EP0092679B1 - Behälter zur Aufnahme von radioaktiven Stoffen - Google Patents

Behälter zur Aufnahme von radioaktiven Stoffen Download PDF

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Publication number
EP0092679B1
EP0092679B1 EP83102908A EP83102908A EP0092679B1 EP 0092679 B1 EP0092679 B1 EP 0092679B1 EP 83102908 A EP83102908 A EP 83102908A EP 83102908 A EP83102908 A EP 83102908A EP 0092679 B1 EP0092679 B1 EP 0092679B1
Authority
EP
European Patent Office
Prior art keywords
container
layer
corrosion
cast
inner layer
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
EP83102908A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0092679A1 (de
Inventor
Franz-Wolfgang Dipl.-Ing. Popp
Kurt Dipl.-Ing. Feuring
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.)
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Original Assignee
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Nukem 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 Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH, Nukem GmbH filed Critical Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Publication of EP0092679A1 publication Critical patent/EP0092679A1/de
Application granted granted Critical
Publication of EP0092679B1 publication Critical patent/EP0092679B1/de
Expired legal-status Critical Current

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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
    • G21F5/008—Containers for fuel elements

Definitions

  • the invention relates to a container for holding radioactive substances, in particular irradiated nuclear reactor fuel elements, in which the basic container body is constructed in multiple layers, the inner layer consisting of a mechanically stable, inexpensive metallic material and the adjacent layer as a corrosion protection layer made of a cast around the inner layer.
  • high-alloy austenitic cast iron with spheroidal graphite and in which the receiving opening of the container body is closed by a sealing cover welded to the corrosion protection layer.
  • the fuel elements are loaded into a transport container.
  • These transport containers must be sealed gas-tight, which is achieved via a lid sealing system, and ensure adequate shielding against radioactivity.
  • the transport containers must have sufficient mechanical strength that can withstand accident conditions.
  • the transport container must also be designed so that the post-decay heat of the transported fuel elements can be safely dissipated to the outside.
  • the loaded transport containers are brought to an interim storage facility, where they are to be stored until the spent nuclear fuel elements are reprocessed later or for long-term storage, the so-called direct final storage.
  • the transport containers must then be opened again.
  • direct final storage the spent nuclear reactor fuel elements must be packed in special final storage containers and placed in geological formations for safe final storage.
  • the repository containers must have certain endager properties. They have to be mechanically stable, corrosion-proof and tightly sealed.
  • the hardener base of the repository container is therefore made of steel or cast iron to ensure the mechanical stability of the container. It would be preferable to use spheroidal graphite cast iron (GGG 40) for the thick-walled container body, since spheroidal cast iron is characterized by its particularly high strength and toughness.
  • This corrosion-resistant protective layer can consist of ceramic, graphite or other materials.
  • This fuel element container designed in this way can also be used for longer surface storage of the irradiated fuel elements and for transport if the thickness of the cheap inner layer is increased in accordance with the requirements for the shielding.
  • the invention is based on the object of designing a container of the type described at the outset in such a way that it can be used not only for final storage, but also for longer surface storage and for transporting the irradiated fuel elements, the amount of material in the corrosion protection layer being kept as low as possible.
  • the container base body has an outer layer of cast iron with spheroidal graphite cast around the corrosion protection layer.
  • the outer layer is cast in a mold around the corrosion protection layer. The surface of the corrosion protection layer is melted, so that a good connection between the outer layer and the corrosion protection layer is created.
  • the good connection between the two layers is also promoted by the fact that the structure of the outer layer is similar to the structure of the corrosion protection layer.
  • the outer layer made of nodular cast iron is very well suited for the use according to the invention due to the high yield strength of spherulitic cast iron, since the nodular cast iron withstands the shrinkage stresses well due to its high yield strength.
  • An advantageous embodiment of the invention is characterized in that the inner layer consists of a drawn steel tube.
  • the inner layer can have a smaller thickness due to the higher mechanical strength of a drawn steel tube. This smaller thickness means a smaller diameter of the inner layer.
  • the invention provides a fuel assembly container which receives the spent nuclear reactor fuel elements delivered in transport containers after a certain decay time.
  • the fuel assemblies can then be stored on the surface in an intermediate storage facility until the final repository is built or the reprocessing of the fuel assembly is decided.
  • the welded-on cover is milled and the fuel elements removed. If the fuel assemblies are to be sent to the direct repository in a geological formation, the fuel assembly container is brought directly to the repository without reloading or additional transport shielding.
  • test of the fuel element container according to the invention is carried out by the usual test methods such as ultrasound examination and X-ray examination, whereby each cast layer can be checked individually.
  • the container receiving the fuel elements has a thick-walled basic container body 3, which is composed of three layers.
  • the container body 3 is cylindrical and open at its front end.
  • the inner layer 5 of the container body 3 consists of a spherulitic cast iron (GGG 40). At the open end, this pot-shaped inner layer 5 has an internal thread 6, into which a pressure cover 7 is screwed.
  • GGG 40 spherulitic cast iron
  • a corrosion protection layer 8 made of high-alloy austenitic nodular cast iron is cast around the inner layer 5.
  • This cast material which provides protection against corrosion, is an austenitic nodular cast iron with a max. 3% C, 13 to 36% Ni and lower alloy components of Si, Cu and Cr.
  • Such a material is GGGNiCr 20.2 (trade name: "Ni-resist").
  • the corrosion protection coating 8 has a welding lip 9 which is concentric with the receiving opening 4.
  • a corrosion protection cover 11 made of the same material is inserted into the receiving opening 4 and connected to the welding lip 9 of the casing 8 via a counter welding lip 12.
  • the outer layer 13 of the container body consists of cast iron with spheroidal graphite (GGG 40).
  • a shielding cover 14 made of spherulitic cast iron is screwed to the outer cast body 13.
  • the respective cup-shaped casting layer was inserted as a molded part in the casting mold during the manufacturing process of the next outer layer. After the material melt of the next layer has been poured in, the surface connects to the cast layer. The three layers of the container body 3 are thus firmly connected.
  • the corrosion protection cover 11 is made of the same material as the corrosion protection layer 8. A subsequent heat treatment of the container after the cover is welded is therefore not necessary.
  • the inner layer 21 is formed from a drawn steel tube, which is welded at the end opposite the receiving opening 4 by a circular steel plate 23.
  • Drawn steel pipes have a higher mechanical strength than corresponding cast bodies. Therefore, the inner layer 21 of the container body 3 can be made thinner. The result of this is that the central corrosion protection layer 8 is of a smaller diameter.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Other Surface Treatments For Metallic Materials (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)
  • Secondary Cells (AREA)
  • Devices For Use In Laboratory Experiments (AREA)
  • Thermally Insulated Containers For Foods (AREA)
  • Laminated Bodies (AREA)
EP83102908A 1982-04-22 1983-03-24 Behälter zur Aufnahme von radioaktiven Stoffen Expired EP0092679B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19823214880 DE3214880A1 (de) 1982-04-22 1982-04-22 Behaelter zur aufnahme von radioaktiven stoffen
DE3214880 1982-04-22

Publications (2)

Publication Number Publication Date
EP0092679A1 EP0092679A1 (de) 1983-11-02
EP0092679B1 true EP0092679B1 (de) 1986-01-29

Family

ID=6161574

Family Applications (1)

Application Number Title Priority Date Filing Date
EP83102908A Expired EP0092679B1 (de) 1982-04-22 1983-03-24 Behälter zur Aufnahme von radioaktiven Stoffen

Country Status (7)

Country Link
US (1) US4569818A (es)
EP (1) EP0092679B1 (es)
JP (1) JPS58190798A (es)
BR (1) BR8302011A (es)
CA (1) CA1189203A (es)
DE (2) DE3214880A1 (es)
ES (1) ES8405189A1 (es)

Families Citing this family (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60158399A (ja) * 1984-01-09 1985-08-19 ウエスチングハウス　エレクトリック　コ−ポレ−ション 鋳鉄製容器
DE3445124C1 (de) * 1984-12-11 1986-01-23 Nukem Gmbh, 6450 Hanau Auskleidung fuer Bohrloecher in Salzstoecken
DE3447278A1 (de) * 1984-12-22 1986-06-26 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Langzeitbestaendige korrosionsschutzumhuellung fuer dicht verschlossene gebinde mit hochradioaktivem inhalt
US4700863A (en) * 1986-01-09 1987-10-20 The United States Of America As Represented By The United States Department Of Energy Seal welded cast iron nuclear waste container
DE3610862A1 (de) * 1986-04-01 1987-10-08 Kernforschungsz Karlsruhe Laengszylindrischer behaelter fuer die endlagerung von einer oder mehreren mit hochradioaktiven abfaellen gefuellten kokillen
DE3632270A1 (de) * 1986-09-23 1988-04-07 Wiederaufarbeitung Von Kernbre Verfahren und vorrichtung zum beladen und verschliessen eines doppelbehaeltersystems fuer die lagerung von radioaktivem material sowie verschluss fuer das doppelbehaeltersystem
US4754894A (en) * 1987-05-11 1988-07-05 Centre Foundry & Machine Co. Waste container
US5337917A (en) * 1991-10-21 1994-08-16 Sandia Corporation Crash resistant container
DE4204527C2 (de) * 1992-02-15 1993-12-23 Siempelkamp Gmbh & Co Verfahren zum Herstellen eines Abschirm-Transportbehälters für bestrahlte Kernreaktorbrennelemente
AT398012B (de) * 1992-07-13 1994-08-25 Theodor Haering Behälter zum transport und zur endlagerung von atomaren brennstäben
US5442186A (en) * 1993-12-07 1995-08-15 Troxler Electronic Laboratories, Inc. Radioactive source re-encapsulation including scored outer jacket
US6891179B2 (en) * 2002-10-25 2005-05-10 Agilent Technologies, Inc. Iron ore composite material and method for manufacturing radiation shielding enclosure
NO20044434D0 (no) * 2004-10-19 2004-10-19 Nuclear Prot Products As Lang-tids lagringscontainer og fremgangsmate for fremstilling av denne
NO336476B1 (no) 2009-03-11 2015-09-07 Mezonic As En fremgangsmåte og et anlegg for produksjon av en lagringsbeholder for å lagring av nukleærstrålings-materiale
CN102708933B (zh) * 2012-06-06 2014-09-03 清华大学 乏燃料贮存竖井屏蔽井盖及其提升装置
US10020084B2 (en) 2013-03-14 2018-07-10 Energysolutions, Llc System and method for processing spent nuclear fuel
CN111739672B (zh) * 2020-05-13 2023-12-22 中国核电工程有限公司 一种降低氚渗透速率的结构

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0083024A1 (de) * 1981-12-21 1983-07-06 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Behälter zum Langzeitlagern von bestrahlten Kernreaktorbrennelementen

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1005196A (en) * 1962-07-27 1965-09-22 Nuclear Power Plant Co Ltd Radiation shielding material
GB1073751A (en) * 1964-03-13 1967-06-28 Atomic Energy Authority Uk Improvements in or relating to containers for transporting radioactive and/or fissile materials
FR2258692A1 (en) * 1974-01-23 1975-08-18 Transnucleaire Package for nuclear fuel elements - particularly for transport prior to reprocessing
US4031921A (en) * 1975-09-09 1977-06-28 The United States Of America As Represented By The United States Energy Research And Development Administration Hydrogen-isotope permeation barrier
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
DE7737499U1 (de) * 1977-12-09 1978-05-24 Steag Kernenergie Gmbh, 4300 Essen Abschirmtransport- und/oder abschirmlagerbehaelter fuer radioaktive abfaelle
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
DE2942092C2 (de) * 1979-10-18 1985-01-17 Steag Kernenergie Gmbh, 4300 Essen Endlagerbehälter für radioaktive Abfallstoffe, insbesondere bestrahlte Kernreaktorbrennelemente

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0083024A1 (de) * 1981-12-21 1983-07-06 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Behälter zum Langzeitlagern von bestrahlten Kernreaktorbrennelementen

Also Published As

Publication number Publication date
US4569818A (en) 1986-02-11
BR8302011A (pt) 1983-12-27
DE3214880A1 (de) 1983-10-27
ES522024A0 (es) 1984-05-16
EP0092679A1 (de) 1983-11-02
DE3361958D1 (en) 1986-03-13
CA1189203A (en) 1985-06-18
JPH0437398B2 (es) 1992-06-19
JPS58190798A (ja) 1983-11-07
ES8405189A1 (es) 1984-05-16

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