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EP0081660B1 - Formkörper zur Einbindung von abgebrannten Kernbrennstoffstäben und Verfahren zu seiner Herstellung - Google Patents

Formkörper zur Einbindung von abgebrannten Kernbrennstoffstäben und Verfahren zu seiner Herstellung Download PDF

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Publication number
EP0081660B1
EP0081660B1 EP82109826A EP82109826A EP0081660B1 EP 0081660 B1 EP0081660 B1 EP 0081660B1 EP 82109826 A EP82109826 A EP 82109826A EP 82109826 A EP82109826 A EP 82109826A EP 0081660 B1 EP0081660 B1 EP 0081660B1
Authority
EP
European Patent Office
Prior art keywords
nuclear fuel
rods
moulding
fuel rods
moulding according
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
EP82109826A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0081660A1 (de
Inventor
Karl Gerhard Dr. Dipl.-Chem. Hackstein
Milan Dr. Dipl.-Ing. Hrovat
Hans Dr. Dipl.-Chem. Huschka
Lothar Rachor
Thomas Dr. Dipl.-Chem. Schmidt-Hansberg
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
Nukem GmbH
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 EP0081660A1 publication Critical patent/EP0081660A1/de
Application granted granted Critical
Publication of EP0081660B1 publication Critical patent/EP0081660B1/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
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • G21F9/36—Disposal of solid waste by packaging; by baling

Definitions

  • the invention relates to a cylindrical or polygonal shaped body made of graphite and nickel sulfide for the safe long-term integration of spent nuclear fuel rods in their original shape or deformed shape and a method for producing such shaped bodies.
  • Spent fuel elements from nuclear reactors have to be disposed of for a final disposal after a certain period of time.
  • Two ways were investigated worldwide, namely the reprocessing of the fuel elements with the return of the fuels to the fuel element production as well as the separation and final storage of the fission products (highly active waste) and alternatively the direct final storage of the spent fuel elements.
  • highly active waste is generated, which must be safely stored in suitable geological formations for 1,000 years or more.
  • DE-A-2818781 describes a method for the environmentally safe storage of spent nuclear fuel rods, in which the nuclear fuel rods are bent and the packages thus obtained are placed in a protective container.
  • the nuclear fuel rods are preferably U-shaped or deformed into a wound roll. This method has the disadvantage that containers are required and the heat dissipation from the nuclear fuel rods to the outside is relatively poor.
  • the molded body contains anchor plates in the head and foot area and in the core fuel rod-free zones inside parallel to the main axis of the molded body in the anchor plates attached metal rods.
  • metal rods with a macroscopically rough surface in order to improve the mechanical bond between the graphite / nickel sulfide matrix and the rods.
  • the shaped body contains the nickel sulfide predominantly in the form of Ni 3 S 2 . This further increases the resistance to corrosion and leaching.
  • the moldings generally contain 10 to 75% by weight of graphite and 25-90% by weight of nickel sulfide, preferably at least 80% thereof in the form of Ni 3 S 2 as the matrix material.
  • the moldings according to the invention have an extraordinarily high mechanical integrity, so that the requirements specified by the repository are completely met.
  • These moldings are preferably produced by first inserting a matrix powder of graphite, nickel and sulfur into a die, then an anchor plate with attached metal rods, then deformed or undeformed nuclear fuel rods together with matrix powder, another anchor plate with attached metal rods and finally again matrix powder is introduced and pressed at temperatures above 100 ° C, the matrix being pre-compressed in the area of the stored nuclear fuel rods before pressing and the metal rods being attached to the anchor plates only in areas above or below which there are no nuclear fuel rods.
  • the pressing is advantageously carried out at temperatures between 400 and 500 ° C.
  • the anchor plates are pressed in such a way that the metal rods slide past one another within the core and edge regions free of nuclear fuel during compression and anchor themselves in the hardening matrix.
  • the mechanical integrity of the shaped body - in particular in the case of tensile and bending stress - is significantly increased, so that it is possible to incorporate the nuclear fuel rods in any shape (e.g. wound, kinked or in original dimensions).
  • the nuclear fuel rods are advantageously deformed into disk-shaped spirals, with a central region of preferably. Leaves 80 mm diameter free. In the production of these fuel rod spirals, it has proven to be advantageous to keep the winding spacing ⁇ 6 mm.
  • the compression ratios of the matrix in the areas containing and free of nuclear fuel are matched to one another in such a way that the residual formability is the same in both areas. This makes it possible to achieve a uniform integral density over the entire length of the molded body.
  • the method according to the invention advantageously also allows individual fuel rod spirals to be incorporated into the graphite-nickel sulfide matrix.
  • Such disks can be stacked on top of each other in a container suitable for final storage, so that they can be easily retrieved or also be stored for final storage as required.
  • the discs can be provided with a central gripping hole for easier retrievability.
  • contaminated nuclear fuel rod casings can also be integrated in this way.
  • Figure 1 shows schematically a shaped body according to the invention in an exemplary embodiment in longitudinal section
  • Figure 2 shows a nuclear fuel rod in spiral form.
  • the molded body contains in the head area (2) and in the foot area (3) an anchor plate (1), on which metal rods (4) are fastened, and only on the areas of the anchor plates (1) between which there are none when pressing the molded body Nuclear fuel rods (5) are located.
  • the nuclear fuel rods (5) are therefore preferably deformed into disc-shaped spirals (6) with a rod-free center (7), so that the metal rods (4) can also be arranged in the center in addition to the outer region of the shaped body.
  • a mixture of 43.7% by weight of finely powdered natural graphite, 15% by weight of finely ground sulfur and 41.3% by weight of nickel metal powder was prepared as the starting powder for the matrix by dry mixing.
  • the nuclear fuel rods had an inner diameter of 8 mm and were filled with sintered U0 2 pellets with a density of 10.4 g / cm 3 .
  • the individual nuclear fuel rods are inserted into suitable steel tubes and these are sealed on both sides.
  • the nuclear fuel rods clamped at one end were wound up with the aid of a suitable device to form spirals with a maximum outer winding spacing of .6 mm and a diameter of approximately 260 mm.
  • a layer of matrix powder was poured into a steel matrix with a diameter of 300 mm, this was cold pre-compressed and an anchor plate with 5 metal rods (3 on the periphery, 2 on the inside) was placed on it. Another - 10 mm thick - matrix powder layer was applied to the anchor plate.
  • a nuclear fuel rod spiral was placed thereon and then matrix powder was filled in at a height which corresponded approximately to the layer thickness of a nuclear fuel rod spiral. In the center and in the edge area of the spiral, the matrix powder content was increased by approx. 30% by additional pre-compression.
  • a further 39 spirals were arranged one above the other in layers in accordance with the working step described.
  • the second anchor plate with staggered metal rods was inserted. Additional matrix powder was filled in above this anchor plate - equivalent to the amount that was filled in at the beginning of the process.
  • the final pressing was carried out with a pressure of 50 MN / m 2 .
  • the temperature was raised to 450 ° C. with continued pressure. After cooling to 300 ° C, the molded body was ejected.
  • the matrix powder was prepared analogously to Example 1. Encapsulated approximately 5 m long Nuclear fuel rods were bent 20 times so that the width was 450 mm-250 mm at a height.
  • the kinked fuel rods were integrated in a square matrix. After filling in the first matrix powder layer and the anchor plate with 2 external metal rods, 6 kinked nuclear fuel rods were arranged and the space was filled with matrix powder. After inserting the second anchor plate with staggered metal rods, this was overlaid with matrix powder - equivalent to the amount that was filled in at the beginning of the process.
  • the matrix properties of the finished molded article correspond to the properties of the molded article described in Example 1.

Landscapes

  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Powder Metallurgy (AREA)
  • Piles And Underground Anchors (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Sealing Material Composition (AREA)
  • Press Drives And Press Lines (AREA)
EP82109826A 1981-11-11 1982-10-23 Formkörper zur Einbindung von abgebrannten Kernbrennstoffstäben und Verfahren zu seiner Herstellung Expired EP0081660B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3144755 1981-11-11
DE3144755A DE3144755C2 (de) 1981-11-11 1981-11-11 Formkörper zur Einbindung von abgebrannten Kernbrennstoffstäben und Verfahren zu seiner Herstellung

Publications (2)

Publication Number Publication Date
EP0081660A1 EP0081660A1 (de) 1983-06-22
EP0081660B1 true EP0081660B1 (de) 1985-02-20

Family

ID=6146108

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82109826A Expired EP0081660B1 (de) 1981-11-11 1982-10-23 Formkörper zur Einbindung von abgebrannten Kernbrennstoffstäben und Verfahren zu seiner Herstellung

Country Status (6)

Country Link
EP (1) EP0081660B1 (es)
JP (1) JPS5888698A (es)
BR (1) BR8206478A (es)
DE (2) DE3144755C2 (es)
ES (2) ES268417Y (es)
FI (1) FI74836C (es)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3344525A1 (de) * 1983-12-09 1985-06-20 Kernforschungsanlage Jülich GmbH, 5170 Jülich Verfahren zur lagerung abgebrannter brennelemente
JPS6145298A (ja) * 1984-08-09 1986-03-05 カシオ計算機株式会社 電子楽器
DE3532155C1 (en) * 1985-09-10 1987-02-19 Kernforschungsanlage Juelich Ultimately disposable bundle and method for producing it
AT385435B (de) * 1986-03-07 1988-03-25 Oesterr Forsch Seibersdorf Verfahren und vorrichtung zum einbetten und gegebenenfalls ausreagieren von insbesondere toxischen und/oder radioaktiven stoffen bzw. abfaellen
DE19700651C1 (de) * 1997-01-10 1998-09-03 Siemens Ag Verdichtung zu entsorgender Steuer- und Absorberelemente aus Leichtwasser-Reaktoren
DE102009044963B4 (de) * 2008-11-10 2011-06-22 ALD Vacuum Technologies GmbH, 63450 Blöcke aus Graphit-Matrix mit anorganischem Bindemittel geeignet zur Lagerung von radioaktiven Abfällen und Verfahren zur Herstellung derselben
ES2530463T3 (es) 2008-11-10 2015-03-03 Ald Vacuum Techn Gmbh Material de matriz a base de grafito y aglutinantes inorgánicos adecuado para el almacenamiento definitivo de residuos radiactivos, procedimiento para su preparación, su elaboración y uso
US8502009B2 (en) 2008-11-26 2013-08-06 Ald Vacuum Technologies Gmbh Matrix material comprising graphite and an inorganic binder suited for final disposal of radioactive waste, a process for producing the same and its processing and use
RU2403633C1 (ru) * 2009-07-27 2010-11-10 Открытое акционерное общество "Российский концерн по производству электрической и тепловой энергии на атомных станциях" (ОАО "Концерн Росэнергоатом") Способ хранения отработавшего ядерного топлива
DE102010003289B4 (de) * 2010-03-25 2017-08-24 Ald Vacuum Technologies Gmbh Gebinde zur Lagerung von radioaktiven Abfällen und Verfahren zu seiner Herstellung

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2375695A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour le traitement de dechets radioactifs
SE413712B (sv) * 1977-05-10 1980-06-16 Asea Ab Sett att innesluta anvenda kernbrenslestavar i en skyddsbehallare for deponering
DE2846845A1 (de) * 1978-10-27 1980-05-08 Battelle Institut E V Verfahren zur endlagerung radioaktiver spaltprodukte
DE2917437C2 (de) * 1979-04-28 1983-11-17 Nukem Gmbh, 6450 Hanau Verahren zum Einbinden von radioaktiven und toxischen Abfällen
DE2942092C2 (de) * 1979-10-18 1985-01-17 Steag Kernenergie Gmbh, 4300 Essen Endlagerbehälter für radioaktive Abfallstoffe, insbesondere bestrahlte Kernreaktorbrennelemente

Also Published As

Publication number Publication date
DE3144755A1 (de) 1983-05-26
DE3144755C2 (de) 1984-06-28
ES8402671A1 (es) 1984-02-01
EP0081660A1 (de) 1983-06-22
BR8206478A (pt) 1983-09-27
FI74836B (fi) 1987-11-30
JPS5888698A (ja) 1983-05-26
FI823335A0 (fi) 1982-09-29
DE3262446D1 (en) 1985-03-28
FI823335L (fi) 1983-05-12
FI74836C (fi) 1988-03-10
ES268417Y (es) 1983-12-01
ES268417U (es) 1983-05-16
ES517238A0 (es) 1984-02-01

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