EP0028670A1 - Procédé de préparation de corps formés contenant des déchets de haute radioactivité - Google Patents

Procédé de préparation de corps formés contenant des déchets de haute radioactivité Download PDF

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Publication number
EP0028670A1
EP0028670A1 EP19800102963 EP80102963A EP0028670A1 EP 0028670 A1 EP0028670 A1 EP 0028670A1 EP 19800102963 EP19800102963 EP 19800102963 EP 80102963 A EP80102963 A EP 80102963A EP 0028670 A1 EP0028670 A1 EP 0028670A1
Authority
EP
European Patent Office
Prior art keywords
glass
ceramic
mpa
pressure
sintered
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
EP19800102963
Other languages
German (de)
English (en)
Other versions
EP0028670B1 (fr
Inventor
Gerhard Dr. Ondracek
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.)
Forschungszentrum Karlsruhe GmbH
Original Assignee
Kernforschungszentrum Karlsruhe 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 Kernforschungszentrum Karlsruhe GmbH filed Critical Kernforschungszentrum Karlsruhe GmbH
Publication of EP0028670A1 publication Critical patent/EP0028670A1/fr
Application granted granted Critical
Publication of EP0028670B1 publication Critical patent/EP0028670B1/fr
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
    • G21F9/30—Processing
    • G21F9/301—Processing by fixation in stable solid media
    • G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
    • 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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
    • 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
    • G21F9/30—Processing
    • G21F9/301—Processing by fixation in stable solid media
    • G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
    • G21F9/305—Glass or glass like matrix

Definitions

  • the invention relates to a method for producing molded articles containing highly radioactive waste materials, in which the waste materials are embedded in a glass, glass ceramic or ceramic matrix.
  • the glass state is an imbalance state, crystallization can be expected with long-term storage. According to previous knowledge, this begins with the macroscopically inhomogeneously distributed, heterogeneous inclusions, which act as nuclei. Crystallized areas with chemically different composition and fine structure are formed, which are arranged macroscopically inhomogeneous in the remaining glass phase. The highly active fission products are - in varying amounts - mainly concentrated in the crystallized areas. Because of their different composition and structure, these have different coefficients of thermal expansion, which leads to mechanical stresses in a glass block during final storage. In particular, the macroscopically inhomogeneous distribution of the different crystal areas, ultimately based on the macroscopically inhomogeneous distribution of the heterogeneous inclusions, increases the risk of cracking and brittle fracture in the glass block.
  • the object of the invention is to provide improved solidification products made of highly radioactive waste and a glass, glass ceramic or ceramic matrix in their properties, in which a homogeneous distribution of the incorporated waste is ensured both during production and during long-term storage. It is a further object of the invention to: •) (DE-OS 26 57 265)
  • the object is also achieved in a different way, namely in that the waste materials are first melted in a known manner into a glass, glass ceramic or ceramic matrix, then mechanically comminuted or ground, the comminuted material or the ground material mixed and pressed at a pressure in the range of 5o MPa to 5oo MPa and then sintered below the melting range of the matrix in the devitrification area or pressure sintered in the range of lo to 5o MPa.
  • the sludge which contains the waste materials and is thickened with glass, glass ceramic or ceramic powder, is compressed in the slip casting prior to drying.
  • According to the invention is sintered at a temperature in the range of 5oo K to 8 00 K or pressure sintered.
  • the first solution also offers the advantage that the glass or glass ceramic / ceramic waste mixture does not have to be melted, the processing temperatures can therefore be reduced to about two thirds of the temperatures required by melting technology, viscosity-related flow problems are avoided and crucible Reactions and signs of segregation of the heterogeneous inclusions (segregation, inhomogeneous distribution) are reduced. In addition, the evaporation of highly active components, which was previously unavoidable when melting, is greatly reduced.
  • radioactive powder can be introduced into the end products solidified by the process according to the invention.
  • a simulated, denitrified waste solution of the following composition was prepared with inactive components:
  • this solution was evaporated to dryness and the residue was ground to a particle size of on average lo to 50 ⁇ m (waste powder).
  • powder fractions can also be used, but powder fractions that are too finely ground will not be used in order to rule out dust formation as far as possible.
  • Example 1 For the production of blocks having a diameter of 2 mm 0 o and 15o mm height by means of cold isostatic pressing in a flexible container, which is for isostatic molding condition, was first described in Example 1, Method. The powder mixture was pressed at a pressure of about 5oo MPa. Thereafter the compacts were lo to 15 hours at 00 6 8 00 K to K sintered and then tempered. The desired macroscopic homogeneity was also achieved with these samples. The density was about 95% of the melt density.
  • Example 1 The waste described in Example 1 and glass powder mixture was filled in a graphite mold with graphite stamp and without a preceding continuous cold pressing with simultaneous task a pressure of from lo to 4o MPa at about 6 00 K (indirect heating) hot pressing or pressure-sintered.
  • a treatment time of 10 minutes was sufficient for the blocks with a diameter of 20 mm and a height of 25 mm.
  • a density of 97% of the solid density on the blocks and the desired macroscopic homogeneity were found.

Landscapes

  • Chemical & Material Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)
  • Compositions Of Oxide Ceramics (AREA)
EP19800102963 1979-11-08 1980-05-28 Procédé de préparation de corps formés contenant des déchets de haute radioactivité Expired EP0028670B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE2945006 1979-11-08
DE19792945006 DE2945006A1 (de) 1979-11-08 1979-11-08 Verfahren zur herstellung von hochradioaktive abfallstoffe enthaltenden formkoerpern

Publications (2)

Publication Number Publication Date
EP0028670A1 true EP0028670A1 (fr) 1981-05-20
EP0028670B1 EP0028670B1 (fr) 1983-09-28

Family

ID=6085400

Family Applications (1)

Application Number Title Priority Date Filing Date
EP19800102963 Expired EP0028670B1 (fr) 1979-11-08 1980-05-28 Procédé de préparation de corps formés contenant des déchets de haute radioactivité

Country Status (4)

Country Link
EP (1) EP0028670B1 (fr)
JP (1) JPS5682499A (fr)
BR (1) BR8007001A (fr)
DE (1) DE2945006A1 (fr)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2525381A1 (fr) * 1982-04-17 1983-10-21 Kernforschungsz Karlsruhe Procede pour le perfectionnement des proprietes necessaires pour un stockage de longue duree de dechets radioactifs solidifies
EP0136401A2 (fr) * 1983-05-30 1985-04-10 Hitachi, Ltd. Méthode et appareil pour traiter une résine de rebut
EP0156001A2 (fr) * 1983-12-01 1985-10-02 Forschungszentrum Jülich Gmbh Procédé pour conditionner les déchets contaminés par enrobage dans le ciment
US4855082A (en) * 1983-09-09 1989-08-08 Willy De Roode Process for rendering harmless dangerous chemical waste
WO2018152290A1 (fr) * 2017-02-16 2018-08-23 GeoRoc International, Inc. Composition et procédé pour le traitement de boues dangereuses et de milieux d'échange d'ions

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4778626A (en) * 1985-11-04 1988-10-18 Australian Nat'l Univ. of Acton Preparation of particulate radioactive waste mixtures

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3000072A (en) * 1959-08-20 1961-09-19 Ca Atomic Energy Ltd Process of containing and fixing fission products
DE2534014A1 (de) * 1975-07-30 1977-02-17 Kernforschung Gmbh Ges Fuer Thermodynamisch stabiles glaskeramikprodukt oder glaskeramikaehnliches produkt zur endgueltigen beseitigung hochradioaktiver abfaelle
DE2747951A1 (de) * 1976-11-02 1978-05-11 Asea Ab Verfahren zur bindung radioaktiver stoffe in einem koerper, der gegen auslaugen durch wasser bestaendig ist

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2627265A1 (de) * 1976-06-18 1977-12-29 Krauss Maffei Ag Mehrstufige gegenstrom-wasch- dekantierzentrifuge
FR2375695A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour le traitement de dechets radioactifs

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3000072A (en) * 1959-08-20 1961-09-19 Ca Atomic Energy Ltd Process of containing and fixing fission products
DE2534014A1 (de) * 1975-07-30 1977-02-17 Kernforschung Gmbh Ges Fuer Thermodynamisch stabiles glaskeramikprodukt oder glaskeramikaehnliches produkt zur endgueltigen beseitigung hochradioaktiver abfaelle
US4097401A (en) * 1975-07-30 1978-06-27 Gesellschaft Fur Kernforschung M.B.H. Thermodynamically stable product for permanent storage and disposal of highly radioactive liquid wastes
DE2747951A1 (de) * 1976-11-02 1978-05-11 Asea Ab Verfahren zur bindung radioaktiver stoffe in einem koerper, der gegen auslaugen durch wasser bestaendig ist
FR2369659A1 (fr) * 1976-11-02 1978-05-26 Asea Ab Pr

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2525381A1 (fr) * 1982-04-17 1983-10-21 Kernforschungsz Karlsruhe Procede pour le perfectionnement des proprietes necessaires pour un stockage de longue duree de dechets radioactifs solidifies
GB2121232A (en) * 1982-04-17 1983-12-14 Kernforschungsz Karlsruhe Method for solidifying radioactive wastes
EP0136401A2 (fr) * 1983-05-30 1985-04-10 Hitachi, Ltd. Méthode et appareil pour traiter une résine de rebut
EP0136401A3 (en) * 1983-05-30 1986-03-26 Hitachi, Ltd. Method and apparatus for processing radioactive waste resin
US4855082A (en) * 1983-09-09 1989-08-08 Willy De Roode Process for rendering harmless dangerous chemical waste
EP0156001A2 (fr) * 1983-12-01 1985-10-02 Forschungszentrum Jülich Gmbh Procédé pour conditionner les déchets contaminés par enrobage dans le ciment
EP0156001A3 (en) * 1983-12-01 1986-10-15 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Process for conditioning contaminated waste by coating with cement
WO2018152290A1 (fr) * 2017-02-16 2018-08-23 GeoRoc International, Inc. Composition et procédé pour le traitement de boues dangereuses et de milieux d'échange d'ions
CN110291593A (zh) * 2017-02-16 2019-09-27 乔罗克国际股份有限公司 用于处理有害污泥和离子交换介质的组合物和方法
CN110291593B (zh) * 2017-02-16 2024-04-16 乔罗克国际股份有限公司 用于处理有害污泥和离子交换介质的组合物和方法

Also Published As

Publication number Publication date
BR8007001A (pt) 1981-05-12
JPS5682499A (en) 1981-07-06
EP0028670B1 (fr) 1983-09-28
DE2945006C2 (fr) 1987-01-15
DE2945006A1 (de) 1981-05-21

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