EP0990237A1 - Procede de production d'un conteneur, et conteneur ainsi produit - Google Patents

Procede de production d'un conteneur, et conteneur ainsi produit

Info

Publication number
EP0990237A1
EP0990237A1 EP98936155A EP98936155A EP0990237A1 EP 0990237 A1 EP0990237 A1 EP 0990237A1 EP 98936155 A EP98936155 A EP 98936155A EP 98936155 A EP98936155 A EP 98936155A EP 0990237 A1 EP0990237 A1 EP 0990237A1
Authority
EP
European Patent Office
Prior art keywords
outer tube
aggregate
annular gap
container
metal
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
Application number
EP98936155A
Other languages
German (de)
English (en)
Other versions
EP0990237B1 (fr
Inventor
Konrad Gluschke
Reinhard Struth
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.)
GNB Gesellschaft fuer Nuklear Behaelter mbH
Original Assignee
GNB GmbH
GNB Gesellschaft fuer Nuklear Behaelter mbH
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 GNB GmbH, GNB Gesellschaft fuer Nuklear Behaelter mbH filed Critical GNB GmbH
Publication of EP0990237A1 publication Critical patent/EP0990237A1/fr
Application granted granted Critical
Publication of EP0990237B1 publication Critical patent/EP0990237B1/fr
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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

Definitions

  • the invention relates to a method for producing a container for the transport and storage of radioactive material and a container with which radioactive material can be transported and stored.
  • Such containers have achieved great importance in the past in the embodiment of so-called "castor containers". They are used to transport radioactive material, such as spent fuel from nuclear reactors, from the power plant to an intermediate or final storage location. Large distances have to be covered in some cases. Such transport requires an extremely high level of security. This applies not only to the transport vehicles (trucks, trains, ships), but above all to the containers in which, for example, the fuel elements are transported.
  • the container must be constructed so that the escape of radioactive radiation and gases is reliably prevented.
  • the container must be designed so that the safety according to 1. also exists if there is an accident, for example a fall of the container from a transport vehicle.
  • the requirements placed on the radioactive shielding of the container are just as high as on its strength and stability.
  • the object of the invention is to provide a method for producing a corresponding container or a container which meets the aforementioned requirements.
  • Radioactive rays include alpha rays, beta rays, Gam a rays and neutron rays.
  • Alpha and beta rays generally have such short ranges that small material thicknesses (of the order of magnitude: a few millimeters) are sufficient for their shielding.
  • the main thing is to attenuate and absorb the neutron and gamma radiation.
  • the mass and thus the bulk density of a corresponding container wall is an essential variable.
  • steel containers such as the Castor container mentioned have been used in the past.
  • steel-reinforced concrete containers are known, which are constructed from a combination of steel / concrete.
  • the invention is based on the knowledge that the shielding effect of such steel-reinforced concrete containers can be achieved by a special selection of heavy concrete between steel walls.
  • the invention proposes a method for producing a container for the transport and storage of radioactive material with the following features:
  • an inner tube made of metal is set in an outer tube made of metal so that an annular gap of constant width is formed between the inner and outer tubes,
  • the annular gap is then filled with an aggregate or an aggregate mixture whose minimum grain size is 2 mm and whose maximum grain size is 20 mm, at least 95% by weight of the aggregate having a bulk density> 4.2 g / cm 3 ,
  • a suspension of cement, water and a condenser is pressed under high pressure into the annular gap through at least one opening at the bottom end of the inner and / or outer tube until the suspension completely fills the gusset between the aggregate and the upper end of the outer tube has reached -
  • the suspension of cement, water and plasticizer is adjusted so that the resulting concrete (together with the aggregate) has a bulk density> 4,100 g / cm 3 and a concrete compressive strength according to DIN 1048 Part 2 of> 45 N / mm 2 28 days.
  • the essential aspect of this process is the special technique of placing the heavy concrete between the metal walls mentioned.
  • cement stands for all types of hydraulic binders.
  • Portland cements are preferably used, specifically Portland cements of the type CEM I 42.5 or higher (for example CEM I 52.5).
  • Surcharges that have the required bulk density are, for example, barite, ferrophosphorus, magnetite, iron (steel), lead, hematite and chilled cast granulate, and other metals, in particular heavy metals, it being possible for the surcharges to be used individually or in mixtures.
  • a mixture of barite, ferrophosphorus, magnetite, haematite or mixtures thereof in combination with steel balls leads to very good density and compressive strength values of the fresh concrete or hardened concrete.
  • the proportions of the individual surcharge components can, for example, be as follows:
  • this term includes in particular steel pipes and here in particular steel pipes with circular cross-section, although other cross-sectional shapes, for example polygons, can also be used.
  • One embodiment of the method provides for the use of an inner tube which is closed at its upper end and shorter than the outer tube.
  • the outer tube and inner tube are placed on a floor (a plate), for example, and then not only the ring space between the inner and outer tubes is filled with the aggregate, but also the space between the upper closed end of the inner tube and the upper edge of the outer tube.
  • the space between the closed end of the inner tube and the upper edge of the outer tube is then filled with the cement / water / plasticizer suspension.
  • a kind of "concrete lid” is created, which in later use (after turning through 180 °) forms the bottom of the container.
  • a metal / steel plate can be attached to the upper edge of the outer tube, for example screwed or welded on.
  • the manufacturing process is simplified if the inner tube and outer tube are closed with a metal / steel cover at their lower end before the addition is filled. This is preferably done by screwing onto the corresponding pipe ends. In this way, the coaxial alignment of the inner and outer pipe is facilitated, even when the aggregate is filled in or when the cement suspension is injected.
  • the lower container end forms the upper container end in the finished container (after rotation through 180 °).
  • spent fuel elements can be inserted into the free space of the inner tube and the container can then be closed again.
  • the stability of the container is significantly improved if a reinforcement is inserted into the annular gap or the space formed between the upper closed end of the inner tube and the open end of the outer tube before the addition is filled. This also improves the heat dissipation during the hydration of the cement.
  • Such reinforcement can consist, for example, of a reinforcement cage which extends essentially over the entire volume of the annular gap or the space mentioned.
  • a width of the annular gap of, for example, 20 to 30 cm is assumed.
  • the "concrete floor slab” mentioned can also have a corresponding thickness.
  • the end container lids can have somewhat smaller wall thicknesses, for example 5 to 15 cm.
  • the invention also includes a container for the transport and storage of radioactive material, which is accordingly characterized by the following features: -
  • the container consists of an outer tube made of metal and an inner tube made of metal arranged with the same circumferential spacing, forming an annular gap of constant width between the inner and outer tubes,
  • the annular gap between the inner and outer pipe is filled with a heavy concrete consisting of an aggregate or aggregate mixture with a bulk density> 4.2 g / cm 3 and a gusset filling the cement between the aggregate, the heavy concrete having a bulk density of> 4,100 g / cm 3 and a 28-day compressive strength according to DIN 1048 Part 2 of> 45 N / mm 2 , and
  • the outer tube and inner tube are closed at the end with a metal base and a metal cover, at least the metal cover being arranged detachably.
  • the container can be designed such that the inner tube ends at a distance from the lower end of the outer tube, is closed at this end and a heavy concrete plate is present between the closed lower end of the inner tube and the lower end of the outer tube, which is material-tight with the heavy concrete present in the annular gap.
  • This embodiment describes the container in the state of use.
  • the inner and outer tubes are arranged rotated by 180 °, as described above.
  • the heavy concrete can be reinforced, the reinforcement consisting, for example, of a reinforcement cage. Further features of the invention result from the features of the subclaims and the other application documents.
  • Figure 1 an arrangement of steel outer and steel inner tube before filling a concrete aggregate
  • Figure 2 the arrangement of Figure 1, the between
  • FIG. 3 the arrangement according to FIG. 2, in which the space between the outer and inner tubes is additionally filled approximately in half with a cement suspension,
  • Figure 4 a finished container in longitudinal section.
  • a steel outer tube 10 and a steel inner tube 12 arranged concentrically therein can be seen in FIG.
  • the outer tube 10 and inner tube 12 each stand on a cover 14 with their lower end, the cover 14 being screwed onto two corresponding external threads at the lower end of the outer tube 10 and the inner tube 12 via two concentric flanges 16, 18 with an internal thread.
  • the inner tube 12 is shorter than the outer tube 10 and ends accordingly at a distance from the upper edge of the outer tube 10.
  • the inner tube 12 is closed at the upper end with a steel plate 20.
  • annular gap 22 of constant width (b) is formed between the outer tube 10 and the inner tube 12 and a space 24 is formed between the steel plate 20 and the upper end of the outer tube 10.
  • the annular gap 22 and the space 24 are filled with a steel reinforcement cage 26 (FIG. 2).
  • the reinforcement can also be previously attached, for example welded, to the inner wall of the outer tube and / or to the outer wall of the inner tube.
  • a heavy concrete aggregate is then filled into the annular gap 22 and the space 24, which here consists of 20% by weight barite of the 4/8 mm grain fraction, 30% by weight of the 8/16 mm grain fraction and 50% by weight.
  • % Steel balls with a diameter between 5 and 8 mm in a homogeneous mixture ( Figure 2).
  • the outer tube 10 has two openings 30, which are offset by 180 ° to one another, into each of which a tubular adapter 32 is screwed.
  • the openings are arranged at the lower end of the outer tube 10.
  • a delivery line (shown schematically by arrow 34) is then connected to the adapter 32.
  • a cement / water / plasticizer mixture in the form of a viscous suspension is then injected under pressure into the annular gap 22 via the delivery line.
  • the suspension consists of cement of type CEM I 42.5, a water content of 35%, based on the cement, and a 3% plasticizer (plasticizer here: melamine sulfonate), based on the cement content.
  • the cement suspension is then further injected until the annular gap 22 and the space 24 arranged above it are completely filled with the cement suspension.
  • a steel plate 38 (shown in broken lines in FIG. 3) is welded onto the upper end of the outer tube 10.
  • the arrangement is then rotated through 180 ° (FIG. 4). If necessary, the container lid 14 can then be replaced by another steel lid 40.
  • the openings 30 on the finished container are preferably likewise closed.
  • the 7-day compressive strength according to DIN 1048, part 2 of the heavy concrete is 26 N / mm 2 , the corresponding 28-day compressive strength is 46 N / mm 2 .
  • the modulus of elasticity of the concrete was determined based on DIN 1048 Part 5 with 30,000 N / mm 2 .

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Curing Cements, Concrete, And Artificial Stone (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Containers Having Bodies Formed In One Piece (AREA)
  • Packages (AREA)
  • Manufacturing Of Tubular Articles Or Embedded Moulded Articles (AREA)
  • Packging For Living Organisms, Food Or Medicinal Products That Are Sensitive To Environmental Conditiond (AREA)

Abstract

L'invention concerne un procédé de production d'un conteneur destiné au transport et au stockage de matériau radioactif, ainsi qu'un conteneur au moyen duquel un matériau radioactif peut être transporté et stocké. Ce sont principalement la sélection d'un béton lourd et une technique spéciale d'introduction de ce béton lourd entre des parois métalliques qui font l'objet des revendications.
EP98936155A 1997-06-19 1998-06-09 Procede de production d'un conteneur, et conteneur ainsi produit Expired - Lifetime EP0990237B1 (fr)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
DE19725922 1997-06-19
DE19725922A DE19725922C2 (de) 1997-06-19 1997-06-19 Verfahren zur Herstellung eines Behälters
PCT/DE1998/001608 WO1998059346A1 (fr) 1997-06-19 1998-06-09 Procede de production d'un conteneur, et conteneur ainsi produit

Publications (2)

Publication Number Publication Date
EP0990237A1 true EP0990237A1 (fr) 2000-04-05
EP0990237B1 EP0990237B1 (fr) 2002-08-07

Family

ID=7832941

Family Applications (1)

Application Number Title Priority Date Filing Date
EP98936155A Expired - Lifetime EP0990237B1 (fr) 1997-06-19 1998-06-09 Procede de production d'un conteneur, et conteneur ainsi produit

Country Status (15)

Country Link
US (1) US6518585B1 (fr)
EP (1) EP0990237B1 (fr)
JP (1) JP2001508874A (fr)
KR (1) KR100320969B1 (fr)
CN (1) CN1165915C (fr)
AU (1) AU8531398A (fr)
CA (1) CA2292589C (fr)
CZ (1) CZ293385B6 (fr)
DE (2) DE19725922C2 (fr)
EA (1) EA001461B1 (fr)
ES (1) ES2181250T3 (fr)
SK (1) SK283640B6 (fr)
TW (1) TW366501B (fr)
UA (1) UA54529C2 (fr)
WO (1) WO1998059346A1 (fr)

Families Citing this family (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
ES2181339T3 (es) * 1999-06-19 2003-02-16 Gnb Gmbh Recipiente de transporte y/o almacenamiento para elementos radiactivos productores de calor.
ES2182452T3 (es) 1999-12-15 2003-03-01 Gnb Gmbh Procedimiento para fabricar un recipiente de transporte y/o almacenamiento de objetos radiactivos.
US7014059B2 (en) * 2002-05-17 2006-03-21 Master Lite Security Products, Inc. Explosion resistant waste container
SE525468C2 (sv) * 2002-11-29 2005-03-01 Oyster Internat Nv C O H B Man Behållaranordning för förvaring av riskmaterial, i synnerhet för slutförvaring av kärnbränsle, och sätt för dess framställning
DE10327466B4 (de) * 2003-01-13 2008-08-07 Jan Forster Baukörper für Strahlenschutzbauwerke
US6946697B2 (en) * 2003-12-18 2005-09-20 Freescale Semiconductor, Inc. Synthetic antiferromagnet structures for use in MTJs in MRAM technology
JP2006038465A (ja) * 2004-07-22 2006-02-09 Kumagai Gumi Co Ltd 放射線遮蔽用コンクリート組成物
US9443625B2 (en) * 2005-03-25 2016-09-13 Holtec International, Inc. Method of storing high level radioactive waste
US20090126555A1 (en) * 2005-05-11 2009-05-21 Jonny Olsson Device for Storage, Transport or Disposal of Objects
ES2296522B1 (es) * 2006-05-26 2009-04-01 Europea De Minerales Y Derivados, S.L. Masa pesada para la fabricacion de productos con alta capacidad de radio-proteccion.
JP5545788B1 (ja) * 2013-07-07 2014-07-09 株式会社安藤・間 放射線遮蔽容器、放射線遮蔽函体、及び放射性廃棄物の収容方法
CN108122650A (zh) * 2016-11-29 2018-06-05 黄璜 可适变异形衬管
US11881323B2 (en) 2020-11-25 2024-01-23 Holtec International High-density subterranean storage system for nuclear fuel and radioactive waste
EP4352753A4 (fr) * 2021-05-17 2025-09-17 Holtec International Système de stockage de déchets nucléaires empilable
DE102022202475A1 (de) 2022-03-11 2023-09-14 Fraunhofer-Gesellschaft zur Förderung der angewandten Forschung eingetragener Verein Mehrlagiger Werkstoffverbund, Bauteil umfassend den mehrlagigen Werkstoffverbund, Verfahren zu deren Herstellung und deren Verwendung

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US3742985A (en) * 1967-01-31 1973-07-03 Chemstress Ind Inc Reinforced pipe
DE2817193A1 (de) * 1978-04-20 1979-10-31 Transnuklear Gmbh Abschirmbehaelter fuer den transport und die lagerung bestrahlter brennelemente
FR2516292A1 (fr) * 1981-11-10 1983-05-13 Stockage Assainissement Coulis special d'injection et son utilisation pour le stockage dans le sol de dechets radioactifs
DE3331892C2 (de) * 1983-09-03 1986-01-23 Kernforschungsanlage Jülich GmbH, 5170 Jülich Transport- und Lagerbehälter für radioaktives Material
DE3635500A1 (de) * 1986-10-18 1988-05-11 Kernforschungsanlage Juelich Schwerbeton zur herstellung eines transportbehaelters fuer radioaktives material
DE3709315C2 (de) * 1987-03-21 1996-04-25 Nuklear Service Gmbh Gns Verfahren zum Einlagern von radioaktiven Abfallstoffen
US5008045A (en) * 1989-03-23 1991-04-16 Alternative Technologies For Waste, Inc. Method and apparatus for centrifugally casting hazardous waste
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JP3084123B2 (ja) * 1992-04-15 2000-09-04 ジオスター株式会社 ボックスカルバートの製造方法
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JP3332687B2 (ja) * 1995-10-03 2002-10-07 株式会社東芝 原子炉格納容器
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Also Published As

Publication number Publication date
SK175199A3 (en) 2000-06-12
DE19725922C2 (de) 2000-07-20
CA2292589A1 (fr) 1998-12-30
CZ293385B6 (cs) 2004-04-14
KR19990007116A (ko) 1999-01-25
ES2181250T3 (es) 2003-02-16
JP2001508874A (ja) 2001-07-03
CZ433899A3 (cs) 2000-04-12
EA199901064A1 (ru) 2000-08-28
CN1261456A (zh) 2000-07-26
WO1998059346A1 (fr) 1998-12-30
CN1165915C (zh) 2004-09-08
DE19725922A1 (de) 1998-12-24
EP0990237B1 (fr) 2002-08-07
EA001461B1 (ru) 2001-04-23
US6518585B1 (en) 2003-02-11
DE59805117D1 (de) 2002-09-12
CA2292589C (fr) 2003-02-25
UA54529C2 (uk) 2003-03-17
TW366501B (en) 1999-08-11
SK283640B6 (sk) 2003-11-04
AU8531398A (en) 1999-01-04
KR100320969B1 (ko) 2002-05-13

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