | EP0036982B1 (es) |
DE (1) | DE3012310A1 (es) |
ES (1) | ES500106A0 (es) |
Families Citing this family (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3324291C2 (de) * | 1983-07-06 | 1986-10-23 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Verfahren zum Befüllen von Metallbehältern mit einer radioaktiven Glasschmelze und Vorrichtung zur Aufnahme einer radioaktiven Glasschmelze |
US4738799A (en) * | 1983-10-28 | 1988-04-19 | Westinghouse Electric Corp. | Permanent disposal of radioactive particulate waste |
US4623510A (en) * | 1983-10-28 | 1986-11-18 | Westinghouse Electric Corp. | Permanent disposal of radioactive particulate waste in cartridge containing ferromagnetic material |
DE3430243C2 (de) * | 1984-08-17 | 1986-11-27 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Lagerbehälter zur Aufnahme von vereinzelten Brennstäben bestrahlter Kernreaktorbrennelemente |
DE4135066C1 (es) * | 1991-10-24 | 1993-04-01 | Gns Gesellschaft Fuer Nuklear-Service Mbh, 4300 Essen, De | |
JP3205179B2 (ja) * | 1994-06-29 | 2001-09-04 | 株式会社日立製作所 | 放射性物質乾式貯蔵設備 |
JPH09211192A (ja) * | 1996-01-30 | 1997-08-15 | Sumitomo Metal Mining Co Ltd | 核燃料物質の輸送方法 |
GB9609304D0 (en) * | 1996-05-03 | 1996-07-10 | British Nuclear Fuels Plc | Improvements in and relating to fuel transportation |
US20010011711A1 (en) * | 1996-05-03 | 2001-08-09 | Graham Nicholson | Container for nuclear fuel transportation |
TW444209B (en) * | 1998-12-24 | 2001-07-01 | Hitachi Ltd | Radioactive material dry storage facility |
DE50211653D1 (de) * | 2002-12-24 | 2008-03-20 | Nuklear Service Gmbh Gns | Transport- und Lagerbehälter für wärmeentwickelnde radioaktive Stoffe, insbesondere abgebrannte Kernreaktorbrennelemente oder HAW-Glaskokillen |
DE102004049236B4 (de) * | 2004-10-09 | 2006-07-13 | GNS Gesellschaft für Nuklear-Service mbH | Transport- und/oder Lagerbehälter für Brennelemente |
US8300760B2 (en) * | 2005-12-29 | 2012-10-30 | Neucon Technology, Llc | Compressed powder composite neutron absorber material |
DE102006017427A1 (de) * | 2006-04-13 | 2007-10-18 | GNS Gesellschaft für Nuklear-Service mbH | Transport- und/oder Lagerbehälter für Brennelemente |
CN108962414B (zh) * | 2018-06-15 | 2021-09-17 | 中国核电工程有限公司 | 一种钚溶液贮罐 |
Family Cites Families (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
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 |
DE2300620A1 (de) * | 1973-01-08 | 1974-07-11 | Transnuklear Gmbh | Behaelter zum transport von plutoniumund uranylnitratloesungen |
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 |
DE2740933C2 (de) * | 1977-09-10 | 1982-11-25 | GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen | Transport- bzw. Lagerbehälter für radioaktive Stoffe, insbesondere bestrahlte Kernreaktorbrennelemente |
DE2828138A1 (de) * | 1978-06-27 | 1980-01-10 | Amtrust Ag | Behaelter zum transportieren von radioaktiven brennelementen |
DE7819282U1 (de) * | 1978-06-28 | 1978-10-12 | Transnuklear Gmbh, 6450 Hanau | Abschirmbehaelter fuer den transport und die lagerung bestrahlter brennelemente oder sonstiger bioschaedlicher abfaelle |
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 |
-
1980
- 1980-03-29 DE DE19803012310 patent/DE3012310A1/de not_active Ceased
-
1981
- 1981-03-05 ES ES500106A patent/ES500106A0/es active Granted
- 1981-03-12 EP EP81101812A patent/EP0036982B1/de not_active Expired
- 1981-03-27 US US06/248,441 patent/US4476394A/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
EP0036982A1 (de) | 1981-10-07 |
ES8303793A1 (es) | 1983-02-01 |
DE3012310A1 (de) | 1981-10-08 |
US4476394A (en) | 1984-10-09 |
ES500106A0 (es) | 1983-02-01 |
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