EP0104398A1 - Trockenlagerbüchse für abgebrannte Kernreaktorbrennelemente - Google Patents

Trockenlagerbüchse für abgebrannte Kernreaktorbrennelemente Download PDF

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Publication number
EP0104398A1
EP0104398A1 EP83108054A EP83108054A EP0104398A1 EP 0104398 A1 EP0104398 A1 EP 0104398A1 EP 83108054 A EP83108054 A EP 83108054A EP 83108054 A EP83108054 A EP 83108054A EP 0104398 A1 EP0104398 A1 EP 0104398A1
Authority
EP
European Patent Office
Prior art keywords
dry storage
lid
storage container
container body
fuel elements
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.)
Withdrawn
Application number
EP83108054A
Other languages
German (de)
English (en)
French (fr)
Inventor
Franz-Wolfgang Dr. Popp
Heinz Scharbach
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
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 filed Critical Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Publication of EP0104398A1 publication Critical patent/EP0104398A1/de
Withdrawn legal-status Critical Current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 dry storage bushing made of steel for the intermediate storage of spent nuclear reactor fuel elements, which has a coating of ceramic or enamel on the outer surface and / or inner surface and which is closed by a welded-on lid.
  • Spent nuclear reactor fuel elements are stored in a decay basin in the nuclear reactor plant in transport containers and brought to an interim storage facility.
  • the spent nuclear fuel elements are stored in these intermediate storage facilities until they are reprocessed.
  • the delivered nuclear reactor fuel elements are unloaded from the transport container, which is used for further transports after decontamination.
  • the unloaded nuclear reactor fuel elements are enclosed in steel dry storage sleeves. It is common to stack these dry storage bushings in air-cooled storage rooms.
  • the highly radioactive fission product inventory enclosed with the spent fuel elements also has the hydrogen isotope tritium. All hydrogen isotopes have a high permeability. The permeation of tritium through the metal wall is therefore a problem, which arises in particular when spent fuel is temporarily stored. It becomes essential tritium held by the cladding tubes of the fuel assemblies. A small amount of tritium can still permeate through the cladding tubes and through the steel can wall.
  • D E -OS 28 04 282 In order to reduce the permeation to almost no longer recordable values, it is already known (D E -OS 28 04 282) to provide the outer surface of the dry bearing bush with an aluminum layer or an oxidic surface protection layer. These layers retain the tritium from the fuel assemblies.
  • ceramic surface layers would have the essential advantage that they make simple and good decontamination of the dry bearing bush possible because their surface is extremely smooth.
  • a ceramic surface protection layer thus fulfills the requirements of easy decontamination and at the same time represents a very good permeation barrier against hydrogen.
  • the sealing cap After loading the dry storage bushing, the sealing cap must be welded onto the open end of the container body.
  • the ceramic coating must be kept at a certain distance from the weld, since the heat development during welding would otherwise damage the coating. By keeping clear of the can closure, however, an annular zone is created that is not covered by ceramics and is without the desirable permeation barrier.
  • the invention has for its object to provide a dry bearing bush of the type described above, in which the cavity of the bush body is better covered.
  • the inventive design of the dry bearing bushing means that the uncoated area of the weld seam is made up of the surrounding area Limitation of the cavity of the dry bearing bush moved out.
  • the outer or inner coating of the dry-bearing bushing can now expansion of the cavity of thekowskila g erbüchse cover.
  • the dry bearing bushing and the sealing cover are welded at a point outside the outline of the cavity of the dry bearing bushing.
  • the small circular joint opening of the hollow body, which is formed by the two welding lips, is due to its thickness, which is determined by the length of the welding lip of the sealing cap, also a good barrier and of considerably less extent than a weld seam placed in the outline of the sleeve cavity Closure cap would represent.
  • the invention provides a dry bearing bush with a ceramic coating, which covers the entire sleeve cavity and in which the dry bearing bush can still be closed by welding.
  • a dry storage bushing consists of a closure cover 1 and a container body 2, which are welded together. Both parts are made of steel.
  • the dry storage bushing takes up spent nuclear reactor fuel elements, not shown here.
  • the outer surface of the container body 2 is provided with a ceramic layer 3, which was produced by enamelling or plasma spraying. The surface of this ceramic layer 3 is very smooth and facilitates the decontamination of the dry bearing bush. Another advantage is that this layer forms a permeation barrier for the tritium.
  • the ceramic layer 3 covers the bottom 7 of the dry bearing bush.
  • the ceramic layer 3 is applied to the jacket of the dry bearing bushing except for a short annular end region.
  • the vertical lid edge 4 forms a welding lip, which can be welded to the end of the container body 2, which is uncoated and represents a welding lip 5.
  • the end of the lid edge 4 ends with the end of the container body 2.
  • the closure lid 1 also has a ceramic coating 6 on its disk-shaped outer surface delimited by the lid edge 4.
  • a cavity 8 is closed in the dry storage bushing.
  • This cavity 8 is formed by the bottom 7 of the container body 2, the inner surface of the disk-shaped closure cover 1 and the inner cylinder wall of the container body 2.
  • This cavity 8 is almost completely covered by a ceramic outer coating on the dry bearing bush.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Closures For Containers (AREA)
  • Rigid Containers With Two Or More Constituent Elements (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
EP83108054A 1982-08-26 1983-08-16 Trockenlagerbüchse für abgebrannte Kernreaktorbrennelemente Withdrawn EP0104398A1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3231747 1982-08-26
DE19823231747 DE3231747A1 (de) 1982-08-26 1982-08-26 Trockenlagerbuechse fuer abgebrannte kernreaktorbrennelemente

Publications (1)

Publication Number Publication Date
EP0104398A1 true EP0104398A1 (de) 1984-04-04

Family

ID=6171737

Family Applications (1)

Application Number Title Priority Date Filing Date
EP83108054A Withdrawn EP0104398A1 (de) 1982-08-26 1983-08-16 Trockenlagerbüchse für abgebrannte Kernreaktorbrennelemente

Country Status (4)

Country Link
EP (1) EP0104398A1 (ja)
JP (1) JPS5954999A (ja)
BR (1) BR8304570A (ja)
DE (1) DE3231747A1 (ja)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6771628B1 (en) 1999-12-20 2004-08-03 Telefonaktiebolaget Lm Ericsson (Publ) Method and apparatus for evaluating a timeslot in a TDMA signal

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2575319B1 (fr) * 1984-12-21 1987-03-20 Sgn Soc Gen Tech Nouvelle Procede d'emballage etanche de conteneur renfermant des matieres toxiques
FR2943166B1 (fr) * 2009-03-11 2012-10-05 Commissariat Energie Atomique Etui de stockage de combustible nucleaire usage a fermeture facilitee.

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3645703A (en) * 1966-07-28 1972-02-29 Hittman Associates Inc Helium permeable containers
FR2462768A1 (fr) * 1979-07-31 1981-02-13 Nukem Gmbh Recipient destine a contenir et a stocker des dechets radioactifs brules
EP0061067A1 (de) * 1981-03-20 1982-09-29 Asea Ab Verfahren zum Einschliessen verbrauchter Brennstäbe eines Kernreaktors in einem Behälter aus Kupfer
EP0082467A1 (de) * 1981-12-17 1983-06-29 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Behälter für die Langzeitlagerung von abgebrannten Kernreaktorbrennelementen

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3645703A (en) * 1966-07-28 1972-02-29 Hittman Associates Inc Helium permeable containers
FR2462768A1 (fr) * 1979-07-31 1981-02-13 Nukem Gmbh Recipient destine a contenir et a stocker des dechets radioactifs brules
EP0061067A1 (de) * 1981-03-20 1982-09-29 Asea Ab Verfahren zum Einschliessen verbrauchter Brennstäbe eines Kernreaktors in einem Behälter aus Kupfer
EP0082467A1 (de) * 1981-12-17 1983-06-29 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Behälter für die Langzeitlagerung von abgebrannten Kernreaktorbrennelementen

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6771628B1 (en) 1999-12-20 2004-08-03 Telefonaktiebolaget Lm Ericsson (Publ) Method and apparatus for evaluating a timeslot in a TDMA signal

Also Published As

Publication number Publication date
JPS5954999A (ja) 1984-03-29
BR8304570A (pt) 1984-04-03
DE3231747A1 (de) 1984-03-01

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PUAI Public reference made under article 153(3) epc to a published international application that has entered the european phase

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AK Designated contracting states

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18W Application withdrawn

Withdrawal date: 19840530

RIN1 Information on inventor provided before grant (corrected)

Inventor name: SCHARBACH, HEINZ

Inventor name: POPP, FRANZ-WOLFGANG, DR.