EP0036982B1 - Enceinte pour le transport et/ou le stockage de matières radioactives - Google Patents

Enceinte pour le transport et/ou le stockage de matières radioactives Download PDF

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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
Application number
EP81101812A
Other languages
German (de)
English (en)
Other versions
EP0036982A1 (fr
Inventor
Erhard Ing. grad. Müller
Richard Dr. Christ
Hartmut Dipl.-Phys. Kroll
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Transnuklear GmbH
Original Assignee
Transnuklear GmbH
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Transnuklear GmbH filed Critical Transnuklear GmbH
Publication of EP0036982A1 publication Critical patent/EP0036982A1/fr
Application granted granted Critical
Publication of EP0036982B1 publication Critical patent/EP0036982B1/fr
Expired legal-status Critical Current

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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 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Carbon And Carbon Compounds (AREA)

Claims (12)

1. Cage intérieure amovible munie de puits pour matières radioactives placée dans des cuves de transport et/ou de stockage, destinée en particulier à recevoir des éléments combustibles brûlés de réacteurs nucléaires, cage caractérisée en ce que la matrice (5) de cette cage (4) est constituée en majeure partie de graphite.
2. Cage selon la revendication 1, caractérisée en ce que les puits (6) et/ou les surfaces extérieures de la cage comportent des revêtements (7, 10) métalliques absorbant les neutrons.
3. Cage selon la revendication 2, caractérisée en ce que les garnitures métalliques (7, 10) sont en acier au bore.
4. Cage selon les revendications 1 à 3, caractérisée en ce que l'on mélange au graphite de la matrice (5) un matériau absorbant les neutrons.
5. Cage selon la revendication 4, caractérisée en ce que la matrice absorbant les neutrons, mélangée à la matrice (5) en graphite, est du carbure de bore.
6. Cage selon l'une quelconque des revendications 1 à 5, caractérisée en ce que la matrice en graphite (5) est constituée de plusieurs éléments (8,14,15,16,22).
7. Cage selon la revendication 6, caractérisée en ce que les éléments sont constituées par des plaques (8).
8. Cage selon la revendication 7, caractérisée en ce qu'entre les plaques (8) se trouvent des plaques métalliques (9).
9. Cage selon la revendication 8, caractérisée en ce que les plaques métalliques (9) sont réalisées sous forme de pots (12).
10. Cage selon l'une quelconque des revendications 1 à 9, caractérisée en ce qu'elle est constituée d'une plaque de fond (6) sur laquelle sont fixés des revêtements métalliques (7), d'éléments en graphite (8, 14, 15, 16, 22) et de plaques métalliques (9), qui sont reliés entre eux par des tirants (19) et des éléments de fixation (20).
11. Cage selon l'une quelconque des revendications 1 à 10, caractérisée en ce que la matrice en graphite (5) contient par des canaux de refroidissement (17).
12. Cage selon la revendication 11, caractérisée en ce que les canaux de refroidissement (17) sont pourvus de revêtements métalliques (18).
EP81101812A 1980-03-29 1981-03-12 Enceinte pour le transport et/ou le stockage de matières radioactives Expired EP0036982B1 (fr)

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 (fr) 1981-10-07
EP0036982B1 true EP0036982B1 (fr) 1984-06-06

Family

ID=6098776

Family Applications (1)

Application Number Title Priority Date Filing Date
EP81101812A Expired EP0036982B1 (fr) 1980-03-29 1981-03-12 Enceinte pour le transport et/ou le stockage de matières radioactives

Country Status (4)

Country Link
US (1) US4476394A (fr)
EP (1) EP0036982B1 (fr)
DE (1) DE3012310A1 (fr)
ES (1) ES8303793A1 (fr)

Families Citing this family (15)

* Cited by examiner, † Cited by third party
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 (fr) * 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
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
ATE385607T1 (de) * 2002-12-24 2008-02-15 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)

* Cited by examiner, † Cited by third party
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

Also Published As

Publication number Publication date
ES500106A0 (es) 1983-02-01
EP0036982A1 (fr) 1981-10-07
DE3012310A1 (de) 1981-10-08
US4476394A (en) 1984-10-09
ES8303793A1 (es) 1983-02-01

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